ML17255A807
| ML17255A807 | |
| Person / Time | |
|---|---|
| Site: | Ginna  |
| Issue date: | 05/03/1984 |
| From: | Kober R ROCHESTER GAS & ELECTRIC CORP. |
| To: | Crutchfield D Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 8405080005 | |
| Download: ML17255A807 (4) | |
Text
REOULATORHRNFORI1ATION DISTRISUTION Sl'EN (BIDS)
ACCESSION NBR:84050e0005 DOC.DATE; 84/05/03 t4OTARIZED:
NO DOCKET
'ACIL:50-244 Robert Emmet Ginna Nuclear,Planta Unit 1R Rochester G
05000?44 AUTH'AblE AUTHOR AFFIL'I ATION KOBERiR.N.
Rochester Gas 8 Electric Corp ~
RECIP ~ NAblE
'ECIPIENT AFFILIATION CRUTCHF IELDR D ~
Operating Reactors Branch 5
SUBJECT:
Responds to addi NRC questions re utjl program to achieve compliance l)/10CFR50RApp R.Adequate indication exists to achieve stable safe shutdowns DISTRIBUTION CODE:
AOOeS COPIES RECEIVED:LTR El4CL SIZE:
I TITLE:
OR Submittal: Fire Protection NOTES: NRR/DL/SKP 1 c Y ~
05000244 RECIPIENT ID CODE/NAblE NRR ORB5 Bc 01 INTERNAL: ELD/HDS4 IE/WHITNEYRR HAbiBACH NRR/DL DIR RGN1 COP IKS LTTR ENCL 1
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AHO t iiiiiiiIJlJlJ~iJiiiiiiiiiiii ROCHESTER GAS AND HEv L 4W ~ 0% I ~ 0 ELECTRIC CORPORATION o 89 EAST AVENUE, ROCHESTER, N.Y. 'f4649-0001 ROGER W. KOBER VlCE PRESIDENT ELZCTRlC&STEAM PRODUCTION TSl.SPHONC AREA CODS Tld 546 2700 May 3, 1984 Director of Nuclear Reactor Regulation Attention:
Mr. Dennis M. Crutchfield, Chief Operating Reactors Branch No.
5 U.S. Nuclear Regulatory Commission Washington, D.C.
20555
Subject:
Appendix R
R.
E. Ginna Nuclear Power Plant Docket No. 50-244
Dear Mr. Crutchfield:
This letter addresses additional questions raised by members of the NRC staff while reviewing our previous submittals (most recently April 27, 1984) regarding RGEE's program to achieve compliance with 10 CFR Part 50 Appendix R. It can be postulated that following a fire inside containment at a specific location removed from high temperature
- lines, separated from reactor coolant pump lubricating oil and in a low traffic area near several transmitters and electrical penetrations, that redundant circuits for pressurizer level and reactor coolant system pressure could be damaged.
However, actions can be taken to compensate for the loss of these circuits following the specific postulated fire such that safe shutdown can be achieved.
A reactor coolant system pressure indicator is available at the Post Accident Sampling System (PASS) panel outside containment.
Although not normally in
- service, the indicator can be aligned to the reactor coolant system by opening remotely operated valves outside containment and by remotely opening an air-operated valve (AOV) from the B loop inside containment or, should the AOV be inoperable, by manually aligning three small valves from the A loop inside containment but away from the fire area.
Pressurizer level indication, per se, is not necessary following this postulated fire.
Pressurizer level can be inferred from charging and letdown flow, normal pressurizer response to reactor shutdown and chemical and volume control system inventories.
Therefore, adequate indication exists to achieve stable safe shutdown.
er truly yours,
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