ML20214J360
| ML20214J360 | |
| Person / Time | |
|---|---|
| Site: | Rancho Seco |
| Issue date: | 08/06/1986 |
| From: | Stolz J Office of Nuclear Reactor Regulation |
| To: | Julie Ward SACRAMENTO MUNICIPAL UTILITY DISTRICT |
| References | |
| TAC-61869, NUDOCS 8608140605 | |
| Download: ML20214J360 (3) | |
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b Ob August 6,1986 Docket No.'50-312 Mr. John E. Ward
' Assistant General Manager, Nuclear Sacramento Municipal Utility District 6201 S Street P. O. Box 15830 Sacramento, California-95813'
Dear Mr. Ward:
The enclosed request for additional information was compiled during our review of Proposed Technical Specification Amendment No. 148 which was submitted by the Sacramento Municipal Utility District on June 13, 1986.
We will need_a response to each item listed in the enclosure before we can complete our review of your proposed amendment.
The reporting and/or recordkeeping requirements contained in this letter affect fewer than ten respondents; therefore, OMB clearance is not required under P.L.96-511.
Sincerely, wmu. sic::a u JCC F SIOM$e" John F. Stolz, Director PWR Project Directorate #6 Division of PWR Licensing-B
Enclosure:
Request for Additional 4
Information cc w/ enclosure:
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- Q Mr. John E. Ward Rancho Seco Nuclear Generating Sacramento Municipal Utility District Station cc:
Mr. David S. Kaplan, Secretary Sacramento County and General Counsel Board of Supervisors Sacramento Municipal Utility 827 7th Street, Room 424 District Sacramento, California 95814 6201 S Street P. O. Box 15830 Ms. Helen Hubbard Sacramento, California 95813 P. O. Box 63 Sunol, California 94586 Thomas Baxter, Esq.
Shaw, Pittman, Potts & Trowbridge 1800 M Street, N.W.
l Washington, D.C.
20036 Mr. Ron Columbo Sacramento Municipal Utility District Rancho Seco Nuclear Generating Station 4440 Twin Cities Road Herald, California 95638-9799 Mr. Robert B. Borsum Babcock & Wilcox Nuclear Power Generation Division Suite 220, 7910 Woodmont Avenue
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Bethesda, Maryland 20814 Resident Inspector / Rancho Seco c/o V. S. N. R. C.
14410 Twin Cities Road Herald, California 95638 Regional Administrator, Region V U.S. Nuclear Regulatory Commission 1450 Maria Lane, Suite 210 Walnut Creek, California 94596 Director Energy Facilities Siting Division Energy Resources Conservation &
Development Commission 1516 - 9th Street Sacramento, California 95814 Mr. Joseph 0. Ward, Chief Radiological Health Branch State Department of Health Services 714 P Street, Office Building #8 Sacramento, California 95814
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REQUEST FOR ADDITIONAL INFORMATION RANCHO SEC0 NUCLEAR GENERATING STATION UNIT N0. 1 AUXILIARY FEEDWATER PUMP TESTING DURING POWER OPERATION (TAC 61869)
In your submittal dated June 13, 1986, you state that during power operation, in order to test the automatic start capability of an auxiliary feedwater (AFW) pump on loss of main feedwater flow, AFW system actuation is achieved by isolating the main feedwater pump discharge line pressure switch which pro-vides AFW pump auto start signal and bleeding off the pressure in the sensing line.
Provide the following additional information with respect to this proposal:
1.
Confirm that only one AFW pump is being tested at any given time during power operation.
2.
Describe the means provided to assure that the main feedwater discharge pressure switch root and drain valves are returned to their normal operating position after testing is completed.
In accordance with the criteria of Recommendation GS-6 of NUREG-0611 and -0635 which was implemented under Item II.E.1.1 of NUREG-0737, procedures should be provided which specify dual operator verification of proper valve position upon system restoration.
3.
Verify that performance of the AFW system actuation test at power will not result in adverse effects to the system.
Consideration should be given to assuring that the AFW discharge line chedk" valves will properly reseat and operation of the AFW pump with the steam generators at normal operating pressure will not result in pump damace (i.e., dead heading will not occur). Also confirm that the introduction of cold AFW flow at power will not result in a transient condition effecting plant operation.
4.
Evaluate the effects of the periodic thennal shock on the integrity of the steam generators including the shell, nozzles, and tubes which results when the relatively cold water is injected into the steam generator during the AFW system test with the plant at power.
Indicate the effect of the proposal on the thermal cycling design margins over the life of plant.
5.
Confirm that the proposed technical specification change will not preclude performance of the AFW system flow path verification test which is to be accomplished prior to startup after an extended cold shutdown (such as a refueling outage) as identified in Recommendation GS-6 of NUREG-0611 and
-0635.
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