IR 05000410/1986011
| ML17055B826 | |
| Person / Time | |
|---|---|
| Site: | Nine Mile Point  |
| Issue date: | 05/22/1986 |
| From: | Eapen P, Gilray J, Napuda G, Oliveira W NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML17055B825 | List: |
| References | |
| 50-410-86-11, NUDOCS 8606160264 | |
| Download: ML17055B826 (36) | |
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U.S.
NUCLEAR REGULATORY COMMISSION
REGION I
Report No.
50-410/86-11 Docket No.
50-410 License No.
CPPR-112 Licensee:
Nia ara Mohawk Power Cor oration 300 Erie Boulevard West S racuse New York 13202 Facility Name:
Nine Mile Point Nuclear Station Unit Two Inspection At:
Scriba and S racuse New York Inspection Conducted:
March 31 - A ri 1
1986 Inspectors:
eorg Napud
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Lead Reactor Engineer Joh Gilray, QA Branc IKE d
e
~z,o dat Approved by:
Wi l 1 i am 01 iveira, Reactor Engineer Or.
P.
K. Eapen, C ief, Quality Assurance Section, OB, ORS d te date Ins ection Summar
Routine announced ins ection on March 31-A ril 4 1986 Re ort No. 50-410/86-11 at the licensee s corporate offices in Syracuse, New York and the Nine Mile Nuclear Station by two Region based inspectors and an IE headquarters engineer.
for Operations in the area of Audits and QA/QC Surveillances; QA/QC Adminis-tration; Test and Measuring Equipment; non-licensed staff training; onsite operations review committee; onsite independent safety review group and offsite safety review committee.
Results:
No violations were identified.
i 8606160264 860605 l
PDR ADOCK 05000410
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DETAILS 1.0 Persons Contacted Nia ara Mohawk Power Cor oration
~R. Abbott, Station Superintendent
- W. Bryant, Manager, Corporate QA
~K. Dahlberg, Maintenance Superintendent
- W. Drews, Technical Superintendent M. Falise, Mechanical Maintenance Superintendent
~A. Kovac, QA Audit Supervisor
- T. Lee, Special Projects
"T. Lempges, Vice President, Nuclear Generation
~J. Orlando, QA Supervisor T. Perkins, General Superintendent
- J. Perry, Vice President, QA
- M. Ray, Manager, Special Projects
- C. Stuart, Assistant to Executive Director
"P. Wilde, QA Technician K. Zollitsch, Training Superintendent Stone and Webster En ineerin Cor oration
- J. Drake, Star t Up and Test Special Projects Supervisor Public Service Commission
- P.
Eddy U.S. Nuclear Re ulator Commission S.
Hudson, Senior Resident Inspector
- R. Gramm, Resident Inspector
- P.
Eapen, Chief, QA Section The inspectors also contacted other licensee technical and administrative personnel during this inspection.
- Denotes those present at the exit, meeting held on April 4, 1986.
2.0 gAAPro ram 2 '
Review Those documents listed in Attachment A that are preceded by an asterisk were reviewed to verify that implementing procedures con-tained adequate details and reflected the commitments and require-ments of the Quality Assurance Program Topical Report (QATR-l),
Revision t
The QATR-1 commits to industry standards ANSI/ANS 3.2-1982 (ANS 3.2),
Administrative Controls and Quality Assurance for the Operational Phase of Nuclear Power Plants; ANSI/ANS NQA-1-1983 (NQA-1) Quality Assurance Program Requirements for Nuclear Facilities; and ANSI/ASME NQA-2-1983 (NQA-2), Quality Assurance Requirements for Nuclear Power Plants.
2.2
~Finds n s
It was identified that most procedures still referenced those industry standards committed to in the licensee's Quality Assurance Program Description (QAPD) that was superseded by the QATR-l, such as ANSI N
18.7-1976 and the ANSI N 45.2 daughter standards 45.2.2, 45.2.3, 45.2.9, 45.2.11, 45.2.12 and 45.2.13.
In several instances procedures also referenced NQA-1-1983.
In one instance NQA-2-1982 was not referenced even though it was applicable to the procedure content.
Two computer matrices were developed to provide the procedure indices summary required by ANS 3. 2, paragraph 5. 1
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One was cross referenced to ANS 3.2 paragraphs and the second to NQA-1 sections.
A number of omissions were identified in these matrices.
The above and other editorial and minor discrepancies were discussed with licensee representatives who proposed actions discussed in para-graph 2.3 below.
2.3 Conclusions It was determined that the details contained in implementing proce-dures met or exceeded the intent and or requirements of the QATR-1 and referenced industry standards.
With respect to the discrepancies and omissions discussed in para-graph 2.2 the Vice President-Quality Assurance stated the following actions would be completed by commercial operation.
Implementing procedures would be reviewed to assure that super-seded references are purged and that these procedures clearly reflect commitments to ANS 3.2, NQA-1 and NQA-2.
These reviews would also be consistent with NRC disposition to the March 14, 1986 letter from C.
V. Mangan, Senior Vice President (licensee)
to E.
G.
Adensam (NRC), Director BWR Project Directorate No. 3.
This letter described the phase out and overlap of the construc-tion QA Program and Pre-operations QA program vice implementa-tion of the new operations QA program and associated commitments.
This is an unresolved item pending NRC verification of licensee's review and provision of implementing procedures during a subse-quent inspection(s)
(410/86-11-01)
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The ANS 3.2 and NgA-1 computer indexing would be reviewed to assure that elements in these standards are reflected.in and by the procedures listed in these matrices.
This item is unresolved pending verification of licensee action durin'g a subsequent inspection(s).
(410/86-11-02)
The details provided in the administrative control procedures were adequate for plant operations support and the above actions will mo-dify the procedures by commercial operation so as to reflect the standards committed to in the gA Topical Report.
No violations were identified.
3.0 Non-Licensed Staff Trainin
~ 1 General The inspection was to assess the effectiveness of the licensee's non-licensed training program.
As a representative sample, the inspector chose the training programs for instrument and control (IKC) techni-cians, electrical and mechanical maintenance personnel, and auxiliary operators (AOs).
The inspector noted that the licensee had received INPO accreditation for Nine Mile Unit 1 (NM1) in the following train-ing areas:
licensed operator (LO);
LO requalification; non LO; shift technical advisor (STA); chemistry technician; and radiological pro-tection technician.
The effectiveness of the existing program was determined by observing and/or reviewing the following:
An AO touring the lower reactor building area and removing a tag from a repaired valve.
Corrective maintenance of motor operated valves A radwaste operator performing a valve line up.
Operation of an RHR pump by AOs during a test.
Loop calibration report (LCR) of the primary containment drywell outboard isolation valve.
Spray actuations.
Six corporate audit reports.
Training records of two training supervisors and three instruc-torss, one On the Job Training (OJT)'evaluator, maintenance manager, four maintenance supervisors, three mechanics, two IKC technicians, radwaste supervisor and operator, one STA, four AOs, and one enginee.2 Details of the Review For each of the job functions identified in paragraph 3. 1, the inspec-tor reviewed the established training program, implementing procedures, qualification, and experience of personnel, qualification and training of instructors, quality of OJT, and the effectiveness of training as evidenced in daily activities.
The comments and evaluations from the trainees, line supervi sors, and instructors were also reviewed to establish how this feedback was factored into future training.
The management's involvement in the training area was assessed to deter-mine their effectiveness.
3.2. 1 Observation of Work Activities The inspector witnessed the work activities identified in Section 3. 1 above.
The activities were conducted in accordance with the procedures by personnel knowledgeable in the requirements of the procedures and Technical Specifications.
This was especially evident in the following:
In conducting the mark up for drywell equipment drain (DER)
valve 2 DER*MOV-119, the AO noticed that one valve in the line up had a missing tag.
The AO noted this problem on his mark up sheet and also notified the control room.
The valve was later tagged properly.
Valve 2 DER"MOV-119 failed its leak rate test and corrective maintenance was performed in accordance with Work Request (WR) no.
012809.
Maintenance personnel found cloth material in the bottom of the valve and the problem was being inve-stigated by the Engineering Department.
The work was cover-ed by quality control (gC) inspectors.
Corrective maintenance to the Limitorque MOV 2CSL~FV-114 included degreasing the operator and elimination of an oscillation problem.
The work was being done in accordance with WRs 3678, 7746 and 007973.
The inspector observed the operator being greased after the old grease had been removed.
The elimination of the oscillation was under discussion and one proposed solution was to replace the motor.
The radwaste operator conducted the valve line up in accord-ance with procedure 10P40, Liquid Radwaste System, Revision 0.
After conducting the transfer from the waste collection tank to the recovery sample tank through the radwaste demi-neralizer, the operator notified the Control Room to start the transfer operation.
During the operation, the operator checked the conditions of the plant equipment and conti-nually kept the Control Room advise Although the operation of the RHR pump and the suppression spray were conducted in accordance with pre-operational test (POT)-31, the AOs were able to explain how the equip-ment would operate during the operational phase.
guality Control provided inspection coverage to this test.
3.2.2 Trainin Polic and Pro ress The Inspector performed a review of selected procedures of the non licensed operators (NLO), Electrical and Mechanical training programs.
The licensee policy and planning in FSAR Chapter
and Nuclear Training Instructions (NTI) 1. 1 and 4.5, address the basis for and the commitment to formal training, on-the-job (OJT)
training, and measuring the program's effectiveness.
A key pro-cedure is NTI 4.3, Training System Development (TSD) of Training that describes the method used to complete the development of the training program.
NTI 4.3 also references the INPO docu-ments for developing the training program but is dependent on the other NTIs which also reference INPO documents.
This is an indication of Niagara Mohawk Power Corporation's (NMPC) commit-ment to obtain INPO accreditation.
The selected procedures and documents reviewed are listed in Attachment B.
Individual OJT manuals have been developed for ISC technicians, mechanics and electricians.
The manuals will be i ssued when the respective departments determine which of their personnel are exempted from specific OJT tasks.
These manuals are expected to be issued by mid April 1986.
Continued training will be provided to all personnel.
In the case of mechanics, training including requalification will be "upon request" by the mechanic.
The Inspector reviewed the training records of one manager, seve-ral supervisors, one STA, one training evaluator, several AOs, I5C technicians, mechanics and electricians.
The training re-cords were easily accessible, current and complete.
Except in the case of a union representative, the craft personnel were not involved in the developement of the training programs.
The Training Center is in the process of distributing post-train-ing surveys and instructors will increase their followup of post training actions with the craft personnel as well as supervision.
The craft personnel interviewed were enthusiastic about the training program, especially in'he OJT area.
They considered the instructors to be knowledgeable and competent.
The instruc-tors rated their training as excellent.
The instructors also found management to be supportive in the preparation and imple-mentation of training courses.
The instructors and students found the training material and facilities to be excellen.2.3 A/
C interface with Non-License Staff Trainin and Performance Two QC inspectors were observed providing QC coverage during the corrective maintenance action for the valve 2 DER*MOV-119 that failed the leak rate test.
A QC inspector provided coverage for spray actuations.
Four of the six corporate audits reviewed had identified train-ing problems as they relate to Unit 1.
The audits were thorough and utilized checklists.
Preparation and supportive information were also in the audit file.
The corrective action was timely and complete.
The licensee representatives informed the inspec-tor that corporate training audits were not yet conducted at Unit 2.
No violations or deviations were identified.
4.0 Measurin and Test E ui ment METE The inspector reviewed the documents in Attachment A and determined that the established controls for the M&TE Program addressed the following:
Responsibilities for establishing and implementing an M&TE Program are delineated.
Development of an equipment inventory list including addition of new equipment.
Identified the calibration status of M&TE.
Established a recall system including the calibration/adjustment frequency.
Out-of-calibration controls and traceability to previously tested or measured items.
4.2 Pro ram Im lementation The inspector randomly selected M&TE that were being used in the field and verified the calibration status, storage, issuance, use and return of M&TE as well as the recording of the data.
The craft and technicians were knowledgeable in the use and care of the M&TE and their respective procedures, especially the need for using cali-brated M&TE.
The technicians also knew the procedural requirements for reporting damaged M&TE and installed instruments that were pro-viding questionable result ;I
The I&C METE program for Unit 2 is in a transition phase.
I&C is still involved with pre-operational and startup (SU) activities.
For example, METE that is maintained and controlled by I&C for SU has not been formally turned over to ILC.
This equipment will be given new identification and wi 11 be controlled by AP 8.4 when SU relinquishes its control.
Maintenance management decided to keep their M&TE program under AP 8.4 to avoid the transition phase problems experienced by I&C.
The Maintenance Calibration Room attaches a copy of the calibration work sheet to the WR when issuing equipment.
This action is to assist the craft to easily trace previous measurements in case the equipment is out of calibration.
Additionally, equipment such as torque wrenches are recalibrated when returned to the Calibration Room.
4.3 The METE observed being used at the work sites and the calibration rooms included:
3 torque wrenches; a dial indicator; 3 Fluke voltmeter s
a strobe light; a stop watch; and 2 pressure gages.
~Findin s
The inspector observed that installed ammeters in the Control Room for service water pumps PIB, PID, and PIF did not have calibration labels.
Also, a test engineer was observed transmitting information
'from ammeter PIB via a telephone.
The Meter and lest group provided the inspector 1984 calibration records that indicated the PIB and PID ammeters had "test failed for records only".
The licensee investi-gated the status of the failed ammeters and found that they had been replaced and were waiting a check of the new scale face (i.e, scale change from 75 to 100 amp) prior to placing a calibration label on the ammeters.
The inspectors met with the SU supervisor and his staff.
From this, it was established that the telephone information provided by the test engineer was not used for acceptance purposes.
Further, a
SU prerequisite for testing is the test en'gineer's veri-fication that all system instrumentation is within current calibra-tion.
No violations were identified.
A/ C Interface in the Measurin and Test E ui ment Pro ram Corporate audit SY-RG-IN-85002 of System Standards Laboratory (Syracuse)
issued in August 1985 identified several deficiencies.
One deficiency regarding use of outside laboratories not approved by QA was discussed with site QA audit personnel.
The QA supervisor was able to produce evidence that the laboratories in question did not provide services during the period identified in the audit.
The laboratories have since been approved and were on the qualified contractors list.
No violations or deviations were identifie.0 Onsite Review Committee 5.1.
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The Station Operation Review Committee (SORC) is the licensee's onsite review committee.
The inspector reviewed plant administrative procedures (see Attachment A) applicable to the SORC to determine whether administrative controls have been established for the follow-ing.
Independent review authority and responsibility.
Ensuring the completion of reviews required by Technical Specifications.
Membership, alternate members, and quorum requirements.
Meeting frequency, maintenance and distribution of minutes/
records.
Lines of communication and interface with other groups such as the offsite review committee.
5.2 Im lementation and Or anization The committee has been established and functioning for several years with respect to Unit 1 and is fulfillingits Unit 2 current respon-sibilities.
Objective evidence that the committee was fulfillingi'ts Technical Specifications (TS) responsibilities such as review and approval of plant procedures, routing slips to members of review items, several meeting minutes, and Outstanding Items List (computer printout) were reviewed.
The onsite organizational structure, positions occupied by SORC members and the assistance available to members for accomplishing day-to-day duties were analyzed and discussed with various licensee representatives.
It was determined the demands of job and committee responsibilities were unlikely to r educe a member'
performance in either position.
Position descriptions, education, experience and training of the SORC members and selected alternates were reviewed to verify compliance with the proposed TS (November 1985 "Proof and Review" draft) and the FSAR (up to Amendment 59).
The April 1, 1986 meeting was attended in its entirety to observe the functioning and interaction of members.
The following were some of the practices note II ~
10'ngineers responsible for three modifications gave presenta-tions, provided additional information and answered questions as needed.
Discussions involved details such as location, maintainability and accessibility of components and equipment in or nearby the modified system.
Feasibility of reducing items in the TS and incorporating them into plant procedures was discussed.
Most of the procedure and technical reviews are done by a pool of qualified Technical Reviewers.
5.3 Conclusions Based on the results of the review performed in this area, the onsite review committee and current status of operational implementation is in compliance with TS and FSAR commitments.
It was also determined that the committee is ready to support plant operations.
No violations were identified.
6.0 Offsite Review Committee The S
6. 1 afety and Audit Review Board (SRAB) is the licensee's offsite review committee.
The SRAB manual (see attachment A) was reviewed to determine whether administrative controls have been established for the following.
Independent review and audit authority and responsibility.
Manner by which TS Section 6 reviews and audits will be accomplished.
Membership, alternate members, and quorum requirements.
Meeting frequency, maintenance and distribution of minutes/records.
Lines of communication and interface with other groups such as the onsite review committee.
6.2 Im lementation and Or anization The committee consists of eleven members including the chairman.
The chairman, secretary and five members are licensee employees ranging from one lead discipline engineer to managers.
Two other members are con-tracted consultants, one is a manager level Nuclear Steam System Supplier (NSSS)
employee and one is a Yice President with another utility that owns nuclear plant The committee has been established and functioning since 1969 with respect to Unit 1 and has been fulfillingits appropriate Unit 2 responsibilities since 1984.
Objective evidence such as meeting minutes and the contents of the review package for the March 20, 1986 meeting were reviewed to verify the committee was fulfilling its TS responsibilities.
The review package included Licensee Event Reports, gA and SRAB audit reports, NRC correspondence and inspecti,on reports, modification safety evaluations (Unit 1), preoperational tests (Unit 2), Management Performance Reports and SORC meeting minutes.
Organizational charts, positions occupied by SRAB members and the assis-tance available to members (employees)
for accompli shing day-to-day duties were analyzed and discussed with various licensee representatives.
It was determined the demands of job and committee responsibilities were unlikely to reduce a member's performance in either position.
The consultants and NSSS members contribution are contractually controlled and the other utility Vice President's participation is delineated in a written reci-procal agreement.
The position description (employees),
education experience and training of the SRAB members and alternates were reviewed to verify compliance with the TS (November 1985 "Proof and Review" draft) and the FSAR (up to Amend-ment 59).
Other facets of committee activities reviewed included the following'S audits are conducted by SRAB member s, gA or third party contractors.
A SRAB member is on every TS audit team.
Day-to-day controls of business items are tracked by computer.
Agenda items and their completion or status are tracked by computer.
6.3 Conclusions Based on the results of the review performed in this area, the offsite review committee and its current status of operational implementation are in compliance with the TS and FSAR commitments.
It was also determined that the committee is ready to support plant operations.
No violations were identified.
7.0 Inde endent Safet En ineerin Grou ISEG 7.
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The inspector reviewed implement,ing procedures (see Attachment A)
to determine whether the following had been accomplishe ) ~4 I
Procedures were established in accordance with regulatory requirements and licensee commitments.
The organization was delineated and staffed to meet regulatory requirements.
Organizational independence existed and interfaces were deli-neated.
Appropriate responsibilities were established and assigned.
Procedures were established for the control of ISEG activities.
Provisions were established to assure that records are properly maintained and transferred to a storage facility.
Administrative controls were established to support the required organizational responsibilities.
Provisions were established to assure that ISEG receives infor-mation and intelligence gathering resource materials upon which to base its reviews and activities.
7.2 Im lementation and Or anization The group has been established and is currently reviewing the backlog of INPO letters and notices; NRC Bulletins, Circulars and Generic Letters; and NSSS letters and Notices.
Approximately 40 NRC items remain to be reviewed and a formalized program to review INPO items has yet to be initiated.
NRC items have been prioritized and NSSS safety related items identified.
All incoming items are logged, assigned and tracked to completion.
Document Review Forms are used for review comments which must be dispositioned by originators and the form returned to ISEG.
Fifteen individuals are now participating in review activities.
The group is directed by the Technical Supervisor who identified five group members who will become permanent incumbents and stated a
contracted individual wi 11 also be assigned to the group unti 1 experience indicates five permanent members are sufficient for effective group functioning.
The six individuals selected for permanent membership include educa-tion in Chemical, Mechanical and Nuclear Engineering and Physics.
gualifications range from minimum requirements to extensive experi-ence.
One individual formerly was a member of an ISEG at another utility's nuclear plan E
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7.3 Conclusions Based on the review performed in this area, the ISEG is in compliance with the TS and FSAR commitments for the current status of opera-tional activities.
It was also determined that the group is ready to support plant operations.
No violations were identified.
8.0 ualit Assurance/Control Administration and Overview 8. ~~ R~i Quality assurance program documents were revi ewed to determine that the following administrative controls have been established for the QA/QC overview effort, as appropriate.
Independence, qualification and training of QA/QC personnel.
Documentation and review of corrective actions.
Inspection requirements and acceptance criteria.
Audit program scope.
Audit followup and re-audit.
Planning and conducting audits.
Long range audit scheduling.
Audit report distribution and required response.
Periodic review of the audit program.
Surveillance of ongoing activities.
8.2 Audits Seven audits of Document Control, Records and Corrective Action were reviewed and it was verified that they were conducted in accordance with NQA-1 requirements and/or licensee commitments including the following.
In accordance with a written checklist covering the scoped audit area.
By a qualified/trained person independent of the authority over the area audited.
Identified deficiencies were documented and reviewe ~
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Corrective action and followup were adequate and timely.
Audit frequencies and general audit conduct was in accordance with the established schedule and procedures.
8.3 Im lementation and Or anization The Vice President of Quality Assurance reports directly to the President of Niagara Mohawk Power Company (NMPC).
The department has five divisions each reporting to a manager.
The function and staffing of three divisions responsible for overview of operational activities were reviewed and the following noted.
The Nuclear QA Operations Division has in excess of 40 NMPC employees and approximately 36 contracted individuals.
Most, if not all of the contractors are involved with preoperational activities.
This division will conduct in-plant audits, QA surveillances and QC inspections.
The Corporate Quality Assurance Division has in excess of 20 NMPC employees and three contracted individuals.
This division conducts internal audits of offsite support and assists in-plant auditing as needed'
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The Quality and Reliability Engineering Division has in excess of 25 NMPC employees and is involved in vendor control, quality engineering, materials engineering and reliability engineering.
The education, experience, qualifications and training of several individuals were reviewed and all exceeded minimum requirements of the QATR-1.
8.4 Conclusions It was concluded that the QA Department is adequately staffed (approx-imately 4 permanent positions are unfilled).
The mechanisms for long range planning are in place and personnel are qualified.
It was also determined that, the department is implementing their current assigned responsibilities and is prepared to support operation of the plant in a manner similar to that for Unit l.
No violations were identified.
9.0 Unresolved Items Unresolved Items are matters about which more information is required in order to ascertain whether they are acceptable items or violations.
Unre-solved items are discussed in paragraph f,p
10.0 Mana ement Meetin s
Licensee management was informed of the scope and purpose of the inspection at the entrance interview on March 31, 1986.
The findings of the inspec-tion were discussed with licensee representatives during the course of the inspection and presented to licensee management at the April 4, 1986 exit interview ( see paragraph 1 for attendees).
At no time during the inspection was written material provided to the licensee by the inspector ~
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ATTACHMENT A Documents Reviewed Nuclear Training Procedure (NTP) -3, Revision 1, Training for Electricians NTP-7, Revision 7, Training and Continued Training of Instrument and Control Technicians NTP-9, Revision 1, Training for Mechanics NTP-12, Revision 0, Unlicensed Operator Training Administrative Procedure (AP) No. AP-8. 1, Revision 0, Preventive Maintenance AP-8.2, Revision 0, Surveillance Testing and Testing Program AP-8.3, Revision 0, Inservice Inspection and Testing Program AP-8.4, Revision 2, Procedure for Control and Calibration of Equipment Used in Tests and Inspections AP-3.3.2, Revision 1,
Placement of Jumpers or Blocks or Lifting of Leads AP-9.0, Revision 0, Administration of Training AP-4.0, Revision 3, Administration of Operations Quality Assurance Procedure (QAP) No. 2. 10, Revision 6, Training QAP-12. 10, Revision 3, Control of Measuring and Test Equipment Niagara Mohawk Power Corporation (NMPC) Nine Mile Nuclear Station Unit 2 Pre-paredness for Operating Plan Evaluation Report dated February 7,
1986 Nuclear Training Instruction (NTI)-3.1, Revision 2, Instructor Certification NTI-3.3, Revision 4, Vendor Instructor Qualifications NTI-4. 1, Revision 0, Training System Development Analysis NTI-4.4. 1, Revision 0, Job Analysis NTI-4.2, Revision 2, Training System Development NTI-4.3, Revison 3,
TSD Development of Training NTI-4.4, Revision 2, TSD Implementation of Training
2'ttachment A
NTI-4.4.2, Revision 2, Conducting Training NTI-4.4.6, Revision 0, Implementation of O.J.T.
NTI-4.5, Revision 3, Evaluation of Training NTI-4.5.1, Revision 4, Training Modification Recommendation Corporate Audit Report SY-RG-IN-85014, Nuclear Design Engineering and Staff Services, 1/8/86 Audit Report SY-RG-IN-85009, I&C Department Unit 1, 8/19/85 Audit Report SY-RG-IN-85011, Training Department at Nine Mile Unit 1, 10/7/85 Audit Report SY-RG-IN-85002, System Standards Laboratory, 5/13/85 Audit Report RG-IN-SY-8400, Maintenance at Nine Mile Unit 1, 12/12/84 Audit Report RG-IN-SY-84007, QA System Services and Procurement QA, 12/20/84
- Quality Assurance Procedures Manual
"Nuclear Engineering Procedures Manual
- Procurement Procedures Manual
- Plant Administrative Procedures (Eight)
Office Instruction (OI)-18, Revision 2, Instructions for SORC Records OI-19, Revision 0, Items for SORC Review Technical Department Procedure (TDP)-9, Revision 0, Independent Safety Engineering Group TDP-5, Revision 0, Administration of Operational Engineering Assessment Items The Safety Review and Audit Board Information Guide-1983 (a manual of responsibilities, Charter, etc.)
Reviewed for adequate details and inclusion of Quality Assurance Topical Report (QATR-1) commitments and requirement,
ATTACHMENT B Non-Licensed Staff Trainin Re uirements/References
CFR 50, Appendix B, Criterion II FSAR Chapters 13 and
Regulatory Guide RG 1.8, Revision 2, Personnel Selection and Training RG 1.58, Revision 1, Qualification of Nuclear Power Plant Inspection, Examination, and Testing Personnel Niagara Mohawk Power Corporation QA Topical Report, (NMPC-QATR-1)
Technical Specifications (TS), Section
ANSI/ANS 3. 1 1978, Selection, Qualification and Training of Personnel for Nuclear Power Plants I