ML18082B191
| ML18082B191 | |
| Person / Time | |
|---|---|
| Site: | Salem  |
| Issue date: | 09/11/1980 |
| From: | Mittl R Public Service Enterprise Group |
| To: | Miraglia F Office of Nuclear Reactor Regulation |
| References | |
| IEB-79-07, IEB-79-14, IEB-79-7, NUDOCS 8009180455 | |
| Download: ML18082B191 (4) | |
Text
e PS~G Public Service Electric and Gas Company 80 Park Plaza Newark, N.J. 07101 Phone 201/430-7000 September 11, 1980 Director of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, D.C.
20555 Attention:
Mr. Frank J. Miraglia, Chief Licensing Branch 3 Division of Licensing Gentlemen:
SUMMARY
OF SEISMIC STRESS ANALYSIS NRC BULLETIN 79-07 NO. 2 UNIT SALEM NUCLEAR GENERATING STATION DOCKET NO. 50-311 PSE&G hereby submits, in the enclosure to this letter, a summary of the seismic stress analysis of safety related piping and resultant modifications in response to the subject bulletin.
Should you have any questions in this regard, do not hesi-tate to contact us.
Enclosure HS3 The Energy People 8f:)09180 HS5 Very truly yours,
- /~}(/
R. L. Mittl General Manager -
Licensing and Environment Engineering and Construction p
95-0942
NRC BULLETIN 79-07 SEISMIC STRESS ANALYSIS OF SAFETY RELATED PIPING SALEM GENERATING STATION NO. 2 UNIT DOCKET NO. 50-311
SUMMARY
AND CONCLUSIONS Initial responses (F. w. Schneider to B. H. Grier) dated May 3, 1979 and June 18, 1979 provided our position with respect to seismic analyses performed for piping systems on Salem 2, and the reevaluation performed on the Residual Heat Removal System.
This evaluation was comprised of various piping sizes and configurations and demonstrated that no overstressed piping exists on Salem 2.
Subsequently, in letters dated July 23, 1979 (O. D. Parr to R. L. Mittl) and August 7, 1979 (R. L. Mittl to o. D. Parr, PSE&G agreed to reevaluate the safety related piping essen-tial to the safe shutdown of the plant.
This reevaluation of pipe stresses and supports, based on current standards, has been completed and the necessary modifications as a result of this reanalysis have been implemented.
The re-evaluation was performed subsequent to verification of "as built" piping with piping isometric drawings.
The stresses and modification types are identified separately in this report.
It is our contention that the requirements of NRC Bulletins 79-07 and 79-14 have been met and that this reevaluation assures the capability for safe shutdown in the event of a design basis seismic event.
SYSTEMS, PIPE STRESSES AND SUPPORTS The 15 safety-related systems that encompass the total scope of the evaluation are listed below.
These systems are those required for safe shutdown of the plant.
The total pipe stress calculations and supports reevaluated are as follows:
System
- 1.
- 2.
- 3.
- 4.
- 5.
- 6.
- 7.
- 8.
- 9.
- 10.
- 11.
- 12.
- 13.
- 14.
- 15.
)
Safety Injection
)
)
Component Cooling
)
)
)
)
)
Chilled Water
)
Chemical and Voll.IDle Control
)
Control Air
)
Diesel Oil
)
Steam Gen. Drains and Blowdown)
Spent Fuel Coolinq
)
) Total Pipe Stress
'Ibtal Calculations Pipe Suports 1077 5755 EVALUATION OF STRESSES AND SUPPORTS The reevaluation of pipe stresses was performed in accord-ance with the criteria previously submitted to the NRC as part of the responses for Salem 1.
The results indicated there are no overstressed pipes.
The reanalysis method used to determine pipe support capa-bilities was based on seismic loads resulting from the three-dimensional square-root-sum-of-the-squares method.
This was performed in accordance with procedures submitted to the NRC as part of the responses for Salem 1.
The. re-analysis resulted in certain modifications of supports.
SUMMARY
OF PIPE STRESS EVALUATION AND SUPPORT MODIFICATIONS The reanalysis of pipe stresses in the 15 safety-related systems indicated no overstressed conditions.
However, the pipe supports within those stress calculations resulted in modifications as summarized below.
Pipe Stresses Pipe Supports
- Modifications Reactor Contairment Balance of Plant 345 1803 300 (A)
(Penetration Areas arrl Auxiliary Building) 732 3952 693 (B)
">Q '
\\"' Total modifications as a result of this reanalysis are 993 (A+B).
These modifications have been completed.
The majority of the modifications were of the U-bolt and strap anchor types.
These were basically calculated to function as a six-way restraint and the pipe stress calcula-tions were performed considering these conditions.
- However, when individual hanger details were being designed, fabri-cated and installed, they did not fulfill the requirements of a rigid anchor as was calculated for pipe stresses.
Hence, theoretically, they did not function as was origi-nally intended.
These U-bolt type anchors and strap anchors were redesigned to comply with the original intended func-tions.
9/11/80 M PBO 92 08 1/3