IR 05000354/1986004

Insp Rept 50-354/86-04 on 860107-10 & 13-15.No Violation Noted.Major Areas Inspected:Readiness for Implementation of QA Program for Operations & Tech Specs Re Design Changes/Mods,Tests & Experiments

ML20153D799
Person / Time
Site:	Hope Creek
Issue date:	02/13/1986
From:	Eapen P, Napuda G NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
To:
Shared Package
ML20153D789	List: IR 05000354/1986004 ML20153D787
References
50-354-86-04, 50-354-86-4, NUDOCS 8602240255
Download: ML20153D799 (6)

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U.S. NUCLEAR REGULATORY. COMMISSION REGION'I Report N /86-04 Docket No. 50-354 License No. CPPR-120 Licensee: Public Service Electric & Gas Company Post Office Box 236 4 Hancocks Bridge, New Jersey 08038

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Facility Wame: Hope Creek Generating Station Inspection At: Hancc ks Bridge, and Salem, New Jersey Inspection Conducted: January 7-10 and 13-15,1986 Inspector: #M Z //

G. Rapuda, Lead Reactor Engineer / #te Approved by: N. O 8 /S 'd Dr. P~. K. Eapen, Chire f, Quality Assurance '~datt Section, 08, DRS Inspection Summary: Inspection on January 7-10 and 13-15, 1986 (Report No. 50-354/86-04).

Areas Inspected: Routine announced inspection by a region-based inspector to assess the readiness for implementation of the QA Program for Operations and the TS in the areas of design changes / modifications; tests and experiments; onsite operations review committee; onsite independent safety review group; and, offsite safety review group. Also, previously identified items were followed u The inspection involved 74 inspection hour Results: No violations were identified nor were there any concerns that would impact on issuance of an O %

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h DETAILS Persons Contacted

• Butler, Principal Training Supervisor R. Burricelli, General Manager Engineering and Plant Betterment

• A. Giardino, Manager Station QA

• D. Cooley, Onsite Safety Review Engineer

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• R. Donges, Lead QA Engineer

• R. Edmonds, Assistant Manager of Nuclear Training J. Ellis, System Engineer Training Supervisor

• Griffith, Principal QA Engineer ,

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D. Hanson, Manager of Nuclear Training

• E. Liden, Manager Offsite Safety Review J. Nichols, Chairman Station Operations Review Committee

• R. Salvesen, General Manager Operations

"W. Schultz, Manager QA Programs and Audits T. Taylor, Manager Plant Engineering.and Betterment Controls NRC

• J. Lyash, Resident Inspector R. Borchardt, Senior Resident Inspector l

Other employees contacted included administrative, engineering, operations, QA/QC and technical personne * attended the January 15, 1986 exit intervie . Previously Identified Items (Closed) ijnresolved Item (85-33-01): Verify that the Station Operations Review Committee (50RC) is functioning in accordance with the TS, and admi-nistrative procedures describe the manner in which the committee executas its responsibilitie It was verified that the following issued procedures do describe the improved safety and technical review activities in suffi-cient detai SA-AP.ZZ-004(Q), Station Operations Review Committee, Rev. 4

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SA-AP.ZZ-032(Q), Review and Approval of Station Procedures and Procedure Revisions, Rev. 3 It was also verified that all department managers were involved in a special SORC meeting where the new procedures.were discussed and that -

other staff training was scheduled for January 21, 1986. The General Manager stated that full implementation of'the new review methodology is-scheduled for February 7,1986 or in any event prior to core load. This area was determined to be ready to support plant operations. This item is close . _ -

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(Closed) Unresolved Item (85-33-02): ' Verify that-the Offsite Safety Review Group has been staffed and is functioning in accordance with established procedures. The group has been staffed, has begun to function and proce -

dure.M40-POP-01, Offsite Review Group Organization and Responsibility, Revision ~0 has been issued. Current members exceed pdsition requirements and the one open position is to be occupied by a qualified contracted in-dividual on an interim _ basis until a permanent employee can be appointe This area was determined to be ready to~ support plant operation This item is close (Closed) Unresolved Item (85-33-03): Verify. that the'Onsite Safety Revie Group has been staffed and is functioning in accordance with established procedures. The group'has been established, is functioning and the follow-ing issued procedures describe their activities in sufficient detail.

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M20-POP-01, Safety Review Group, Revision 0 l-

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M20-MSP-01, Onsite Safety Review Group Manual Preparation and l Control, Revision 0 l

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M20-AP-01, Safety Review Group Recommendations, Revision 0 l

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M20-AP-02, Safety Review Group Independent Review of Reactor Scram /ECCS Actuation Events, Revision 0 Current members education and experience were reviewed._to verify they met position qualifications. Two contracted individuals were being considered to occupy the one open position on an interim basis until a permanent em-ployee could be assigned. Both individuals were determined to meet position requirements. This area was determined to be ready to support plant l operations.

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l This item is closed.

l Design Changes / Modifications 3.1 References / Requirements FSAR Section 17.2, Quality Assurance During the Operations Phase

, ANSI N18.7-1976, Administrative Controls and Quality Assurance l for the Operational-Phase of Nuclear Power Plants-

' ANSI N45.2.11-1974, Quality Assurance Requirement for the Design of Nuclear Power Plants f GM8-EMP-009, Operational Design Change Control, Revision 0 i

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, GM 8-1, Engineering and Plant Betterment Department Manual

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3.2 Program' Review The intent of this review was to ascertain the readiness of the licen-see's Design, Design Change and Modification, and Tests and Experiments Programs for,the operational phase of the statio Procedures were reviewed to verify that they provided sufficient detail and were con-sistent with the licensee's commitments. Employees were interviewed to determine that they were aware of their. authorities and responsi-bilities, and were knowledgeable-in applicable-procedures. Trainin and personnel records of selected employees were also reviewed to ve-rify that incumbents had adequate education and experience, or proper supplemental training for their positions. Records of com-

'pleted activities were reviewed to determine the effectiveness of the established program. When possible, ongoing activities were observed to assure they were accomplished in accordance with established pro-cedure The licensee'has recently completed a restructuring of those engineer-ing organizations that support plant operations. Department procedures and instructions have been completely rewritten-and issued. GM8-EM-009 and the Engineering Department Manual were reviewed and it was deter-mined that the following were established:

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A formal method for initiating design changes

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Measures to control modifications, design reviews and safety evaluations

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A metaod to assure that a change does not constitute an un-reviewed safety question as defined in 10 CFR 50.59

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Measures to control changes to previously approved documents, recall obsolete documents, and release and distribute approved documents

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Measures to include those temporary changes, tests and experi-ments, that were not described in the FSAR, into the modifica-tion control program

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Responsibilities to assure the implementation of the above have'

been delineated in writin .3 Implementation and Findings The engineering groups have.been restructured and the-engineering manual describes the organization, responsibilities and methods of implementation. Supplementary training for Systems Engineers is scheduled for the latter part of this year and will be similar to

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that currently being given to the Salem Station System Engineer ;

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The course was reviewed and discussed with Training Department snana-gers and instructor It is the.SR0 course.without the requirements'

of memorization of ' operating. procedures.and other details determined to be unnecessary for engineers. lhe-Licensed Operator Instructors-will also present the Hope Creek course. including simulator. trainin The training uses a Qualification Card system and the " objectives" are tasks extracted from the published System Engineer Job Analysi It was determined that this area 'is ready to support plant operation No violations were identifie . QA/QC Interfaces 4.1 Audits Audit S-NM-85-13, Engineering and Plant Betterment, was completed during this inspectio It was conducted by five auditors and a technical specialist (design engineer) using approximately 80 man days. The auditors determined that the engineering program had been improved but identified some implementati'on problems. The audit results were discussed with the team leader and it was concluded that the identified-deficiencies would not significantly impact the support provided for plant operations. The licensee acknowledged the statement that this area would be periodically reviewed during subsequent routine NRC inspection No violations were identifie .2 Training The QA/QC Inspector Training program was reviewed and discussed with Training Department managers and instructors. The individual courses were developed along INP0 Guideline 84-003 and the relevant Job / Task Analysis. Subjects such~as hydraulics, fasteners, valve operators and welding were addressed. It was noted that most of the traiaing courses involved hands-on application. The program was based on sound and valid educational principles. ' Student and instructor texts had been developed and were to be used for each cours Exams have been developed by QA to' determine the level et knowledg of. individuals' and are currently.being administered to .various depart-ment personnel. A test failure will indicate that the. individual requires additional training and specific courses from the above training program will be given to those individual No violations were identifie ,

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• Management Meetings-License management wa's informed of the scope and purpose of the inspection at the entrance interview on. January 6,1986. . The findings of the inspec--

tion were discussed with licensee representatives during the course of the inspection and presented to licensee management at the January-15, 198 exit interview (see paragraph 1 for attendees),

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At no time during the inspection was written material provided to the licensee by the inspectors.

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