ML19210D674
| ML19210D674 | |
| Person / Time | |
|---|---|
| Site: | Shoreham File:Long Island Lighting Company icon.png |
| Issue date: | 11/19/1979 |
| From: | Novarro J LONG ISLAND LIGHTING CO. |
| To: | Harold Denton Office of Nuclear Reactor Regulation |
| References | |
| SNRC-448, NUDOCS 7911270444 | |
| Download: ML19210D674 (4) | |
Text
.s LONG ISLAND LIGHTING COMPANY 7 FLt'O
_Mwam SHOREHAM NUCLEAR POWER STATION P.O. BOX 618, NORTH COUNTRY ROAD + WADING RIVER, N.Y.11792 November 19, 1979 SNRC-448 Mr. Harold R.
Denton, Director Office of duclear Reactor Regulation U.
S. Nuclear Regulatory Commission Washington, D. C.
20555 SHOREHAM NUCLEAR POWER STATION - UNIT 1 DOCKET NO. 50-322
Dear Mr. Denton:
Mr.
S.
A.
Varga's letter of October 9, 1979, requested that LILCO, along with other Mark II Owners, embrace the generic positions on the Mark II Suppression Pool Dynamic Loads Program wherever feasible in order to minimize both NRC and utility manpower requirements, and to expedite the completion of the NRC review of the Mark II program.
Mr. Varga's letter also requested specific definitions of any areas which might require " plant specific" positions by LILCO.
The Mark II program has divided the Mark II containment plants into a " Lead Plant" group and a " Follow-On" plant group.
The Shoreham station, a member of the Lead Plant group alonc t'ith the Zimmer and LaSalle Stations, has employed a Jargely,ineric approach to the resolution of the Mark II suppression pool loads.
In fact, Shoreham has accepted what we believe to be overly conservative load specifications in some areas in order to expeditd resolution of the overall program.
In a great ma'ny cases, the NRC Acceptance Criteria, as defined in NUREG-0487, has been applied to our plant "as is".
In other cases the Lead Plants have presented generic alternative positions which we believe are acceptable to the NRC Staff on the basis of technical meetings held on these subjects.
In a few instances, plant-unique load specifications have been required because of physical differences between the units and/or particular calculational techniques being employed.
Such information has been provided to the NRC Staff for evaluation as required.
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In summary, the Mark II lead plants have been employing, and will continue to employ, a largely generic approach to the resolution of the Mark II Suppression Pool Dynamic Loads Program.
In addition, we have adopted the NRC Staff Accept-ance Criteria verbatim wherever feasible.
To illustrate this point, Attachment 1 shows a listing of the major Mark II Lead Plant open items which were discussed in our letter SNRC-362 dated March 5, 1979 and updated here to reflect their current status.
An can be scen from this list, the generic approach has been extensively employed.
We believe that we are apprcaching a final resolution of the Mark II lead plant program with the NRC Staff and that we have already submitted all information required.
If there is any additional information required by the Staff in order to complete their review of the Mark II issue on the Shoreham docket, we request that you inform us of these as soon as possible.
Very truly yours, y
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[ P.0cVnRR V
v J.
P.
- Novarro, Project Manager Shoreham Nuclear Power Station WJM/cc Attachment cc:
Messrs.
S. A. Varga J. Higgins 1398 090
3/5/79 (SNRC-362) Sii0 R Ell AM POSITION UPDATED To 11/01/79 FOR MK II NRC ACCEPTANCE CRITERIA LEAD PLANT S110REll AM NRC OPEN ITEM 2/9/79 SIIO REll AM POSITION CENERIC
_pdIQUE COMMENTS 1.
Pool Swell Elevation Question Response X
Submitted 2/16/79 via SNRC-360 020.68.
for Shoreham-Acceptable to NRC per 9/13/79 ACRS Meeting.
2.
Small Structure Impact Comply with NRC X
Loads criteria.
3.
Asymmetric Pool Swell Comply with current X
Current NRC position uses twice Loads NRC position.
10% of maximum bubble pressure applied to 1/2 of submerged boundary per G.E.
letter of 3/16/79.
4.
Submerged Boundary Alternate position.
X Agree to 24 psi below vent exit Loads During Vent plane per G.E.
3/20/79 letter -
Clearing Acceptable to NRC 9/13/79.
5.
LOCA/SRV Submerged Comply with NRC X
Ring vortex model relegated to Drag Loads criteria.
MK II follow-on plant program.
a,b LOCA Water Jet c.
Lift Coefficient
)
Alternate position X
Documentation submitted on d.
Sensitivity Studies)
LaSalle Docket DAR Appendix C, e.
Interference Effect)
Rev. 6 of 10/79.
f.
Zone of Influence Alternate position X
Using 5 ft radius cylinder; Quencher Water Jet Susquehanna DAR Section 3.0 shows no water jet effect at a distance less than this.
6.
SRV Bubble Phasing Alternate position X
Documentation provided by 7.
and Frequency Shoreham letter submitted SNRC-374 of 3/30/79. S&L 12/13 presentation showed equivalence tg of lead plant approach to NRC so request.
Acceptable to NRC.
CO CD
~O LEAD PLANT S110REllAM NRC OPEN ! TEM 2/9/79 S110REllAM POSITION GENERIC UNIQUE COMMENTS 8.
Chugging FSI Effects NRC request X
Ongoing task in MK II Program acceptable.
as part of improved chugging load definition A.16.
Shoreham evaluation for structures showed FSI insignificant.
9.
Load Case 10 Alternate position X
Baseil on 7/26/79 G.E. presentation, letter report 10/19/79 - acceptable to NRC if documentation accepted.
M 4
CO CD G
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