IR 05000354/1985065

Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Rept 50-354/85-65

ML20154H174
Person / Time
Site:	Hope Creek
Issue date:	03/05/1986
From:	Ebneter S NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
To:	Corbin McNeil Public Service Enterprise Group
References
NUDOCS 8603100207
Download: ML20154H174 (2)

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MAR 051986

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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. 50-354/85-65 This refers to your letter dated February 12, 1986, in response to our letter dated January 31, 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.

Your cooperation with us is appreciated.

Sincerely, Original Signoe. My :

Lee II. Bettenhaus en Stewart D. Ebneter, Director Division of Reactor Safety cc:

T. J. Martin, 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 A. J. Pietrofitta, General Manager, Power Production Engineering, Atlantic Electric 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 D(

State of New Jersey I

0FFICIAL RECORD COPY RL HC 85-65 - 0001.0.0 8603100207 860305 , 02/2U86 PDR ADOCK 05000354 G PDR

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Public Service Electric & Gas Company 2

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Region I Docket Room (with concurrences)

Management Assistant, DRMA (w/o encl)

DRP Section Chief J. Grant, DRP l

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x-() 0FFICIAL RECORD COPY RL PC 85-65 - 0002.0.0 02/27/86

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Public Servim

- Electric and Gas Company Corbin A. McNelH, Jr. Public Service Electric and Gas Company P.O. Box 236, Hancocks 3 ridge NJ 08038 609339-4800 WC3 President -

NuclGar February 12, 1986 Dr. Thomas E. Murley, Administrator U. S. Nuclear Regulatory Commission Office of Inspection and Enforcement Region I 631 Park Avenue King of Prussia, Pennsylvania 19406

Dear Dr. Murley:

NRC INSPECTION #85-65 ITEM OF NONCOMPLIANCE HOPE CREEK GENERATING STATION Please find below our response to the item of noncompliance cited at the January 3, 1986, exit interview for NRC Inspection No. 85-65.

According to 10CFR50 Appendix J, Section III, Leakage Testing Requirements, Part A(b), closure of containment isolation valves for Type A test shall be accomplished by normal operation and without any preliminary exercising or adjustments (e.g., no tightening of valves after closure by valve motor). In addi-tion, Step 7.1.3 of Section 7.0, Special Precaution and Notes of PSSUG-PTP-GP-1, " Integrated Leak Rate Test" states, "All containment valves shall be positioned by their normal means, no torquing of handwheels or exercising of the valve shall be permitted".

Contrary to the above, upon completion of the preoperational Integrated Leak Rate Test (ILRT), the Limitorque operator for containment isolation valve KL-HV-5148(V-001) was found with its declutch lever in the engaged position, indicating that the valve may have been hand-tightened.

Corrective Steps Taken and Re;ults Achieved Given the importance of the ILRT and the company's strict position regarding compliance with safety tagging rules, the decision was made to use red blocking tags under the Station Safety Tagging Procedure for the ILRT valve lineup rather than the standard orange T-mod tags.

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Dr. T. However, subsequent to the Structural Integrity Test and prior to initiation of the ILRT, PSE&G QA surveillance identified outboard containment isolation valve BE-HV-F015A(V-025) as having its declutch lever engaged. The ILRT was postponed pending completion of inspection of all motor operated containment isolation valves outside the containment. Fourteen additional valves were found with their declutch levers engaged. All fifteen motor operated valves were electrically restroked reestablishing the requisite test conditions.

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Immediately following the ILRT, a team of personnel from Opera-t tions, QA/QC and the ILRT Group conducted a walkdown of the sixteen motor operated isolation valves inside the containment.

l During this walkdown, the discrepant condition of valve KL-HV-5148(V-001) was identified.

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On-the-Spot Change No. 28 to preoperational test procedure

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PTP-GP-1 was issued providing a leakage penalty of 97 SCCM (measured leak rate through the valve) to be added to the integrated test results.

Startup Deficiency Report (SDR) No. KL-0288 was initiated to address the potential for malfunction of motor operated valve KL-HV-5148(V-001). Subsequent investigation verified the declutch adjustment as correct and no malfunction was observed during repeated cycling of the motor operated valve.

Investigation Our investigation revealed that in the process of tagging out a motor operated valve (MOV), the equipment operator normally engages the clutch and tries to rotate the handwheel in the closed direction to ensure that the valve is safely seated, thereby protecting personnel. Manually verifying closure of a MOV during a tagout is not prohibited by existing station procedures.

Therefore, we conclude that during the valve lineup activities for the ILRT, the operating shift personnel were not properly ,

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advised of the requirements of PTP-GP-1 and Appendix J. Station supervisory personnel failed to ensure that all shift operators clearly understood the change to the no*. mal tagout procedure.

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Dr. T. /12/86 A review of the tagging request forms prepared for the ILRT valve lineup indicated no precautionary instructions had been entered in the Special Instructions portion of the forms.

We conclude that the personnel responsible for preparing the ILRT tagging requests were unaware of Operation's standard practice of verifying closure when tagging out MOV's.

These valves are designed to be operated manually or electrically.

Engagement of the clutch into the manual mode disengages the electric drive mechanism. Electrical actuation of the valve automatically reengages the electric drive. Remote set capa-bility of the valve is unaffected whether the valve was last actuated manually or electrically. Therefore, manual verification of closure has no adverse impact on MOV operability.

Corrective Steps Taken to Preclude Recurrence All Operations personnel will be briefed on the contents of this violation and our response.

Operating procedure OP-AP.ZZ-109(Q), "Equipnent Operational control", has been revised incorporating the requirement that manual torquing of motor operated valves is not permitted when performing ILRT lineups.

In addition, on January 18, 1986, a Procedure Revision Request was initiated to incorporate the same requirement into the next revision of the Hope Creek Station Safety Tagging Procedure SA-AP.ZZ-015(Q).

A test precaution will also be incorporated into the inservice Type A test procedure M9-ILP-301 stating, in part, " Power actuated containment isolation valves shall not be manually operated."

Date of Full Compliance All Operations personnel will have been briefed by February 21, 1986.

Revision 1 to OP-AP.ZZ-109(Q) was approved on January 22, 1986.

Sincerely,

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Dr. T. /12/86 C' Office of Inspection and Enforcement Division of Reactor Construction Inspection Washington, D. C. 20555 NRC Resident Inspector P. O. Box 241 Hancocks Bridge, NJ 08038 i

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