IR 05000272/1990003
| ML18094B334 | |
| Person / Time | |
|---|---|
| Site: | Salem  |
| Issue date: | 02/26/1990 |
| From: | Eapen P, Lopez A, Prividy L NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML18094B333 | List: |
| References | |
| 50-272-90-03, 50-272-90-3, 50-311-90-03, 50-311-90-3, NUDOCS 9003140273 | |
| Download: ML18094B334 (6) | |
Text
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U. S. NUCLEAR REGULATORY COMMISSION
REGION I
Report No /90-03 50-311/90-03 Docket No License Nos. DPR-70 DPR-75 Licensee:
Public Service Electric and Gas Company P. O. 236 Hancocks Bridge, New Jersey 08038 Facility Name:
Salem Units No. 1 and 2 Inspection At:
Hancocks Bridge, New Jersey Inspection Conducted:
January 8-12, 1990 on site and January 16-29, 1990 at Region I offices Inspectors: t(, ~. /?~,
.
frv A. E. Lopez, Reactor Engineer, STPS, EB, DRS i-~-t..
L. J. Pri~ior Reactor Engineer STPS, EB, DRS date date Inspection Summary:
Routine Unannounced Inspection on January 8-12, 1990 (Inspection Report Nos. 50-272/90-03 (Unit 1) and 50-311/90-03 (Unit 2))
Areas Inspected:
The licensee's corrective action controls were reviewe Particular emphasis was devoted to inservice testing program activities and several related unresolved items from prior NRC inspection *
Results:
In general, the inspectors determined that the licensee's policies and procedures for their corrective action controls were adequat New licensee actions will be implemented t6 achieve !ST p~ogram administration improvements in response to several observed weaknesses (Section 2.2).
Details 1.0 Persons Contacted 1.1 Public Service Electric and Gas Company L. Miller, General Manager, Salem Operations J. Musameci, Operations Engineer W. Schultz, Manager, Station QA - Salem F. Thomson, Assistant to General Manager, Salem Operations E. Villar, Station Licensing Engineer P. White, Technical Manager The inspectors also held discussions with other members of the station staf.0 Review of License Corrective Action Controls (92720 and 73756)
The inspectors reviewed the licensee's corrective action controls to address operational events and to resolve internally identified problems, NRC inspection -findings, and QA audits finding In general, the*
inspectofs determined that the licensee's policies and procedures for corrective action controls were adequate for the following:
Reporting plant problems to appropriate levels of plant management and to the NRC when require *
Establishing actions and responsibilities to resolve problem *
Fo 11 owing corrective action to comp 1 et ion for identified prob 1 em *
For tracking action items developed from various QA findings using the Action Tracking System (See Section 2.1)
Assuring that personnel adm~nistering containment isolation valve leak rate testing were adequately interfacing with maintenance personnel *to correct known leaking valves on a:timely basis.
. The inspectors also witnessed an auxiliary feed pump surveillance test to assess the effectiveness of improvements implemented in response to previous NRC concerns in the inservice testing are The details of this review are discussed below~
2.1 Action Tracking System The Action Tracking System (ATS) is used at the Salem Nuclear Generating Station Units 1 and 2 to track and status regulatory and internal action items.
Eac~ action item may have three levels of detail:
the.item, assigned tasks, and subtask Each item has its own sponsor department and only the item sponsor can create or update that item recor The task(s) may be assigned by the item sponsor to the responsible department(s) for action~ The task assignee has the option to assign subtasks within the responsible departmen The inspector reviewed the action status of LER's 50-272/89-005, 016, and 031 and Generic Letters 88-17 and 89-1 The ATS status of LER 50-272/89-031 and the two Generic Letters reviewed were up-to-date and adequately addressed the stated concerns. The tracking of LER 50-272/89-005 and 016 was found to be incomplet The subject of LER 50-272/89-005 addressed the failure of Emergency Diesel Generator lC lube oil heate The system engineer had recommended the deYelop-ment of a lube oil heater preventive maintenance procedure (MP) which completed* his task being tracked in the AT However, a new task had not been defined in the ATS for the m~intenance department to develop this MP which is not yet complet Operation with an oxygen concentration greater than 2% for 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> in the Waste Gas Decay Tank as limited by Technical Specifications was the subject addressed in LER 50-272/89-01 Due to the continuing concern of oxygen entry into the Waste Gas Decay System, the licensee completed an inve5tigation of this event in October 1989 and made certa~n recommendations for corrective actio How~ver, these recommendations have not been fully reviewed and entered into th ATS at the time of this inspectio The inspector had no technical*
concerns with respect to the recommendation During the ATS review, the inspector noted that the licensee was not al~ays following the current station administrative procedures for tracking of responses and commitment The licensee stated that they were in transition as a new system is being implemente The licensee stated that NC.NA-AP.ZZ-0057, "Nuclear Administrative Procedure -
Action Tracking Program, 11 would be issued by February 28, 1990, and that 11Administrative Procedure No. 30 - Response/Commitment Tracking Program, 11 would be updated by May 1, 199.2 _Inservice Testing (IST) Program Administration As a result of witnessing Surveillance Procedure (SP) 4.0.5-P-AF(22),
11 Inservice Testing-22 Auxiliary Feed Pump, 11 folfowup inspection of several unresolved items concerning !ST issues and telephone conversations subsequent to the exit meeting (see Section 3.0), the inspector noted following findings regarding the IST program admini-stration:
(1)
On December 13, 1989, the onsite Technical Department assumed the following additional !ST program responsibilities which had previously been under the cognizance of the offsite Nuclear Services group:
Updating the !ST manual, Maintaining the IST component data base, Preparing any !ST program submittals to the NRC, and Coordinating any required reviews of the !ST program at Sale The inspector noted that only one engineer in the Technical Department is assigned part-time to coordinate !ST program
- activitie At the exit interview the General Manager of Operations acknowledged that his Technical Department Manager had recently expressed concern in this area als The licensee stated that they intend to provide one additional per~6n to the on site Technical Department by May l, 199 This person wi 11 work full time ~n IST issue (2) Administrative Procedure (AP) 27, Revision 5, 11 Inservice Inspection and Testing Program" requires revision to reflect the recent transfer bf lST responsibilities from the offsite Nuclear Services group to the onsite Salem Operations grou This version of AP-27 lists many specific responsibilities for
_the Nuclear Services group which do not now exi~t. The licensee stated that Administrative Procedure 27 will be revised by March 31, 1990 to reflect the current assignment of IST responsibilitie (3) Guidance documents are required to better define com~onent testing required by Section XI of the ASME Cod The lack of such guidance has resulted in unresolved items in prior NRC inspection Specifically, the vibration measurement techniques during pump testing and the evaluations of Turbine Auxiliary Feed Pump data were identified as unresolved items in NRC Inspection Reports 50-272/89-11 and 50-272/89-15, respective-ly. _These issues are still unresolved and the aforementioned guidance documents are required to resolve these concerns adequatel In this regard, the licensee provided the inspector with a draft copy of the 11PSE&G Guide for Developing Pump Perfor-mance Test Requirements at the Artificial Island" which addresses this concern relative to hydraulic parameter The licensee stated that by March 31, 1990, one-inch paint marks will be provided at the applicable bearing housing locations to identify specific pump vibration measurement points. This work will provide the needed reference-points to enable compilation of repeatable data and will be completed for the pumps in the
!ST progra Three separate actions addressed the general concern regarding improved documentation for evaluating pump test dat First, a pump data sheet will be developed by March 31, 199 This data sheet will contain the key pump information required by Section XI of the ASME Code. *Secondly, the licensee recognized the need to perform a comprehensive review of instrumentation used for
!ST activities before formally incorporating specific test instrumentation information into the pump test recor This instrumentation review will continue through 1990 and the licensee agreed to inform the NRC of their actions by December 31, 199 Thirdly, an administrative procedure will be developed by June 30, 1990 to define the appropriate method for evaluating !ST dat One goal for this procedure is to achieve consistency in evaluation of !ST data by various plant personne These actions were considered to be responsive to the !ST program findings identified by the inspecto The inspector noted that the licensee was revising the valve portion of their !ST program consistent with their commitments to Generic Letter 89-04 concerning limiting stroke time values for power operated valve These revisions were scheduled to be completed by January.15, 199.3 Service Water System Walkdown On January 10, 1990, the inspectors walked down the service water system for both units with the cognizant system engineer including the service water pump area, the component cooling water heat exchangers and the penetration area for the containment fan coolers service water pipin Modifications were in progress to ~eplace the original carbon steel piping for the air conditioning chiller This modification is part of a service water piping replacement project to utilize high (6%) molybdenum, stainless steel material for the major service water nuclear header Based on the system walkdown and discussions with the system engineer, the inspector determined the following:
The system engineer was knowledgeable concerning the service water system operation, its history and its current problem *
Many of the past problems associated with the service water pumps were due to the unavailability of replacement part This situation has significantly improved in the past year such that a spare pump is kept availabl *
The licensee will install test piping at the discharge of the service water pumps to provide better inservice testin **
G*
The inspector noted a loose U-bolt support for the 3/4-inch bearing cooling water line associated with service water pump 1 The system engineer initiated work orde.r 900111118 to correct ~his problem and the work was scheduled to be done on January 12, 199 The licensee evaluated the piping system assuming that the above support was inoperabl The calculated stresses for this configuration were acceptable and they were well within the code allowable stress for this materia The inspector found these actions to be ~cceptable to resolve the loose support concer.0 Exit Meeting A.t the conc;lusion of the site inspection, on January 12, 1990, an exit interview was conducted with the licensee's senior site representatives (denoted in Section 1) to discuss the results and ~onclusions of this inspectio Additional responses to the inspe*ction findings were discussed with the licensee in a telephone conference call on January 29, 199 At no time during this inspection was written material provided to the licensee by the inspecto Based on the NRC Region I review of this report and discussions held with licensee representatives during this inspection; it was determined that this report does not contain information subject to 10 CFR 2.790 restrictions.