ML19305C956
| ML19305C956 | |
| Person / Time | |
|---|---|
| Issue date: | 03/31/1980 |
| From: | Reid R Office of Nuclear Reactor Regulation |
| To: | Gammill W Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 8004110481 | |
| Download: ML19305C956 (3) | |
Text
{{#Wiki_filter:.-- pusc o q(o UNITED STATES [( g g NUCLEAR REGULATORY COMMISSION 5 c C WASHINGTON, D. C. 20555 o, 8 March 31, 1980 /
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MEMORANDUM FOR: William P. Gammill, Acting Assistant Director for Operating Reactor Projects, DDR FROM: Robert W. Reid, Chief, Operating Reactors Branch #4, D0R
SUBJECT:
FORTHCOMING MEETING WITH B&W AND B&W OWNERS GROUP Time & Date: 9:30 am, Thursday April $,1980 i Location: P-ll8, Phillips Building t Bethesda, Maryland
Purpose:
To discuss B&W Reactor Response and Vulnerability of Task Force Report
Participants:
NRC R. Capra, R. Tedesco, T. Novak et al UTILITIES B&W, B&W Licensees O)i k I. bc -:- ,L a Nobert W. Reid, Chief Operating Reactors Branch #4 Division of Operating Reactors
Enclosure:
Cross-Reference Listing of Reconmendations cc w/ enclosure: See last page of this memo gooMlod
Enclosure ' TABLE 2-1 CROSS-REFERENCE LISTING 0F RECOMENDATIONS .R:comendation Number TMI-2 Numb'r Subject in Report Page Action Plan 1. AFW system upgrade to safety-grade. 5.2.6.3(1) II.E.1 2. Signal selection for automatic initiation of AFW. 5.2.6.3(2) II.E.1 Automatic control and interlock for overcooling and overfill protection. 3. Addition of motor-driven AFW pump for Davis-Besse. 5.2.6.3(4) II.E.1 4. OTSG high level trip of MFW and/or AFW. II.E.1 5. Total independance between AFW and ICS. II.E.1 6. Modifications to steam line break detection and 5.2.7.3(1) II.E.1 mitigation system. 7. Improvements in plant control system (ICS/NNI). 5.3.5.l(1) I.D.1 8. Selected data set of principal plant parameters 5.3.5.l(2) I.D.2 for operator. 9. Incore thermocouple input to subcooling meter. 5.3.5.1(3) I.D.1 10. Continuous or trending display for incore thermo-5.4.4.(7) I.D.1 couples. 11. High radiation signal initiation of containment 5.3.5.1(4) II.E.4.2 isolation. 12. System response to maintain pressurizer level on 5.2.1.2(1) II.E.5 scale and pressure above HPI setpoint. 13. Alternative solution to PORY unreliability/ safety 5.2.3.3(3) II.K.3 system challenge rate concerns. Table C3-(2) 14a. Continued evaluation of need to trip RCPs during 5.2.4.2(1) II.K.3 small break loss-of-coolant accidents. TableC3-(5) 14b. Evaluation of RCP restart criteria. 5.2.4.2(1) II.K.1 Table Cl-(27) 15. Mandatory one week simulator training for oper-5.4.4(1) I.A.3 ators as part of requalification program. 16. Guidelines for loss of NNI/ICS 5.4.4(2) I.C.1 17. Operator training on Crystal River 3 event. 5.4.4(3) I.C.5 18. Modifications to eliminate manual actions as 5.4.4(4) II.E.5 part of immediate operator response to transients. 19. Qualified I&C Technician on duty. 5.4.4(6) 1.A.l.3 20. IREP Crystal River Study. 6.3(1) II.C.1 l 21. Reevaluate location of AFW injection into OTSG 5.2.3.3(1) II.E.1 l i 22. Generic review of transients and accidents 5.2.3.3(2) I.C.1 23. PAS report on improvements in capability of PWRs 5.2.6.3(3) II.C.2 to cope with transient initiated accidents. 24. Staff study of personnel related LERs with re-5.4.4(5) 1.C.5 l spect to high number for B&W plants. l 2-10
MEETING NOTICE DISTRIBUTION ORB #4 "~.:.::.. Docket File W. Gammill NRC PDR L. Shao L PDR J. Miller, D0R
== ORB #4 Rdg P. T. Kuo (seismic reviews only) NRR Rdg H. Gaut, State Programs [q H. Denton AE0D E. G. Case D. Eisenhut R. Vollmer a W. Russell I.'. B. Grimes [I.. T. J. Carter A. Schwencer [;.}. D. Ziemann T. Ippolito = R. Reid V. Noonan P. Check G. Lainas G. Knighton Project Managers-ORB #4 ~ OELD OI&E(3) Ej OSD i"- S. Showe, I&E (PWR) R. Ingram ~ Receptionist, Bethesda R. Fraley, ACRS (16) Program Support Branch TERA g R. Buchanan Meeting Notice File NPI Participants RCapra TNovak RTedesco COPIES OF MEMO ALSO SENT TO ALL MEMBERS OF SACRAMENTO MUNICIPAL UTILITY DISTRICT (RANCHO SECO) AND METROPOLITAN EDIS0N COMPANY (TMI) SERVICE LISTS. = '#1.l g; ^ .;=.
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