ML20207E589
| ML20207E589 | |
| Person / Time | |
|---|---|
| Site: | Hope Creek  |
| Issue date: | 12/18/1986 |
| From: | Corbin McNeil Public Service Enterprise Group |
| To: | Murley T NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| References | |
| NLR-N86200, NUDOCS 8701020220 | |
| Download: ML20207E589 (3) | |
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Public Service Electric and Gas Company Corbin A. McNeill, Jr.
Public Service Electric and Gas Company P.O. Box 236, Hancocks Bridge, NJ 08038 609 339-4800 Vice President -
December 18, 1986 NLR-N86200 1
United States Nuclear Regulatory Commission Region I 631 Park Avenue King of Prussia, PA 19406 Attention:
Dr. Thomas E.
- Murley, Regional Administrator Gentlemen:
CORRECTIONS TO AUGMENTED INSPECTION REPORT NO. 50-354/86-50 e
HOPE CREEK GENERATING STATION As requested by your letter dated October 31, 1986, transmitting y 4
the subject report, please find below our comments regarding the
^
accuracy of the factual content and the conclusions drawn in the f.
re por t.
>[
1.
Page 5, paragraph A.2 - Revise first sentence to read as follows:
"Upon restoration of plant systems, after the hot loss of offsite power test, erroneous status indications were r
provided to the operator for circulating water valve HV-2152D and pumps CP501 and DP501."
2.
Page 6, top paragraph - Revise first sentence to read as follows:
" Pump start-enable indicating lights on the main i
control board were not illuminated even though both pumps were started upon completion of the test."
i 3.
Page 15, paragraph D.8 - Revise second sentence to read as follows:
"An observer noted that the valves were open, and an operator visually confirmed that the dump had occurred at which time he manually re-closed the valves."
4 4.
Page 21, paragraph F.1 - Revise paragraph to read as follows:
"During the hot loss of offsite power test, it was noted that operating procedure OP-SO-BD-001C (Q) did not describe the sequence of operations needed to switch the reactor core isolation cooling system from its pressure control mode (recirculation to and from the condensate storage tank) to 4
its water level control mode (direct injection into the i
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.e Dr. Thomas E.
Murley 2
12-18-86 reactor vessel) and vice versa.
During system preoperational tests, this particular procedure had not been used.
The control room operators were able to effect the mode transfer.
Subsequently, step-by-step instructions have been formally incorporated into the procedure as part of the Licensee's long term corrective action."
5.
Page 31, paragraph A.5 - Revise third sentence to read as follows:
"The return refrigerant high side ball float within the chiller was found to be partially flooded."
6.
Page 34, top paragraph - Delete second sentence as unsubstantiated.
The Hope Creek design fires through both the primary and alternate circuitry.
7.
Page 44, third paragraph - Revise first sentence to read as follows:
"QA conducted 7 audits in the startup area since June, 1984."
- 8. - Revise heading of first column to read
" Licensee Observation."
Thank you for the opportunity to address these minor discrepancies.
Sincerely, r
O e
C Mr.
D.
H.
Wagner USNRC Licensing Project Manager Mr.
R.
W.
Borchardt USNRC Senior Resident Inspector c'
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