ML20132C958
| ML20132C958 | |
| Person / Time | |
|---|---|
| Site: | Diablo Canyon  |
| Issue date: | 07/26/1985 |
| From: | Maneatis G PACIFIC GAS & ELECTRIC CO. |
| To: | Asselstine J, Bernthal F, Palladino N NRC COMMISSION (OCM) |
| References | |
| CON-#385-996 DCL-85-25, OL, NUDOCS 8509270207 | |
| Download: ML20132C958 (2) | |
Text
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._c PACIFIC OAS AND EI_.E C T RI C C O M PANY h
77 BEALE STREET
- SAN F R A N CISCO, C A LI FO R NI A 94106 GEORGE A. M AN EATIS esecunva vice eatssotmv July 26, 1985 uswic PGandE Letter ho.: DCL-M-25R 29 P4 :11
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Chairman Nunzio J. Palladino U. S. Nuclear Regulatory Commission BRANCH 1717 "H" Street, N.W.
Washington, D.C.
20555 Commissioner James K. Asselstine Commissioner Frederick M. Bernthal Commissioner Thomas M. Roberts Commissioner Lando W. Zech, Jr.
nL Re: Docket No. 50-323T OL-DPR-81
-Diablo Canyon Unit 2 Low Power Testing Schedule
Dear Mr. Chairman and Commissioners:
In our June 26, 1985, letter (DCL-85-227) requesting authority to operate Diablo Canyon Unit 2 above five percent power, we indicated that we expected to achieve initial criticality on July 27, 1985, and complete the low-power test program on August 6,1985. Unit 2 is presently in the initial heat-up cycle subsequent to fuel loading. The unit entered Mode 4 on July 19 and Made 3 on July 25, 1985.
The heat-up program has been slightly delayed due to some minor problems encountered during the scheduled startup tests and system
-walkdowns.
Interferences were encountered involving two pipe supports on the steam generator blowdown system. These interferences were resolved, making the piping system available for continued heat-up.
It was determined that these interferences were caused by the piping system responding differently than predicted by analysis.
An interference between steam generator 2-1 and 2-2 bumper block assemblies was encountered during heat-up. Plant heat-up was held to obtain measurements, calculate new gap requirements, and machine the bumper block faces. This work has been completed and heat-up resumed.
It has been determined that this was a construction problem limited tc these two steam generators.
8509270207 850726 PDR C0191S NRCC CDRRESPONDENCE PDR
,o Nunzio J. Palladino, Chairman, et al PGandE Letter No. DCL-85-250 July 26, 1985
.. Testing of an Emergency Core Cooling System (ECCS) check valve indicated leakage that was higher than the acceptance criterion.
Investigation revealed that one.of the ECCS check valve test valves was leaking past its seat, making it appear that the check valve under test was leaking. The test valve was exercised and the~ check valve was then successfully tested.
After review of the remaining activities, we now estimate that.
we will achieve initial criticality on August 6,-1985, and complete the low-power test program on August 16, 1985.
Kindly acknowledge receipt of this material on the enclosed copy of this letter and return it in the enclosed addressed envelope.
Sincerely,
/W cc:
H. R. Denton R. T. Dodds W. R. Johnson, Judge-J. B. Martin T. S. Moore, Judge H. E. Schierling Service List t
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