ML20199F038

Insp Repts 50-219/86-15 & 50-289/86-08 on 860430-0502.No Violations Noted.Major Areas Inspected:Independent Safety Reviews & Overviews by General Ofc Review Board,Audits & Previously Identified Items

ML20199F038
Person / Time
Site:	Oyster Creek, Three Mile Island, 05000000
Issue date:	05/30/1986
From:	Eapen P, Napuda G NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
To:
Shared Package
ML20199F011	List: ML20199F005 ML20199F038
References
50-219-86-15, 50-289-86-08, 50-289-86-8, NUDOCS 8606240175
Download: ML20199F038 (6)

See also: IR 05000219/1986015

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U.S. NUCLEAR REGULATORY COMMISSION

REGION I

Report Nos. 50-219/86-15

50-289/86-08

Docket Nos. 50-219

50-289

License Nos. DPR-16

DPR-50 Category C

Licensee: GPU Nuclear Corporation

100 Interpace Parkway

Parsippany, New Jersey 07054

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GPU Nuclear Corporation

Post Office Box 480

) Middletown, Pennsylvania 17057

j Facility Names: Oyster Creek Nuclear Generating Station

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Three Mile Island Nuclear Station, Unit 1

4 Inspection At: Parsippany, New Jersey

i Inspection Conducted: April 30 - May 2, 1986

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Inspector: [ h4 Id #

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G.fNapuda,LeadReactorEngineer gArate

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Approved by:

Dr. P. K. Eapen, Chief

N. ket///vt - NDd4

/ dat'e

l Quality Assurance Section, 08, DRS

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1 Inspection Summary: Routine announced inspection on April 30-May 2, 1986

j (Combined Report Nos. 50-219/86-15; 50-289/86-08)

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Areas Inspected: Independent safety reviews and' overviews by the General Office

Review Board (GORB), audits and previously identified items by one region-based

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inspector.

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Results: No violations were identified.

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8606240175 860618

PDR ADOCK 05000219

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j DETAILS

1.0 Persons Contacted

GPU Nuclear Corporation

• I. Finfrock, Jr., Chairman General Office Review Boards (G0RBs)

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R. Markowski, QA Program Development / Audit Manager

R. Whitesel, Vice Chairman GORBs

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! Other licensee administrative and technical personnel were also contacted

j during the inspection.

* Denotes those present at the exit meeting held May 2, 1986

2. Previously Identified Items

(0 pen) Violation (289/85-27-07). Failure to properly implement the onsite

independent safety review process.

Based on the review of the status of the corrective action and program

implementation discussed in paragraph 4.0 this item remains open pending

further review of program implementation.

3. Offsite Independent Review

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j 3.1 Procram

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A General Office Review Board (G0RB) has been established for the

Oyster Creek (OC) Station and another for Three Mile Island, Unit 1

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(TMI-1). The primary responsibility of the GORB is to independently

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consider potentially significant nuclear and radiation matters in-

ciuding related management aspects of those matters. A secondary

responsibility to consider potentially significant industrial safety

matters. The GORBs provide advice and report directly to the Office

, of the President. The GORB makes written recommendations to the

1 Chief Operating Officer or appropriate Vice President and requires

written responses by the addressees.

The documents listed in Attachment A were reviewed to determine the

following had been accomplished.

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Procedures were established in accordance with regulatory

requirements and licensee commitments.

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The organization was structured and staffed to meet QA Program

requirements.

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Organizational independence existed and interfaces were delineated,

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Appropriate responsibilities were established and assigned.

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-- Procedures were established for the control of GORB activities;

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Provisions were established to assure that records are properly

maintained and transferred to a storage facility;

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Administrative controls and human resources were established to

support the required organizational responsibilities;

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Provisions were established to assure that GORB receives infor-

mation and intelligence gathering resource materials upon which

< to base its reviews and activities.

3.2 Organization and Staffing

Each GORB has eleven members including the Chairman and Vice Chair-

man. One but not more than two members are from the operating

j organization, one from the engineering organization and five from

outside the General Public Utilities (GPU) employee group. Admi-

nistrative and technical resources are provided by the Nuclear Safety

j Assessment Department (NSAD). The collective expertise of each GORB

includes nuclear station design, nuclear power plant operation,

materials, engineering (nuclear, mechanical, electrical), instrumen-

tation and controls, quality assurance, training and human factor

analysis, safety analysis and accident control, radiation safety,

metallurgy, chemistry and radiochemistry. The four permanent

GORB major issue committees that have been established are Risk and

Control Process, Human Factors, Hardware and Radcon, and Modifica-

tions and Maintenance.

3.3 Implementation and Findings

GORB meeting minutes between November 1984 to March 1986

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(Nos. 105-113) and December 1984 to April 1986 (Nos. 62-70) for

OC and TMI-1 respectively were reviewed and the following were noted.

2

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GORB met every second month;

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Meetings were held onsite and lasted a minimum of two days;

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Presentations were given by the plant Review Group, Independent

Onsite Safety Review Group, GORB committees and Quality

Assurance;

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Subjects reviewed and discussed included Licensee Event Reports,

Technical Specification changes, response to NRC IE inspection

reports, industrial safety, plant status, outage schedule, Ap-

pendix R modifications, non-licensed training, reliability and

i risk assessments, and QA audit adverse findings and responses;

)

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Recommendations and Action Items were discussed at each meeting,

documented, and tracked through close out;

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Meeting minutes were formatted to the standard agenda;

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The Chairman of the GPU Board of Directors and board members

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observed a number of GORB meetings and on occasion attended the

full two day sessions;

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GORB members had extensive experience and most held post gra-

duate university degrees;

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Recommendations were well formulated, received prompt attention

j and close out actions were adequate (random samples);

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GORB was persistent in pursuit of the satisfactory close out of

their items.

No violations were identified.

4. Nuclear Safety Assessment

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The independent technical and safety review of procedures and other deve-

loped documents (e.g. modifications, specifications, Technical Specifica-

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I tion changes) are performed by individuals in a pool of reviewers. Master

! matrices contain the names of qualified technical and independent safety

} reviewers at both stations and the corporate offices. Each organization

division has a Technical Review Coordinator who assigns the reviews to

] individuals selected from the matrices. The technical reviewer may be

j from the same division as the originator but the independent safety review-

er must be from another division.

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A review of the limited amount of work accomplished since recent revisions

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to implementing procedures (see paragraph 2) indicated the following.

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A bi-monthly report was transmitted to the NSAD Director;

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The Independent Onsite Safety Review Group (ISORG) has had no recent

recommendations;

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The ISORG reviewed TS Change Request No. 112 and " signed off" the

j cover sheet;

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The annual review cycle for the review of trends in functional area

performance is not yet due.

No items violations were identified.

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! 5. Audits

Audit packages S-0C-83-13, Safety Review; S-TMI-86-04, TMI-1 Safety

Review (a draft); and 0-0C-85-04, Safety Review Program were reviewed and

i verified that:

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The audits were conducted in accordance with a written checklist

covering the scoped audit area;

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The audits were conducted by qualified / trained personnel independent

j of the authority over the area audited;

-- The identified deficiencies were documented and reviewed;

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Corrective action followup was adequate and timely;

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Audit frequency and general audit conduct were in accordance with the

, established schedule and procedures.

! No violations were identified.

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i 6. Management Meetings

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Licensee management was informed of the scope and purpose of the inspec-

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tion at the entrance interview on April 30, 1986. The findings of the

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inspection were discussed with licensee representatives during the course

of the inspection and presented to licensee management at the May 2, 1986

exit interview (see paragraph 1 for attendees).

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i At no time during the inspection was written material provided to the

licensee by the inspectors.

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ATTACHMENT A

Documents Reviewed

General Office Review Boards (G0RBs) Responsibility, Authority, Organization

and Resources, Revision 2

GORBs Administrative Procedures, Revision 2

6310-ADM-1010.01, Independent Onsite Safety Review Group Procedure-TMI-1,

Revision 4

Resumes of GORB members

GPU Review and Approval Matrix

GPU Nuclear Corporate Policy and Procedures Manual, 1000-PLN-1291.01

GPU Nuclear and Radiation Safety Plan, Revision 0-00

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