IR 05000272/1986020
| ML18092B249 | |
| Person / Time | |
|---|---|
| Site: | Salem  |
| Issue date: | 07/25/1986 |
| From: | Eapen P, Hunter J, Oliveira W NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML18092B248 | List: |
| References | |
| 50-272-86-20, NUDOCS 8608150236 | |
| Download: ML18092B249 (18) | |
Text
--
~-** *
U.S. NUCLEAR REGULATORY COMMISSION
REGION I
50-272/86-20 Report No /86-20 50-272 Docket No DPR-70 License Nos. DPR-75 Licensee:
Public Service Electric and Gas Company P. 0. Box 236 Hancocks Bridge, New Jersey 08038 Facility Name: Salem Nuclear Generating Station, Units 1 and 2 Inspection At: Hancocks Bridge, New Jersey Inspection Conducted: June 30 - July 8, 1986 Inspector:
Approved by:
'
date 7,1 as:-/ r;{-b date7 Inspection Summary:
Routine, unannounced inspection conducted on June 30 through July 8, 1986 (Combined Report Nos. 50-272/86-20 and 50-311/86-20)
Areas Inspected: Quality assurance program, Measuring and test equipment, Records program, and Document control progra Results:
No violations were identifie *
DETAILS 1.0. Persons Contacted Public Service Electric and Gas (PSE&G)
R. Antonow, Maintenance Department Senior Staff Engineer D. Boyle, Associate Staff Engineer (Maintenance)
E. Browder, Station Quality Assurance (QA) Supervisor M. Cocking, Senior Maintenance Supervisor B. Connor, Operations Lead Engineer J. Doterer, Methods and Systems Supervisor
- R. Dulee, Principal Station QA Engineer R. Gabel, Senior Maintenance Supervisor N. Garrity, Operations Senior Shift Supervisor
- C. Johnson, General Manager, Nuclear QA (NQA)
Jim Kovar, Maintenance Department Measuring and Test Equipment (M&TE)
Coordinator R. Kuzanas, Nuclear Department Calibration Supervisor B. Leap, Operations Response Coordination Senior Engineer S. Liden, Document and Records Clerk F. Mekulsia, Senior I&C Supervisor
- L. Miller, Assistant General Manager, Salem Operations M. Murphy, Records Administrator J. Morrison, Maintenance (Mechanical) Engineer M. Orticelle, Operations Department Surveillance Coordinator D. Perkins, Station QA Manager J. Ronfalvy, Technical Manager
- J. Rupp, Licensing Engineer W. Schlegelmilch, Operations Lead Engineer E. Schmieder, Prinicipal Technical Administrator-Engineering Design W. Schultz, Program and Audit Engineer, Nuclear Department L. Sutton, Stores M&TE Coordinator J. Zupko, General Manager, Salem Operations During the course of the inspection the inspectors also contacted other technical and administrative licensee personne United States Nuclear Regulatory Commission
- K. Gibson, Resident Inspector
- Denotes those who attended the exit meeting July 8,1986
DETAILS 1.0. Persons Contacted Public Service Electric and Gas (PSE&G)
R. Antonow, Maintenance Department Senior Staff Engineer D. Boyle, Associate Staff Engineer (Maintenance)
E. Browder, Station Quality Assurance (QA) Supervisor M. Cocking, Senior Maintenance Supervisor B. Connor, Operations Lead Engineer J. Doterer, Methods and Systems Supervisor
- R. Dulee, Principal Station QA Engineer R. Gabel, Senior Maintenance Supervisor N. Garrity, Operations Senior Shift Supervisor
- C. Johnson, General Manager, Nuclear QA (NQA)
Jim Kovar, Maintenance Department Measuring and Test Equipment (M&TE)
Coordinator R. Kuzanas, Nuclear Department Calibration Supervisor B. Leap, Operations Response Coordination Senior Engineer S. Liden, Document and Records Clerk F. Mekulsia, Senior I&C Supervisor
- L. Miller, Assistant General Manager, Salem Operations M. Murphy, Records Administrator J. Morrison, Maintenance (Mecnanical) Engineer M. Orticelle, Operations Department Surveillance Coordinator D. Perkins, Station QA Manager J. Ronfalvy, Technical Manager
- J. Rupp, Licensing Engineer W. Schlegelmilch, Operations Lead Engineer E. Schmieder, Prinicipal Technical Administrator-Engineering Design W. Schultz, Program and Audit Engineer, Nuclear Department L. Sutton, Stores M&TE Coordinator J. Zupko, General Manager, Salem Operations During the course of the inspection the inspectors also contacted other technical and administrative licensee personne United States Nuclear Regulatory Commission
- K. Gibson, Resident Inspector
- Denotes those who attened the exit meeting July 8,1986
2.0 Quality Assurance Program Annual Review The purpose of this inspection was to assess the effectiveness of the li-censee1 s quality assurance (QA) program changes and implementatio The licensee 1s implementing procedures were also reviewed to ascertain that 1984 and 1985 QA Program Description (QAPD) changes were adequately incor-porate The inspector interviewed licensee personnel having responsbility for preparing the implementing documentation and verified that they under-stood the significance of the change The inspectors reviewed the imple-mentation of the licensee 1s QA program by performing inspections in the Measuring and Test Equipment area; Records Management; and Document Contro The inspection results of these areas are discussed in paragraphs 3, 4, and.1 Findings The changes to the QAPDs, except in one case, affected QA procedure VPN-QAP-01, Operational QA Progra These changes were made to clarify licensee requirements and commitment For example, FSAR Section 17.2.2.4.1 clarified qualification requirements for the position of Manager, Nuclear Operations Quality Assuranc This clarification was requested in the NRC letter of December 6,1984, addressing 10 CFR 50.54(a) QAPD Review.
The one change that required a revision to a lower tier implementing procedure (a maintenance procedure) involved the addition of Chil"led Water System to the 11Q 11 List and the FSAR Table 17.2-The in-spector not only reviewed the affected maintenance procedure MllE, Mechanical Equipment Trouble Shooting and Repair, but also verified its effective implementation by reviewing Work Order (WO) 06-07-07-168-6,
11 Inspect Compressor for Missing Valve Spring 11 *
The chilled water system and the compressor were classified as safety related in both case QA personnel reviewed Design Change (DC) 1953 and noted that weld preparation and cleanliness checks were bypassed on work performed on No. 12 Chiller Condenser. To correct this, the Station QA personnel issued A Stop WO (SWO) SS 86-SOOl on February 7, 1986 against this design chang The corrective action was to cut out and rework the welds.
- The Operations, Maintenance, and Technical Department personnel re-sponsible for implementing changes to their respective station proce-dures were interviewed. The results indicated that the personnel were advised of QAPD changes that may affect their departments. They are knowledgeable of the technical specifications (TS), FSAR, and code requirements and are able to review the changes and respond in a timely manne No violations were identifie.0 Measuring and Test Equipment (M&TE)
3.1 Program Review The inspector reviewed the documents in Section II of Attachment C and determined that the established controls for the M&TE Program addressed the following:
Responsiblities for establishing and implementing a M&TE progra Development of an equipment inventory list including addition of new equipmen Identification of the calibration status of M&T A recall system for the M&T Out-of-calibration controls and traceability of the M&TE to previous use.2 Program Implementation The inspector randomly selected M&TE that were being used in the fiel The calibration status, storage, issuance, use, return and the records of M&TE were reviewe The craft, technicians and the M&TE Coordinators were knowledgeable in the use and care of the M&TE and associated procedure The technicians also knew the procedural requirements for reporting those M&TE that were damaged or providing questionable result~.
The inspector observed the use of M&TE with the Operations, Main-tenance, and Stores M&TE Coordinator The department's M&TE programs were documented and the equipment was calibrated, adequately stored and maintaine The inspector observed personnel requesting M &TE, its issue, checking of the issued equipment by personnel prior to leaving the issue area and returning the equipment.
The following work activities involving M&TE were observed to verify the adequacy of the use of these instruments in safety related activitie *
WO 86-06-23-053-7, Inspection/Order (I/0) 400018, Reactor Protec-tion System (RPS) Channel Function Test of No. 13 SG Stearn Press Channel Test performed in accordance with I&C procedure lPD-2.6.05 WO 86-06-19-140-0, RPS Channel Function Test of Reactor Coolant Flow Loop 2, Channel Test performed in accordance with I&C procedure 2PD-2.6.006 WO 85-11-25-029-8, No. 11 Bleed Stearn Coil Drain Tank Pump Vi-bration Analysi The pump is not safety related, however the analysis and the documentation were treated as safety relate The analysis was performed in accordance with maintenance mechanical procedure Mll The machinist was trained in the use of the vibration instrument at the Training Cente In each of the work activities, the personnel were observed recurding the M&TE on the WO and the M&TE calibration data on the procedure data sheets as required by procedure AP-2 The M&TE randomly selected or observed in use included: one torque wrench; two dial indicators; three rnultirneters; four power supplies; one voltmeter; and one vibration monitoring instrumen The Nuclear Department Calibration (NOC) facility was able to produce the records for each of these equipmen The records included past calibrations, the calibration procedures, and the reference standards which were traceable to National Bureau of Standards (NBS).
NOC determines the frequency of calibration with the inputs from the user The equip-ment (instrument) failures are trended using a compute If an in-strument provided unacceptable 1as found 1 reading during three successive calibrations, its calibration interval would be reduced to hal This instrument will go back to its original calibration fre-quency only if the trend shows improvement If an instrument fails during calibration, the M&TE Coordinator receives an Evaluation and Report (ER) form from NO The Coordinator researches all the work activities involving the failed instrumen The inspector reviewed ERs 002061, 7066, and 12608 with the coordinato In the case of ER 7066, the Coordinator initiated WO 86-07-01-0123 to recalibrate a deviation alarm transmitter.
- 3.3 Findings Nuclear Department Calibration (NOC) sends a monthly report to the Coordinators requesting the return of ins~ruments requiring recali-bratio The inspector reviewed the list of instruments overdue for recalibratio Between two and eight percent of all instruments were overdu Stores personnel in accordance with the Nuclear Procurement and Material Control Procedure Mll-P-550, issue a memorandum request-ing the departments to return instruments for recalibratio The inspector noted three instruments that had not been returned for recalibration because they were contaminate The Stores log indi-cated this information was provided orally and there was no evidence of any formal response to the memoranda sent by Store The in-spector discussed the status of these instruments with-the Main-tenance Department personne The inspector located one such overdue instrument in the hot shop waiting to be recalibrate The licensee management informed the inspector that the other two instruments were scraped as contaminated waste and that Stores would be so advise QA identified the above lack of control for recalibration of contam-inated M&TE in Surveillance Reports S-83-29 and 84-1 QA also initiated and chaired a meeting on June 3, 1986 with the department coordinators to discuss this concern and to identify actions required to correct the proble Maintenance Department has revised procedure A9 to tighten the contro*1 of issued instrument These actions indi-cate that the licensee has realized problems in controlling contami-nated M&TE and is implementing actions to preclude recurrence. The control of contaminated M&TE is an unresolved item pending completion of corrective action planned in the June 3, 1986 meeting. {50-272/
86-20-01 and 50-311/86-20-01).
No violations were identifie.4 QA/QC Interface in the Measuring and Test Equipment Program Four QA audit reports listed in Section II of Attachment C and the supporting material were reviewe The reports are comprehensive, and the responses and the subsequent verification are timel The Station QA personnel conduct surveillances of the station depart-ment control of M&T It was during one of these surveillances that the issue of contaminated equipment was identified as discussed in paragraph The inspector reviewed six Station QA Surveillance Reports and found them to be in compliance with their procedure M31-Q-01 * *
Records Management The basic requirements and guidelines for collect1on, storage and mainten-ance of Quality Assurance records are listed in Section III of Attachment.1 Program Review The above requirements and guidelines are implemented by the licen-see1 s Quftlity Assurance Program by utilizing Site Administrative procedures, Quality Assurance procedures, and Vice President Nuclear procedures, Nuclear Records Management procedures, and Nuclear Ad-ministrative Methods procedures, listed in Attachment B, Section III:
The licensee's implementing procedures were reviewed to verify com-pliance with the requirements and guidelines and to assure that the licensee's procedures adequately established the following; Requirements to maintain and retain records required by the licensee's quality assurance progra Responsibilities to identify and maintain QA records; Responsibilities to transfer and retain construction and pre-operational phase records; Record storage controls to identify record storage facility, designate custodian(s) in charge of storage facilities, file and retrieve record Controls to verify that the records received are in agree-ment with pre-established checklists or transmittal documents; Control access to the files, traceability when files are removed from storage; Requirements for correcting files and disposing superseded records; Authorities and responsibilities for authorizing the disposal of records no longer required to be maintained; and Responsibilities for determining retention times for records not covered by the FSAR, T.S. or 10 CFR.
- .3
Implementation The inspector selected a random sample of records to assess retrieva-bil it These records (listed in Attachment C,Section III) consisted of surveillance test, operator log, maintenance work order, deficiency report and radiography record The inspector verified that the re-cords sampled were processed according to procedures, listed on the computer index or transmittal sheet, properly filed, complete and readily retrievabl The inspector also reviewed the records for technical adequacy and proper dispositio No discrepancies were identifie Findings The Central Records Facility (CRF) is located outside the Salem sta-tion and is where records are received, indexed, microfilmed, repro-duced, and store The Engineering Records Center located in TB-2 is responsible for filming drawings and retaining the original trac-ings and one copy of each drawing on operative card The CRF pro-cesses the film and makes the drawing operative card The licensee s procedures outline the responsibilities and provisions for access control, collection, disposition, retention, storage, and maintenance of record The procedure addressing the storage facility does not adequately describe the record storage facilities, the filing system, the retrieval process, and the controls applied to hard copy records removed from the storage facilitie The storage facilities presently used for records turned over to the records management organization, but not yet filmed, do not meet the requirements of ANSI N45.2.9 regarding fire protection and temperature and humidity control The licensee is aware of the deficiency and has taken corrective action in that two 2-hour rated fire resistant file trailers conforming to NFPA 232-1975 have been installe The new facilities have fully enclosed metal cabinets for record storage, temperature and humidity control and monitoring, and a halon fire suppression system with an automatic notification to the guard hous The inspector toured the new facilities and was informed by the licen-see that the transfer of records would commence prior to August 198 The inspector found the new storage facilities adequat Engineering and Plant Betterment (E&PB) has not yet established and implemented an internal Records Management progra The program is being developed in response to the Quality Assurance request MAR-MA-86-MOOl from Quality Assurance audit NM-85-01 The audit iden-tified that permanent Quality Assurance records generated by E&PB were not transmitted to the CRF for processin The records are presently stored in boxes and file cabinets throughout TB-In
response to the Quality Assurance finding the E&PB department has developed a schedule to generate a procedure governing E&PB records management by August 1, 1986, conduct training for the procedure im-plementation by September 1, 1986, and commence implementing the procedure September 1, 198 Plans are also being developed to transfer the records to the CRF for processin While reviewing Piping Isometric and Hanger Support Evaluation and Stress Calculations (listed in Attachment C) the inspector noted that the format of documenting the calculations was not in accordance with procedures in that an explicit statement of the purpose was not al-ways written. It was also noted that verification forms accompanying the calculations were not always properly completed in the areas of QA requirements and industry code applicabilit The aforementioned discrepancies were previously identified in Quality Assurance Audit NM-85-013 and requests QAR-MA-86-QOOl and QAR-MA-86-Q002 were written to initiate corrective actio The engineering design group is in the process of evaluating the discrepancies and their caus Through discussions with management and a review of the current staffing, the inspector determined that the licensee is adequately staffed to handle the current records workloa There is however a substantial amount of backlog records which need to be processe The licensee informed the inspector that there are plans to use a contractor to help alleviate the records backlo The records man-agement organization also has contingency plans for temporary help during outage period The attributes of the records management system reviewed, except for the aforementioned items, were adequat No violations were identi-fie.0 Document Control Program The basic guidelines and requirements of a document control program are identified in Attachment A,Section I.1 Program Review The requirements and guidelines established in the reference docu-ments in paragraph 5.0 are implemented by the licensee 1 s Quality Assurance Program by utilizing Quality Assurance Procedures, Vice President Nuclear Procedures, Site Administrative Procedures, Nuclear Engineering Procedures, Nuclear Document Distribution Procedures and Nuclear Department Manual Procedure The inspector reviewed the procedures in Section IV of Attachment B.
These procedures for document control were reviewed to verify that the program is consistent with the requirements and guidelines of the referenced documents in paragraph 5.0 and to assure that the program contains the following attributes:
Require that current as-built drawings, including p1p1ng and instrument drawings (P&ID's), will be provided to the plant site-in a timely manner; Require that proposed drawing changes and the revised drawings receive the same level of management review as originals; Provide provisions for identifying and marking drawings with outstanding revisions; Establish control of obsolete drawings; Require that discrepancies found between as-built drawings and the as-constructed facility are handled as design changes; Require master indices to be maintained for drawings, manuals, technical specifications and, procedures that indicate the latest revision; Periodic review of master lists to verify Technical Specifi-cation changes are incorporated into appropriate procedures, instruction and drawings; and Provide a mechanism for document issuance, distribution, use and periodic revie.2 Implementation The inspector selected a random sample of controlled documents to de-termine their consistency with master indice The controlled docu-ments examined (listed in Section IV, Attachment C) included manuals, FSAR, Technical Specifications, vendor information, procedures and drawing The inspector verified that the revisions of the selected controlled copies located in the Engineering Records Center, Control Room, Technical Document Room (TOR), Maintenance department, station Quality Assurance group, management offices and the Engineering and Plant Betterment Department were consistent with the applicable mas-ter indice The inspector also walked down a portion of the Service Water system and determined that the controlled drawing accurately reflected the installation in the field.
- Findings The licensee is currently transferring controlled document distri-bution responsibilities from the releasing organizations to the Doc-ument Distribution Group (DOG).
The DOG to this time has taken over the distribution of drawings, maintenance procedures, administrative procedures, department manuals, and various other controlled docu-ments at Salem with plans to eventually perform all controlled doc-ument distributio The DOG utilizes a computer based index to generate Document Distribution Notices (DON) to distribute control-led document distribution and track the receipt of such documents by the copyholder The methods and procedures utilized by the DOG were found to be adequat The Licensing and Regulation department is currently responsible for the distribution of Technical Specifications and the Safety Analysis Report, however, plans exist to relinquish this function to the DO The inspector reviewed the current method employed by the group to insure copyholders receive the latest revisions and found it ade-quat The Engineering & Plant Betterment department has been utilizing interim procedures for the control of design drawing A new pro-cedure, GM8-EMP-004 11Design Drawing Control 11, has been written and is scheduled for implementation by the end of July 198 The inspector reviewed the draft procedure and determined that it adequately es-tablished administrative controls for design drawing While verifying the revisions of copyholder controlled documents the inspector noted that the Maintenance Department did not have two on-the-spot changes to procedure M36, 11Motor Operated Valve Testing 11,
incorporated in their controlled copy of maintenance procedure The inspector verified that the documents had been transmitted from the DOG and determined that they had apparently been misplace The maintenance department took corrective action by requesting another copy of the change The inspector verified that the field copies used for work were the latest revision with changes incorporate The inspector determined that of all the documents reviewed this discrepancy was an ~solated cas The attributes of the document control program reviewed were adequat No violations were identifie.0 Unresolved Items Unresolved items are matters about which more information is required in order to ascertain whether they are acceptable items or violation An Unresolved item is discussed in paragraph * Management Meetings Licensee management was informed of the scope and purpose of the inspection at the entrance interview on June 30, 198 The findings of the inspection were discussed with licensee representatives during the course of the in-spection and presented to licensee management at the July 8, 1986 exit interview (see paragraph 1 for the attendees).
At no time during the inspection was written material provided to the licensee by the inspector The licensee indicated that no proprietary information was involved within the scope of this inspectio *
ATTACHMENT A Requirements/References Quality Assurance Program CFR 50, Appendix B, Criterion II CFR 50.54(a)(l) FSAR Chapter 17 Regulatory Guide RG 1.33, Revision 2, Quality Assurance Program Requirements (Operational) and Training Nuclear Quality Assurance Department Manual I Measuring and Test Equipment CFR 50, Appendix B, Criterion XII IEEE 498-1980, 11 IEEE Standard Requirements for the Calibration and Control of Measuring and Test Equipment Used in Nuclear Facilities 11 FSAR Chapter 1.
RG 1.33 Nuclear Quality Ass~rance Department Manual III. Records Mana_g_§!tnent, CFR 50, Appendix B, Criteria XVI.
Technical Specifications, Section 6, Administrative Control.
Final Safety Analysis Report (FSAR), Sections 17.2.17 and 1.
ANSI N45.2.9-1974, Requirements for Collection, Storage, and Mainten-ance of Quality Assurance Records for Nuclear Power Plant.
Regulatory Guide 1.88, Rev. 2, Collection, Storage and Maintenance of Nuclear Power Plant Quality Assurance Record.
ANSI 18.7-1976, Administrative Controls and Quality Assurance for the Operational Phase of Nuclear Power Plant.
ANSI N45.2-1979, Quality Assurance Program Requirement.
NFPA No. 232-1975, Standard for Protection of Records I Document Control CFR 50, App. B, Criteria II, V, VI Tech Specs, Section 6, Administrative Control Final Safety Analysis Report (FSAR) 17..
ANSI N45.2 - 1979, Quality Assurance Program Requirements ANSI N18.7 - 1976, Administrative Controls and Operational Quality Assurance for the Operational Phase of Nuclear Power Plants Regulatory Guide 1.33, Rev. 2, Quality Assurance Program Requirements (Operation)
- ATTACHMENT B Procedures Reviewed Quality Assurance Program Vice President - Nuclear Procedure VPN-QAP-01, Revision 0, Operational Assurance Program Administrative Procedure (AP) 9, Revision 9, Maintenance Program I Measuring and Test Equipment VPN-PLP-07, Revision 0, Measuring & Test Equipment Administrative Procedure (AP) 9, Revision 9, Maintenance Program AP 22, Revision 7, M&TE Control Program Maintenance Procedure A-9, Revision 11, Control and Calibration of Measuring and Test Equipment (M&TE) Operations Department (DD) Directive 22, Revision 0, Control of Test Equipment Instrument & Cuntrol Manual (ICM) 1 Revision 0, Control of Test Equipment Nuclear Procurement and Material Control Procedure Mll-P-550, Revision 2, Contrrl of Calibrated Measurement and Test Equipment III. Records Management AP-11, Record Retention Program, Rev. 8, April 8, 1986 QAP-8-1, Records Control, Rev. 2, March 31, 1986 VPN-MSP-07, Re.cords Management, Rev. 0, June 22, 1984 VPN-MSP-07, Records Management, Rev. 1, Draft M28-RMP-003, Training of Personnel, Rev. 1, November 19, 1985 M28-RMP-108, Destruction of Records in Storage, Rev. 0, November 19, 1985 M28-RMP-113, Operation of the Temporary Storage Facility, Rev. 1, November 19, 1985 M28-RMP-112, Development and Maintenance of the Records Transfer Schedule, Rev. 0, November 19, 1985 M28-RMP-110, RMS Control and Maintenance, Rev. 1, November 19, 1985 1 M28-RMP-107, Off-Site Storage of Records, Rev. 1, November 19, 1985 1 M28-RMP-101, Records Processing and Maintenance at the Central Records Facility (CRF), Rev. 2, November 19; 1985
Attachment B Maintenance Procedures M3L, Unit 2 Motor Operator Valve Testing, Rev. 11, Change 2, March 27, 1985 M19B, Main Turbine Over Speed Protection Valve Examination, Rev. 2, November 8, 1984 Administrative Procedures AP-07, ALARA Program, Rev. 1, December 23, 1985 AP-08, Design Change, Test and Experiment Program, Rev. 7, March 15, 1985 I Document Control QAP 8-2, Document Control, Rev. 1, March 5, 1986 VPN-MSP-05, Document Control, Rev. 0, October 31, 1984 VPN-ADP-10, Correspondence Control, Rev. 0, September 28, 1985 AP-03, Document Control Program, Rev. 13, December 12, 1985 GM8-EMP-004, Design Drawing Control, Rev. 0, Draft M28-DDP-102, Receipt and Distribution of U.S. Mail, Rev. 0, December 28, 1984 M28-DDP-101, Distribution Control, Rev. 2, March 13, 1986 M28-DDI-001, Distribution Control, Rev. 0, April 15, 1986 Ml-LEP-2, License Change Requests and License Amendments, Rev. 0, June 12, 1984 1 Ml-LEP-6, Safety Analysis Reports Change Control, Rev. 0, June 19, 1986
ATTACHMENT C Quality Assurance Program Wor~ Order 07-03-168-6, Inspect Compressor for Missing Valve Spring VPN Letter to NRC Region I regarding submittal of QA Program Description I Measuring & Test Equipment QA Audit Reports: S-83-25; S-84-17; S-84-43; NS-85-015; and NM-86-04.
1985-86 Area/Functional Surveillance Audit Reports:
one in chemistry; one in I&C; three in plant equipment; and three in 11 various 11 areas/function.
Corrective Action Requests (CARs): 84-0004; Quality Action Requests (QARs): SS-86-Q020; Nuclear Department Calibration Laboratory's Overdue M&TE List Memoranda from Manager - Nuclear Procurement & Material Control to Department Managers regarding over due M&T.
Memorandum SQA-86-0304 of May 30, 1986 regarding control and calibration of contaminated M&T II Records Management Calculations EC-2063 Calculation 567871, Rev. IR-0 EC-2063 Calculation 567870, Rev. IR-0 Stress Calculation 5671767 Deficiency Reports MT-85-056, Mechanical Snubbers, February 23, 1985 (surveillance attached) SIC-85-0154, S.G. Blowdown Transmitter, March 18, 1985 SMD-85-3505, 22 Changing Pump Drain Valve, May 28, 1985 MT-86-0003, CVC Hanger, January 6, 1986 (surveillance attached)
Operator Logs Unit 1, December 18, 1984 Unit 2, December 18, 1984 Unit 1, June 5, 1985 Unit 2, June 5, 1985
- Attachment C Work Orders, Radiography on 11 and 13 MS46 Valves, March 5, 1985, Radiography on 21, 23 MS46 Valves, March 27, 1985, Perform MP2.11 Surveillance, April 5, 1986, Valve 21SW262P-3 has hole, March 27, 1986 (Maintenance procedure), Valve IVC5&6 Leak Test, September 11, 1985 (surveillance attached)
I Document Control Drawings, Unit 1 Auxiliary Feedwater, Rev. 22, March 12, 1986, Units 1&2 Diesel Engine Auxiliaries, Sheet 1, Rev. 20, June 3, 1986, Unit 2 Turbine Drains, Sheet 1, Rev. 11, August 7, 1984, Unit 2 Service Water-Turbine Area, Rev. 14, August 24, 1984, Unit 2 Containment Spray~ Rev. 15, June 2, 1986, Unit 1 4160V Group Buses One Line, Rev. 12, May 9, 1985, Units 1&2, 13kV Switchgear One Line, Rev. 4, July 23, 1980 Vendor Information, Pacific Pump SI Assembly Drawing J-127, Rev. 2, issued August 15, 1983, Crane Co. 10 11 to 12 11 150 #CS Gate Valves K-7359, Rev. C, issued April 22, 1985, Honeywell PP908 A&B Pneumatic Controllers Installation Instructions Form 95-5531, Rev. 9-68, issued September 20, 1983 Miscellaneous UFSAR, Rev. 4 Technical Specifications, Amendment 75 Nuclear Department Repair Program Manual, Rev. 1 First Issue, May 22, 1986