ML20235J221
| ML20235J221 | |
| Person / Time | |
|---|---|
| Site: | Grand Gulf  |
| Issue date: | 09/04/1987 |
| From: | Taylor J BROOKHAVEN NATIONAL LABORATORY |
| To: | Jape F NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| Shared Package | |
| ML20235J225 | List: |
| References | |
| CON-FIN-A-3453 NUDOCS 8710010357 | |
| Download: ML20235J221 (2) | |
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' BROOKHAVEN NATIONAL L BORATORY?
QQl ASSOCIATED UNIVERSITIES, INCl 87 SEP28 mIO: 15 o
Upton, Long Island, New. York 11973 L l:[<
'(516) 282s-
' Department of Nuclear Energy FTS 666/
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7005
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L Building'130 j
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. September 4,11987 1j W. Frank" Jape' h
L' U.S. Nuclear Regulatory Commission
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Region II-101 Marietta Street; N.W.
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Atlanta, Georgia.-30303'
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Reft Grand Gulf Nuclear Station. Unit 1 Probabilistic Risk Assessment--
Based System Inspection Plans - Draft Copy - FIN A-3453 BNL Technical ' Report A-3453-87-5, Rev. O, Advance Copy _
Dear Frank:
-We have received your comments and observations regarding the above refer-ence, which we mailed.to you with our.May 8, 1937 cover letter.' ' Enclosed is an.
advance copy of the report, which we have designated Rev. O.
The, majority of the clarifications, corrections, deletions and additions have'been, incorporated into this report. There are some items which we feel require. additional discus-sion, and have outlined them below:
1.
Battery Charger CHRIC5: this charger is available to supply DC power to bas DCl25-llDC. PRAs look beyor.d toch spec requirements and evaluate capabil--
ity of equipment to mitigate accidents. To this extent charger C5 was con-siderad in the evaluation.
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2.
Trending for wear on CRD mechanisms:
trending for wear of control rod j
drives as a result of maintenance activities can be a useful: monitoring _
f tool. This is BNL's recommendation; it need not be implemented.
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3.
SSW drawings: drawings from the system description for Grand. Gulf have l
been substituted. 'The drawings'in the report are generally from the FRA, and only those loads deemed important by the PRA in mitigating-accidents were analyzed and depicted in the drawings.
4.
Inspection items with limited or restricted availability:
.a special" table 1
,1 has. been prepared for inspection of the risk'significant -items which are -
located in containment /drywell. These items can be inspected.during-refueling outages.
5.
ADS drawing: Figure IV-5.6.1:.does show valves F051K 'and F051F with the correct. designations, although the print is not cicar.
Plant drawing,
M-1077C Rev. 21,;"P&lD - Nuclear Boiler. System"-agrees with the schematic arrangement of Fig. IV-5.6.1.
The figures in the BNL document are extract-ed from the PRA and are intended to give the reader a general' overview of system layout, and should not be used for any other purpose.-
p, h OFFICIAE. COP %
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Frank Jape 7/17/87 l
i 6.
Condensate unavailability for backup if an isolation has occurred:
We believe Failure Mode No. 2, "Operstor Fails to Restore Instrument. Air" in-Table B2-1 addresses this concern.
Also,:in a conversation with Tony.
Fresco on August 14, 1987, you and Rudy Bernhardt agreed that you will verify the licensee's capability to utilize this system as a low pressure injection source by opening up feedwater startup valve AVS13.
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7.
LPCI Loop C items'in the walkdown table:
the presence of a CSS Actuation 1
Signal renders Loops A & B unavailable for LPCI, this action pushes the Loop C failure modes to:the top of the importance values.. Th'is table has now been combined with the other RHR modes (CSS, SDC, and SDC) such that the walkdowns now reflect items from Loops A, B, and C.
8.
LPCS-F001:
according to System Operating Instructions 04-1-01-E21-1, Rev.
21 (12/18/86), desired switch position is "Open" and desired valve position is "Open."
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Please be aware that in addition to the changes precipitated by your let-l ter, EPS and ADS walkdowns have been completed and tables for operations, sur-
.j veillance and calibration, and maintenance inspection guidance have been added j
to the document.
The description of dominant accident sequences has also been.
i expanded.
We are forwarding selected portions of your comments.to the PRA authors at Sandia National Laboratories under. separate cover, a copy of which will be sent
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to you.
We hope we have addressed your concerns regarding our first draft for Grand
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Gulf. We appreciate the effort reflected in your letter, finding it the best response received to date regarding the PRA-based system inspection plants.
Very truly yours,
/4 N /C m ]'
I JU:af Jbhn H. Taylo6 roup Lee. der Encl.
,/ Plant Systems and Equipment Analysis cc R. Bari R. Barrett, NRC A. Fresco R. Ihl1 B. Hillman, NRC W. Kato J. Usher File
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