IR 05000354/1986035
| ML20215N092 | |
| Person / Time | |
|---|---|
| Site: | Hope Creek  |
| Issue date: | 10/28/1986 |
| From: | Ebneter S NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | Corbin McNeil Public Service Enterprise Group |
| References | |
| NUDOCS 8611040265 | |
| Download: ML20215N092 (2) | |
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OCT 2 8 mo
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Docket No. 50-354 Public Service Electric & Gas Company ATTN: Mr. C. A. McNeill, Jr.
Vice President - Nuclear Post Office Box 236 Hancocks Bridge, New Jersey 08038 Gentlemen:
Subject:
Inspection No. 50-354/86-35 This refers to your letter dated September 29, 1986, in response to our letter.
dated August 26, 1986.
Thank you for informing us of the corrective and preventive actions documented in your letter. These actions will be examined during a future inspection of your licensed program.
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Your cooperation with us is appreciated.
Sincerely, Originc1 Signed BY.
Ime H. EsttW=en Stewart D. Ebneter, Director Division of Reactor Safety cc w/ encl:
P. R. H. Landrieu, Vice President - Engineering (Newark)
R. S. Salvesen, General Manager, Hope Creek Operations-A. E. Giardino, Manager, Station Quality Assurance R. L. Mitti, General Manager, Nuclear Assurance and Regulation W. H. Hirst, Manager, Joint Generation Projects Department, Atlantic Electric Company L. A. Reiter, General Manager - Licensing and Reliability Rebecca A. Green, Bureau of Radiation Protection Public Document Room (PDR)
Local Public Document Room (LPDR)
Nuclear Safety Information Center (NSIC)
NRC Resident Inspector State of New Jersey 8611040265 861028 PDR ADOCK 05000354 G
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OFFICIAL RECORD COPY RL HC 86-35 - 0001.0.0 10/27/86
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and Gas-Company bec w/ enc 1:
Region'I Docket Room (with concurrences)
Management Assistant, DRMA (w/o encl)
DRP Section Chief
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OFFICIAL RECORD COPY '
RL HC-86-35 - 0002.0.0 10/27/86
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l Pubhc Service Electne and Gas Company Corbin A. McNeill, Jr.
PubhcService ElectncandGasCompany P.O. Box 226.Hancocks Bndge NJ08038 609339-4800 Vics President -
' Ndel33r September 29, 1986 NLR-N86134 U. S. Nuclear Regulatory Commission j
Region I 631 Park Avenue l
King of Prussia, PA 19406 Attention:
Dr. Thomas E. Murley, Administrator I
Office of Inspection and Enforcement Gentlemen:
NRC INSPECTION REPORT #86-35 DOCKET NO. 50-354 HOPE CREEK GENERATING STATION Public Service Electric and Gas -Company (PSE&G) is in receipt of.
your letter dated August 26, 1986, which transmitted a Notice of Violation concerning a failure to comply with the requirements of 10CFR50 Appendix B, Criterion V and Criterion XI.
Pursuant to the provisions of.10CFR2.201, our responses'to the Notice of Violation are provided in Attachment 1.
This submittal is late, as agreed to by Mr.
L. Wink of your staff.
Sincerely,
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Attachment C
Mr. James M. Taylor, Director Office of Inspection and Enforcement Washington, DC 20555 NRC Resident Inspector P.O. Box 241 Hancocks Bridge, NJ 08038
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ATTACHMENT 1 10 CFR 2.201 INFORMATION PUBLIC SERVICE ELCCTRIC AND GAS COMPANY HOPE CREEK GENERATING STATION
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RESPONSE TO NOTICE OF VIOLATION INSPECTION REPORT NUMBER 50-354/86-35 ITEM A
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i Your letter dated August 26, 1986 identified two Violations.
One of the Violations cited a failure to comply with the requirements of 10 CFR 50, Appendix B, Criterion V and Technical Specification 6.8.1.a (through its reference to Regulatory Guide 1.33, Re v.
2, and ANSI N18.7-1976, Section 5.3) that " Activities affecting quality shall be prescribed by documented procedures appropriate
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to the circumstances."
As described in the Notice of Violation, the inspector noted, ' prior to implementing step 5.3.1 of power ascention test TE-SU.BD-142, that the step was not appropriate to the circumstances, in that it would have resulted in the termination of reactor core isolation cooling (RCIC) flow to the reactor. vessel.
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PUBLIC SERVICE ELECTRIC AND GAS COMPANY DOES NOT DISPUTE THE VIOLATION.
The Notice of Violation and insped. ion report allude to the postulated detrimental effects of a termination of RCIC flow to the reactor vessel during performance of this test procedure.
Contrary to this, the purpose of the test was to vary RCIC flow to the reactor vessel... including the reduction of flow from near rated flow to a very low flow condition.
The reduction to a low (or zero) flow value was a planned evolution for which adequate preparations were made to preclude both equipment damage and low reactor water level. A loss of flow to the reactor vessel during the referenced step in the procedure would have not satisfied the i.
test objective in that the low flow data point would not have
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been obtained.
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THE ROOT CAUSE OF THE INCIDENT WAS A TEST PROCEDURE l
INADEOUACY WHEREIN A LOW RCIC TURBINE SPEED WAS SPECIFIED.
INSTEAD OF A LOW PUMP FLOW VALUE.
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IMMEDIATE CORRECTIVE ACTIONS:
As noted in the inspection report, the procedural step was modified to incorporate a pump flow value instead of a turbine speed value prior to performance of the step.
l Additionally, all other RCIC and HPCI test procedures were reviewed for this type of problem and are being changed, as l
necessary, prior to performance of the af fected procedures.
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WE ARE IN FULL COMPLIANCE.
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ATTACHMENT 1 (CONT'D)
ITEM B Your letter also identified a second violation concerning f ailure to comply with the requirements of 10 CFR 50, Appendix B, Criterion XI, which states that " Testing be performed in accordance with written test procedures," and further requires that " Test results shall be evaluated to assure that test requirements have been satisfied."
As described in the Notice of
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Violation, calculations required by step 2.15 of power ascension j
test TE-SU.ZZ-041 were not performed-in accordance with the equations provided in the procedure and a review of the test
l results later f ailed to identify the error.
1.
PUBLIC SERVICE ELECTRIC AND GAS COMPANY DOES NOT DISPUTE THE VIOLATION.
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THE ROOT 'CAUSE OF THE VIOLATION WAS PERSONNEL ERROR WHEREIN A MATHEMATICAL ERROR WAS MADE DURING THE PERFORMANCE OF THE CALCULATIONS IN STEP 2.15 OF TEST PROCEDURE, TE-SU. ZZ-041.
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IMMEDIATE CORRECTIVE ACTIONS:
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The Power Ascension Manager counselled all test engineers to 1) provide greater attention to detailed analysis-type
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steps (such as calculations) and 2) take the necessary time to make periodic overview evaluations of detailed steps.
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The number of senior independent review personnel was increased to enhance the quality of the independent review process.
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WE ARE IN FULL COMPLIANCE NOW.
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