ML20237E222
| ML20237E222 | |
| Person / Time | |
|---|---|
| Site: | Hope Creek  |
| Issue date: | 12/18/1987 |
| From: | Kane W NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML20237E195 | List: |
| References | |
| 50-354-87-17, NUDOCS 8712280219 | |
| Download: ML20237E222 (16) | |
Text
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APPENDIX A NOTICE OF VIOLATION Public Service Electric and Gas Company Docket No. 50-354 Hope Creek Generating Station License No. NPF-57 During an NRC safety inspection conducted on July 14 - August 17, 1987, NRC inspectors reviewed the circumstances associated with violations identified by the licensee and reported to the NRC, including a violation of a Technical Specification Limiting Condition for Operation. In accordance with the
" General Statement of Policy and Procedure for NRC Enforcement Actions," 10 CFR Part 2, Appendix C (1987), the violations are set forth below:
A. Technical Specification Limiting Condition for Operation (LCO) 3.3.3 Emergency Core Cooling System Actuation Instrumentation, and its associated Table 3.3.8-1, Section 4, Trip Functions for the Automatic Depressurization System (ADS), require that whenever the reactor is in Modes 1,2 or 3, two residual heat removal (RHR) pump discharge pressure instruments per pump shall be operable to satisfy the ADS actuation permissive logic. With less than two pressure instruments per RHR pump operable, the affected pump must be declared inoperable. Further Tech-nical Specification LCO Action Statement 3.5.b.1 states that with one RHR pump inoperable, operation of the reactor may continue for not more than 30 days, provided at least one core spray system is operable.
Contrary to the above, from some time after April 10, 1987 until July 11, 1987, while the reactor was in Mode 1, the two discharge pressure instruments for the "C" RHR pump were inoperable because tne isolation valve for pressure transmitters PTN055H and PTN0560 was closed, and the "C" RHR pump had not been declared inoperable. (Prior to July 11, 1987 the instrument isolation valve was last verified open on April 10,1987.)
Consequently, the "C" RHR pump is considered to have been inoperable for more than 30 days.
This is a Severity Level IV violation (Supplement 1).
B. Technical Specification 6.8.1 requires that written procedures be estab-lished, implemented, and maintained covering the activities recommended in Appendix A of Regulatory Guide 1.33, Revision 2, February 1978, which includes Administrative procedures for equipment control.
Operations Department Administrative Procedure OP-AP.ZZ-108(Q), " Removal and Return of Equipment to Service," requires that all applicable Tech-nical Specification Limiting Conditions for Operation (TS LCOs) be reviewed to determine if equipment status requires entry into an action statement.
OFFICIAL RECORD COPY NOV HC 87 0005.0.0 8712280219 871218 12/16/87 PDR ADOCK 05000354 G PDR
Appendix A 2 Contrary to the above, the review of TS LCOs was not adequate, in that: l (1) On July 11, 1987, residual heat removal pressure transmitters PTN055H and PTN056D were found to be out of service and the applicable TS 3.3.3 action statement had not been entered; and (2) On July 25, 1987, both high pressure coolant injection room coolers were removed from service and the applicable TS 3.5.1 action state-ment was not entered.
This is a Severity Level IV violation (Supplement 1).
Pursuant to the provisions of 10 CFR 2.201, Public Service Electric and Gas Company is hereby required to submit a written statement or explanation to the U.S. Nuclear Regulatory Commission, ATTN: Document Control Desk, Washington, DC 20555, with a copy to the Regional Administrator, Region I, and a copy to the NRC Senior Resident Inspector within 30 days of the date of the letter transmitting this Notice. This reply should be clearly marked as a " Reply to a Notice of Violation" and should include for each violation: (1) the reason for the violation if admitted, (2) the correct steps that have been takco and the results achieved, (3) the corrective steps that will be taken to avoid further violations, and (4) the date when full compliance will be achieved.
If an adequate reply is not received within the time specified in this Notice, an order may be issued to show cause why the license should not be modified, suspended, or revoked or why such other action as may be proper should not be taken. Consideration may be given to extending the response time for good cause shown.
FOR THE NUCLEAR REGULATORY COMMISSION William F. Kane, Director Division of Reactor Projects Dated at King of Prussia, Pennsylvania, this 18th day of December 1987 1
) 0FFICIAL RECORD COPY NOV HC 87 0006.0.0 12/16/87
o
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ENCLOSURE 2 ENFORCEMENT CONFERENCE MEETING
SUMMARY
I. Introduction:
On October 19, 1987, an enforcement conference was held in Region I due to recurrent violations resulting from improper alignment of various safety-related equipment. Although these . items were identified by the licensee and properly reported to the NRC, preventive measures taken for a similar previously cited violation (Inspection Report 50-354/86-48) may have been ineffective in preventing the current. violations. Therefore, the enforcement conference was held to discuss the licensee's planned corrective actions to prevent future similar violations and to enhance the management controls to assure proper equipment alignment.
- 2. Meeting Attendees:
N. R_C J. M. Allan, Deputy Regional Administrator, RI J. M. Gutierrez, Regional Counsel, RI S. J. Collins, Deputy Director, Division of Reactor Projects (DRP)
E. C. Wenzinger, Chief, Projects Branch No. 2, DRP P. D. Swetland, Chief, Reactor Projects Section No. 2B, DRP R. W. Borchardt, Senior Resident Inspector D. K. Allsopp, Resident Inspector R. J. Summers, Project Engineer, RPS 2B, DRP, Licensee:
S. Miltenberger, Vice President - Nuclear Operations i S. LaBruna, General Manager, Hope Creek Operations G. Connors, Operations Manager, Hope Creek Operations B. Preston, Manager, Licensing & Regulation State of New Jersey - Department of Environmental Protection D. Scott, Chief, Bureau of Nuclear Engineering, NJDEP D. Zannoni, Hope Creek Liaison, Bureau of Nuclear Engineering, NJDEP OFFICIAL RECORD COPY NOV HC 87 0008.0.0 12/16/87
Enclosure 2- 2
- 3. Meeting Presentation and Discussion:
NRC Region I presented the findings of Inspection Report No. 50-354/87-17 including the details of the apparent violations due to inadequate con-trols for the proper alignment of plant equipment. One of these items, pertaining to the inadvertent disposition of an instrument root valve associated with the permissive logic of the ADS, was noted as being simi-lar to an event which resulted in a prior violation of NRC requirements, and for which preventive measures appeared to be ineffective.
The licensee made a presentation on the control of equipment alignment.
A copy of this presentation is included as an attachment to this meeting summary. The licensee's presentation and subsequent discussion addressed the following:
l -
Analyses, by both the station and the independent Safety Review Group, of relevant plant events to determine the magnitude and type of errors that have invol'ved improper equipment alignment.
An assessment of prior corrective actions for those events identified above to determine if preventive measures have been effective; or if not, to identify additional measures to be taken.
Details of corrective actions already taken, or planned for comple-tion in both the short and long term to provide sufficient controls
- to assure that important equipment is properly aligned for operation.
- 4. Conclusions The NRC determined that the loss of control over system alignment for the ADS logic instrumentation valves, resulted in a violation of the Technical Specification Limiting Condition for Operation for the "C" RHR pump. The I
licensee's review of this and similar plant events has resulted in planned corrective actions to prevent recurrence of equipment. misalignment problems and improve the quality of their root cause analysis and l corrective action programs. The licensee's corrective measures will be l reviewed during future routine safety inspections.
L i
OFFICIAL RECORD COPY NOV HC 87 0009.0.0 12/16/87
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n PUBLIC SERVICE ELECTRIC & GAS COMPANY HOPE CREEK NUCLEAR GENERATINC STATION PRESENTATION TO U.S. NUCLEAR REGULATORY COMMISSION REGION 1 OCTOBER 19, 1987 CONTROL OF EQUIPMENT ALIGNMENT
's. ,
s 1 Introduction - General Manager - Hope Creek A. Concerns B. Presentation background 1 Analysls of all incident reports /LER's from 4/11/86 to present relevant to control of switches and valves 2 Independent Safety Reylew Group (SRG) analysis over s a rn e period
- 3. Broad assessment of operational control 11 Presentation -
Operations Manager - Hope Creek {
A. Incident reports grouped by category 1 Operating error - skipped steps, fallore to follow '
procedure, misunderstanding, etc.
- 2. Failure of administrative controls -
existing procedure failed to prevent Incident 3 Program deficiency - no program in existence or staff error B. Conclusions Ill. Corrective actions - General Manager - Hope Creek '
A. Completed B. Short term C. Long term
i RELEVANT ICCIDENT REPORTS INCLUDED IN REVIEC 1R LER DATE DESCRIPTION
, _ CATEGORY 86-036 86-005 4/16/86 FRVS IN LOCKOUT OP ERROR 86-058 86-015 5/6/86 INTERMEDIATE INSTRUMENT PROGRAM DEF VALVES86-062 t/11/86 DIESEL GENERATOR FIRE FAIL ADM CONT PROTECTION FUSES86-159 8/3/86 TURBINE AUXILLARY COOLING Fall ADM CONT VALVES INOPERABLE 86-167 8/10/86 MAIN STEAM SEALING ALARM Fall ADM CONT INOPERABLE 86-172 8/16/86 D DIESEL GENERATOR LUBE OIL FAIL ADM CONT MAKEUP SHUT 86-234 10/22/86 RECIRC FL0t UNIT LEFT OP ERROR BYPASSED 86-236 86-070 10/22/86 C CORE SPRAY TRANSMITTER PROGRAM DEF j ISOLATED 86-247 11/6/86 ACID SPILL OP ERROR 86-272 12/12/86 FIRE PUMP VALVING ERROR OP ERROR 87-077 5/24/87 FIRE DAMPER INCORRECT SWITCH PROGRAM DEF SETTING 87 082 87-023 6/5/87 B AND C OlESEL GENERATOR AIR OP ERROR START SWITCHES IN OFF 87-088 6/18/87 MANUAL EXCESS FLOW CHECK PROGRAM DEF VALVES BYPASSED 87-097 87-029 7/11/87 C RHR TRANSMITTER ISOLATED Fall ADM CONT 87-110 7/28/87 HPC) ROOM COOLERS IN STOP OP ERROR 87-119 8/7/87 A DIESEL GENERATOR FANS Fall ADM CONT CONTROL IN OFF 87-120 8/8/87 D DIESEL GENERATOR AIR OP ERROR START SWITCH OFF 87-122 8/13/87 HPCI HiGH EXHAUST PRESS SW PROGRAM DEF VALVED OUT l
l 87-139 87-040 9/10/87 INCORRECT RWCU LINEUP OP ERROR i 87-140 I l
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, CONCLUSIONS ROOT CAUSE AND CORRECTIVE ACTIONS TOO SPECIFIC TO EVENT OR SYSTEM UNDER CONSIDERATION Q/NON-Q INSTRUMENT VALVES NOT INCORPOR/TED ON P&lD IN A CONSISTENT MANNER O/NON-Q lNSTRUMENT VALVE OPERATIONS LEAD TO POTENTIAL VALVING ERRORS EQUIPMENT RESTORATION PROGRAM DID NOT GIVE EQUIPMENT OPERATORS A DETAILED VALVE LINEUP FOR VALVES INSIDE BOUNDARIES ASPECTS OF OPERATIONAL CONTROL AND ROLE CLARIFICATION BETWEEN OPERATIONS, MAINTENANCE, AND MANAGEMENT NEED TO BE REDEFINED AND TRAINING IMPLEMENTED MORE FREQUENT REVIEW OF CONTROLS AND lNDICATIONS BY LICENSED AND NON-LICENSED OPERATORS IS REQUIRED POTENTIAL LETDOWN IN MORALE FOLLOWING RECENT IBEW CONTRACT NEGOTIATIONS l
i
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, CORRECTIVE ACTIONS COMPLETED OPERATIONS MANAGER ISSUED A LETTER TO ALL OPERATORS AND HELC SMALL GROUP MEETINGS TO REVIEW THE RECENT VALVlNG AND SWITCHING ERRORS (10/2/87) i IMPLEMENTED QUARTERLY SHIFT MEETINGS CONDUCTED BY THE GENERAL MANAGER TO DISCUSS CONCERNS OF LICENSED AND NON-LICENSED OPERATORS AND IDENTIFY AREAS OF NEEDED MANAGEMENT SUPPORT (COMMENCED 9/2/87)
SHORT TERM
\
GENERAL MANAGER TO ISSUE A LETTER TO ALL PERSONNEL CLARIFYlNG RESPONSIBILITIES FOR PLANT OPERATIONS. MANAGEMENT TO HOLD SMALL GROUP MEETINGS TO REVIEW RESPONSIBILITY FOR EQUIPMENT OPERATIONS (BY 11/2/87)
OPERATIONS MANAGER TO REVISE THE PROCEDURE FOR PARTIAL SYSTEM RESTORATIONS PRIOR TO RETURNING EQUIPMENT TO SERVICE (BY 11/15/87)
PROVIDE RE-TRAINING FOR LICENSED AND NON-LICENSED OPERATORS DURING REQUALIFICATION ON RECENT VALVE AND CONTROL PROBLEMS IN THE INDUSTRY AND AT HOPE CREEK (BY 2/1/88)
LONG TERM CONDUCT TRIS AUDIT OF INSTRUMENT ROOT VALVES ON A CONTINUING BASIS AS P&lD'S ARE REVISED TO COMPLETE UPDATE PROGRAM (BY 6/88)
COMPLETE INSTRUMENT INTERMEDIATE VALVE NUMBERING AND LOCKING PROGRAM FOR INSTRUMENT SENSING LINES (B Y 6/88)
RE-ANALYZE NEED FOR Q/NON-Q BOUNDARY VALVES IN PRESSURE INDICATION LINES REQUIRING PERIOOIC USE GENERAL MANAGER TO CHAIR NUCLEAR DEPARTMENT INCIDENT AND TRIP REDUCTION TASK TEAM (COMMENCED 10/6/87)
INPO TO MAKE A PRESENTATION OF THE HUMAN PERFORMANCE EVALUATION SYSTEM (HPES) FOR STATION MANAGEMENT TO ASSESS LESSONS LEARNED AND POTENTIAL APPLICATION (SCHEDULED 10/28/87)
STATION MANAGEMENT TO PARTICIPATE IN THE BWR OWNERS GROUP WORKSHOPS ON SCRAM REDUCTION, ROOT CAUSE ANALYSIS, AND LER REDUCTION
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