Headquarters Daily Report OCTOBER 10, 1997 *************************************************************************** REPORT NEGATIVE NO INPUT ATTACHED INPUT RECEIVED RECEIVED HEADQUARTERS û REGION I û REGION II û REGION III û REGION IV û PRIORITY ATTENTION REQUIRED MORNING REPORT - HEADQUARTERS OCTOBER 10, 1997 MR Number: H-97-0126 NRR DAILY REPORT ITEM GENERIC COMMUNICATIONS NRC Information Notice 97-77, "Exemptions From the Requirements of Section 70.24 of Title 10 of The Code of Federal Regulations," dated October 10, 1997. The NRC is issuing this information notice to inform addressees about actions the staff plans to take regarding enforcement actions and the granting of exemptions from the requirements of Section 70.24 of Title 10 of the Code of Federal Regulations (10 CFR 70.24). Technical contact: G. Wunder, NRR 301-415-1494 _ REGION III MORNING REPORT PAGE 2 OCTOBER 10, 1997 Licensee/Facility: Notification: Commonwealth Edison Co. MR Number: 3-97-0102 Byron 1 Date: 10/09/97 Byron,Illinois LICENSEE VIA ENS & RI VIA PHONE &PC Dockets: 50-454 PWR/W-4-LP Subject: REACTOR SHUTDOWN REQUIRED BY TECHNICAL SPECIFICATIONS Discussion: On October 10, 1997, at 4:48 a.m. (CDT), Unit 1 completed a shutdown required by Technical Specifications and entered Mode 3 (Hot Standby.) During an ECCS venting surveillance on 10/9/97, the licensee identified that a Reactor Coolant System Pressure Isolation Valve (1SI8819C, SI Cold Leg Check Valve) was leaking. The licensee calculated that the leak rate was approximately 5 GPM at 7:14 p.m. on 10/9/97. Technical Specification 3.4.6.2.f allowed a maximum of 1 GPM leakage with RCS pressure at 2235 psig. Action C required the leak rate to be reduced within 4 hours or be in hot standby within the next 6 hours and in cold shutdown within the following 30 hours. The licensee was unable to reduce the leak rate and began the shut down at 10:08 p.m. on 10/9/97. The licensee identified the excessive leakage after a safety injection system venting surveillance indicated more gas coming out of solution than normally expected. Also, during the SI cold leg injection header venting, the 1C safety injection accumulator level dropped, indicating back leakage through the SI cold leg check valve and the source of the water was the 1C SI accumulator. No additional leakage from the Reactor Coolant System was identified. Currently the licensee is formulating repair plans. Regional Action: The resident inspector observed the shutdown and will monitor repairs of the check valve and the subsequent startup. Contact: T. M. TONGUE (630)829-9613 _