ML17264A162
| ML17264A162 | |
| Person / Time | |
|---|---|
| Site: | Ginna  |
| Issue date: | 09/20/1995 |
| From: | Mecredy R ROCHESTER GAS & ELECTRIC CORP. |
| To: | Andrea Johnson NRC (Affiliation Not Assigned), NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| TAC-M90036, NUDOCS 9509260255 | |
| Download: ML17264A162 (3) | |
Text
PRZORXTY 1 (ACCELERATED RZDS PROCESSING)
REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)
ACCESSION NBR:9509260255 DOC.DATE: 95/09/20 NOTARIZED: NO DOCKET FACIL:50-244 Robert Emmet Ginna Nuclear Plant, Unit 1, Rochester G
05000244 P
AUTH.NAME AUTHOR AFFILIATION MECREDY,R.C.
Rochester Gas 6 Electric Corp.
RECIP.NAME RECIPIENT AFFILIATION R
JOHNSON,A.R.
SUBJECT:
Submits addi info re environ gulification of neutron flux instrumentation.
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'OCHESTER GASANDELECTR1C CORPORAVON ~ 89 EASTAVENUE, ROCHESTER, N.Y. 1ddd9-0001 AREA CODE716 546-2700 ROBERT C. MECREDY Vice President Nvcteor Operotions September 20, 1995 U.S. Nuclear Regulatory Commission Document Control Desk Attn:
Allen R. Johnson Project Directorate I-1 Washington, D.C.
20555
Subject:
Supplemental Submittal Regarding Neutron Flux Instrumentation (TAC No. M90036)
R.E.
Ginna Nuclear Power Plant Docket No. 50-244 Ref.(a):
Letter from Robert C. Mecredy, RG&E, to Allen R. Johnson,
- NRC, "Use of Neutron Flux Instrumentation During Post-Accident Severe Accident Conditions," February 3,
1995
Dear Mr. Johnson:
As a result of NRC staff review of information submitted in Reference (a),
a conference call was held between Rochester Gas and Electric and NRC staff on June 30, 1995.
During that call, the NRC staff discussed additional information needed to conclude that environmental qualification of neutron flux instrumentation is not necessary.
Accordingly, we are providing the following information which we believe satisfies the remaining staff concern regarding this issue:
Concern:
Ensure that, in the event of an accident resulting in a harsh containment environment (for which source range neutron flux is not environmentally qualified),
- boration, as required to mitigate the accident, is being delivered to the core.
Response
RG&E agrees that. boric acid injection is required in such circumstances.
Our plant design provides for the automatic initiation of the engineered safety features (including boric acid addition via the safety injection pumps) upon receipt of an adverse containment signal of 4 psig.
A review of our Emergency Operating Procedures (EOP's) indicates that actions are presently specified to direct the operator to restore safety injection.if initiation is not obtained.
For postulated accidents where the RCS is not depressurized below the shutoff head of the safety injection pumps, the operator is directed to align boric acid injection using the charging pumps.
We believe that our current arrangement of EOPs and Critical Safety io Function Status Trees, allowing for optimal recovery procedures to 95092b0255 950'st20 PDR ADOCK 05000244 P
PDR Ark> r8'PH&18@j
be 'exercised prior to reliance on Functional Restoration Procedures (FRs),
combined with timely use of appropriate FRs as
- needed, provides the actions needed to address. the NRC's concern.
Even though we believe that the current procedures acceptably address the NRC's concern, we are emphasizing this issue, including a caution to the operators to not rely on neutron flux during a
harsh environment condition, in our latest operator requalification training cycle session, which began on August 8, 1995.
Very truly yours, Robert C. Mecred GJW4388 Attachment xc: Mr. Allen R. Johnson (Mail Stop 14B2)
Project Directorate I-1 Washington, D.C.
20555 U.S. Nuclear Regulatory Commission Region I 475 Allendale Road King of Prussia, PA 19406 Ginna Senior Resident Inspector