ML17324B271
| ML17324B271 | |
| Person / Time | |
|---|---|
| Site: | Cook  |
| Issue date: | 03/06/1987 |
| From: | Wigginton D Office of Nuclear Reactor Regulation |
| To: | Dolan J AMERICAN ELECTRIC POWER SERVICE CORP., INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG |
| References | |
| NUDOCS 8703110118 | |
| Download: ML17324B271 (5) | |
Text
Docket Nos.:
50-315 and 50-316 MAR 06 $87 Mr. John Dolan, Vice President Indiana and Michigan Electric Company c/o American Electric Power Service Corporation 1 Riverside Plaza
- Columbus, Ohio 43216
Dear Mr. Dolan:
During the review of the Indiana and Michigan Electric Company submittal dated July 30,
- 1986, on the relief valve and safety valve testing, we have identified two areas where additional information is needed.
The attached questions were developed by our contractor and pertain to verification of the REPIPE code and stresses on pipe supports in a faulted condition.
It is requested that IMEC provide the information or identify the submittal if the information has been provided.
If there are any questions on this matter, please let us know.
Sincerely, Dave L. Wigginton, Project Manager PWR Project Directorate ¹4 Division of PWR Licensing-A
Enclosures:
As stated cc:
See next page DISTRIBUTION:
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UNITEDSTATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 f6AR 0 6 $87 Docket Nos.:
50-315 and 50-316 Mr. John Dolan, Yice President Indiana and Michigan Electric Company c/o American Electric Power Service Corporation 1 Riverside Plaza
- Columbus, Ohio 43216
Dear Mr. Dolan:
During the review o e
n i f th I d'ana and Michigan Electric Company submittal dated we have Ju y
, on 1
30 1986 the relief valve and safety valve testing, we identified two areas where additional information is nee e
d d.
The attached questions were eve ope y
d lo ed b
our contractor and pertain to verification of t e REPIPE code and stresses on pipe supports in a au e
con requested that
!MEC provide the information or identify the submitta
) t e information has been provided.
If there are any questions on this matter, please let us know.
Sincerely, ave L. Wi 'on, Project Manager PWR Project Directorate 0'4 Division of PWR Licensing-A
Enclosures:
As stated cc:
See next page
Mr. John Dolan Indiana and Michigan Electric Company Donald C.
Cook Nuclear Plant CC:
Mr. M. P. Alexich Vice President Nuclear Operations American Electric Power Service Corporation 1 Riverside Plaza
- Columbus, Ohio 43215 Attorney General Department of Attorney General 525 West Ottawa Street Lansing, Michigan 48913 Township Supervisor Lake Townshio Hall Post Office Box 818 Bridgeman, Michigan 49106 W.
G. Smith, Jr., Plant Manaaer Donald C.
Cook Nuclear Plant Post Office Box 458 Bridgman, Michigan 49106 U.S. Nuclear Regulatory Commission Resident Inspectors Office 7700 Red Arrow Highway Stevensville, Michigan 49127 Gerald Charnoff, Esquire Shaw, Pittman, Potts and Trowbridge 2300 N Street, N.W.
Washington, DC 20037 Mayor, City of Bridgeman Post Office Box 366 Bridgeman, Michigan 49106 Special Assistant to the Governor Room 1 - State Capitol i.ansing, Michigan 48909 Nuclear Facilities and Environmental Monitoring Section Office Division of Padiological Health Department of Public Health 3500 N. Logan Street Post Office Box 30035 Lansing, Michigan 48909 The Honorable John E. Grotberg United States House of Representatives Washington, DC 20515 Regional Administrator, Region 111 U.S.
Nuclear Regulatory Commission 799 Roosevelt Road Glen Ellyn, Illinois 60137 J. Feinstein American Electric Power Service Corooration 1 Riverside Plaza
- Columbus, Ohio 43216
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UNRESOLVED QUESTIONS ON D.C.
- COOK, UNITS 1
AND 2 1.
The licensee was previously requested to provide verification that the REPIPE program produces accurate fluid forces when used in conjunction with RELAP for discharge transients of the type occurring in a PWR overpressure protection system.
The licensee responded by stating that verification of REPIPE's capacity to generate force histories is provided by the Control Data Corporation.
This statement does not in itself provide evidence of verification for the program.
Therefore, provide a verification of this program by comparing calculated forces with measured forces from the EPRI test data or other similar verification.
2.
The licensee has provided load combinations that were used to evaluate adequacy of the piping and pipe supports for normal, upset, and emergency conditions.
The load combinations used for these three service conditions are in accordance with FSAR requirements and recommendations of the EPRI PWR Safet and Relief Valve Test Pro ram Guide for A lication of Valve Test Pro ram Results to Plant-S ecific Evaluations, July 1982.
The licensee submittals do not,
- however, provide a load combination for a faulted condition whereby loads for a worst case blowdown are combined with loads for a worst case seismic event.
Such a load combination is specified in the FSAR (Chapter 4, Section 4.3. 1) and in the EPRI Guide.
Based on the stress values presented in the Teledyne reports included in the licensee submittals, a load combination of Deadweight
+ Design
+
Safety Valve Discharge
< 2.4 Sh can be performed for pipe stresses and I
the resulting stresses for this faulted condition are acceptable.
The informati on supplied by the licensee,
- though, does not permit performing a similar load combination for a faulted condition on the pipe supports.
Therefore, determine an allowable stress for pipe support components for a faulted condition and perform a load combination such as Normal
+ Safety Valve Discharge in which the resulting stresses are compared to the established allowables.