ML20205F789
| ML20205F789 | |
| Person / Time | |
|---|---|
| Site: | Fort Saint Vrain  |
| Issue date: | 03/25/1987 |
| From: | Brey H PUBLIC SERVICE CO. OF COLORADO |
| To: | Berkow H NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM), Office of Nuclear Reactor Regulation |
| References | |
| P-87120, TAC-63029, NUDOCS 8703310293 | |
| Download: ML20205F789 (2) | |
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2420 W. 26th Avenue, Suite 1000, Denver, Colorado 80211 March 25, 1987 Fort St. Vrain Unit No. 1 P-87120 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D.C.
20555 Attention: Mr. H. N. Berkow, Director Standardization and Special Pro,jects Directorate Docket No. 50-267
SUBJECT:
Standby Diesel Generator Surveillance
REFERENCE:
PSC letter, Williams to Berkow, dated 9/24/86 (P-86549)
Dear Mr. Berkow:
This letter is to confirm that PSC normally loads each Standby Diesel Generator at Fort St. Vrain to approximately the full load rating during weekly testing.
This information was previously discussed during a telephone conversation with Mssrs. K. Heitner and I.
Ahmed on March 18, 1987.
In the referenced letter, PSC requested NRO approval of a proposed change to FSV Technical Specification SR 5.6.1.
This proposed change involved extending the frequency of Loss of Offsite Power testing from once per six months to once per refueling, not to exceed 18 months.
Diesel auto-start capability on simulated loss of bus voltage was proposed at approximately six month intervals.
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.; "..~o P-87120 Page 2 March 25, 1987 During the NRC's review of this proposed change, a concern was raised 1
about the frequency of full load testing of the Standby Diesel Generators, since the weekly - test requirement of SR 5.6.1.a only specifies loading to at least 50%. As a matter of good practice, PSC applies a load of at least 1200 kw during this two-hour run test.
j This practice is specified in PSC's written surveillance procedure 1
and is essentially a full load test since the continous load rating of each diesel generator set is 1210 kw.
l If you have any questions about this information, please contact Mr.
M. H. Holmes at (303) 480-6960.
Very truly yours,-
k, i
H. L. Brey, Manager j
Nuclear Licer. sing and 2
Fuels i
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HLB /SWC/ paw i
cc:
Regional Administrator, Region IV ATTN: Mr. J. E. Gagliardo, Chief Reactor Projects Branch i
l Mr. Robert Farrell l
Senior Resident Inspector Fort St. Vrain 1
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