ML20027E667

Amend 65 to License DPR-16,authorizing Changes to Administrative Organization by Retitling Position of Director Station Operations to Deputy Director Oyster Creek

ML20027E667
Person / Time
Site:	Oyster Creek
Issue date:	11/05/1982
From:	Crutchfield D Office of Nuclear Reactor Regulation
To:
Shared Package
ML20027E668	List: ML20027E667 ML20027E672 ML20027E676
References
NUDOCS 8211150591
Download: ML20027E667 (17)

Text

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/ cuc%jo UNITED STATES g

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g NUCLEAR REGULATORY COMMISSION g

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4 GPU NUCLEAR CORPORATION AND JERSEY CENTRAL POWER & LIGHT COMPANY DOCKET NO. 50-219 OYSTER CREEK NUCLEAR GENERATING STATION AMENDMENT TO THE AMENDED PROVISIONAL OPERATING LICENSE Amendment No. 65 License No. DPR-16 1.

The Nuclear Regulatory Commission (the Commission) has found tSat:

A.

The application for amendment by GPU Nuclear Corporation and Jersey Central Power and Light Company (the licensees) dated June 15, 1982, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations set forth in 10 CFR oc-Chapter I; B.

The facility will operate in conformity M th the application, the provisions of the Act, and the rules and regulations of the Commission; l

There is reasonable assurance (i) that the activities authorizeh C.

by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; D.

The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E.

The issuance of thi.s amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.

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Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment and Paragraph 2.C(2) of Provisional Operating License No. DPR-16 is hereby amended to read as follows:

(2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 65 are hereby incorporated in the license. GPU Nuclear Corporation shall operate the facility in accordance with the Technical Specifications.

3.

This license amendment is effective as of the date of its issuance.

FOR THE NUCLEAR REGULATORY COMMISSION sich Dennis M.

tch ie'd,

.ie Operating Reactors Br nch #5 Division of Licensing Ati$$hment:

Changes to the Technical Specification; Date of Issuance: November 5, 1982 O

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i ATTACHMENTTOLICENSEAMENDM'ENTN0.65

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s PROVISIONAL OPERATING LICENSE N0. DPR-16 s

DOCKET NO. 50-219 i

ReplacethefollowingpagesoftheTechnicalSpecificationswiththe'I enclosed pages.

The revised pages are identified by the captioned amendment number and contain vertical. lines indicating the area of change.

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(Appendix A) 6-1 6-4 6-5 N

6-7 through

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6-16 ec-(Appendix B) 5-3 s

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i Page 6-12 is merely included for pagination purposes.

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ADMINSTRATIVE CONTROLS 6.1 RESPONSIBILITY l

6.1.1 The Vice President & Director shall be responsible for ovarall facility operation. Those responsiblities delegated to the Vice President & Director as stated in the Oys ter Creek Technical

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Specifications may also be fulfilled by the Deputy Director. The Vice President & Director shall delegate in writing the succession to this responsibility during his and/or the Deputy Directors absence.

. 6.2 ORGANIZATION

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6.2.1 0FFSITE The organizaion for GPU Nuclear Corporation for management and technical support shall be functionally as shown on Figure 6.2.1.

6.2.2 FACILITY STAFF The facility organization shall be as shown on Figure 6.2.2 and:

a.

Each cu duty shif t shall include at least the shift staffing indicated on Figure 6.2.2.

b.

At least one licensed reactor operator shall be in the control room when fuel is in the reactor.

c.

Two licensed reactor operators shall be in the control room ~

during all reactor startups, shutdowns, and other periods involving

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planned control rod manipulations.

d.

ALL CORE ALTERATIONS shall be directly supervised by either a licensed Senior Reactor Operator or' Senior Reactor Operator Limited to Fuel Handlirg,who has no other concurrent responsibilities during this operation.

e.

An individual qualified in radiatio"n protection measures shall be on site when fuel is in the reactor.

f.

A Fire Brigade of at least 5 members shall be maintained onsite at all times. The Fire Brigade shall not include the minimum shif t crew necessary for.2afe shutdown of the unit or any personnel i

required for other essential functions during a fire emergency.

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Each on duty shift shall include a Shift Technical Advisor

,i except that the Shift Technical Advisors position need not be filled if the reactor is in the refuel or shutdown mode and the feactor is N

less than 212*F.

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6.3 FACILITY STAFF QUALIFICATIONS 6.3.1 The members of the facility staff shall meet or exceed the following qualifications:

Vice President & Director / Deputy Director Requirements: Ten years total power plant experience of which three years must be nuclear power plant experience.

A maximum of four years of academic training may fulfill four of the remaining seven years of required experience. Both must be capable of obtaining or l possess a Senior Reactor Operator's License.

Plant Operations Director Requirements:

Eight years total power plant experience of which three years must be nuclear power plant experience.

A maximum of two years of academic or related technical training may fulfill two years of the remaining five years of required experience. The Plant Operations Director must be capable of obtaining or possess a Senior Reactor Operator's License.

Plant Engineering Director Requirements:

Eight years of responsible positions related to power generation, of which three years shall be nuclear power plant experience.

A maximum of four of the remaining five years of experience may be fulfilled by satisfactory completion of academic or related technical training.

Manager Plant Administration Requirements:

Eight years total power plant experience of 'which four years must have been in nuclear power plant experience.

The Manager should possess a four year college degree or equivalent in Business Administration or an Engineering discipline.

Manager Plant Operations Requirements:

Eight years total power plant experience of which three years must be nuclear power plant" experience.

A maximum of two years of academic or related technical training may fulfill two of the remaining five years of required experience.

The Manager Plant Operations must possess a Senior Reactor Operator's License.

Safety Review Manager Requirements:

Eight years totsi power plant experience of which three years must be nuclear power plant experience.

A maximum of two years of academic or related technical training may fulfill two of the remaining five years of required experience.

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6-5 AmendmentNo.%)fI,f0',[.f[.66

plant. A maximum of four years of this five year experience may be fulfilled by related technical or academic training.

Shift Technical Advisor Requirements:

Bachelor's degree or equivalent in a scientific or engineering discipline with specific training in plant design, and response and analysis of the plant for transients and accidents.

6.3.2 Each member of the radiation protection organization for which there is a comparable position described in ANSI N18.1-1971 shalI meet or exceed the minimum qualifications specified therein, or in the case of radiation protectior, technicians, they shalI have at least one year's continuous experience in applied radiation protection work in a nucleaar facility dealing with radiological problems similar to those encountered in nuclear power stations, and shall have been certified by the Mgr/ Deputy Radiological Controls, as quallfled to perform assigned f unctions. This certification must be based on an PRC approved, documented program consisting of classroom training with appropriate examinations and documented positive findings by responsible supervision that the individual has demonstrated his ability to perform each specified procedure and assigned function with an understanding of its basis and purpose.

6.4 TRAINING 67.1 A retraining program for operators shall be maintained under the direction of the Manager Plant Training Oyster Creek and shall meet the requirements and recommendation of Appendix A of 10CFR Part 55.

Replacement training programs, the content of which shall meet the requirements of 10CFR Part 55, shall be conducted under the direction of the Manager Plant Training Oyster Creek for licensed operators and Senior Reactor Operators.

6.4.2 A training program for the Fire Brigade shalI be maintained under the direction of the Manager Plant Training Oyster Creek.

6.5 SAFETY REVIEW AND AUDIT The Vice President & Director and three organizational units, the l Plant Operations Review Committee (PORC), the Independent Safety Revlew Groups (lSRG) and the General Of fice Revlew Board (GORB) function to accomplish nuclear safety review and aucit of the Oyster I

Creek Station.

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Amendment No. [ [, M 65 i

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6.5.1 VICE PRES 10ENT & DIRECTOR l

6.5.1.1 FUNCTION The Vice President & Director shall ensure that:

l a.

All proposed changes to equipment or systems have been evaluated to determine if they constitute a change to the f acility or procedures as described in the Safety Analysis Report.

b.

All proposed changes to equipment or systems that constitute a change of the f acility or procedures as described in the Safety Analysis Report have been evaluated to determine whether they involve an unreviewed safety question as defined in paragraph 50.59, Part 50, Title 10, Code of Federal Regulations.

c.

All proposed tests and experiments have been eval uated to determine whether or not they involve unreviewed safety question's as defined in paragraph 50.59, Part 50, Title 10, Code of Federal Regulations.

6.5.1.2 AUTHORITY i

t The Vice President & Director has the authority to:

l a.

Make a determination as to whether proposed changes to equipment, or systems involve a change to the procedures or facility as described in the Safety Analysis Report.

b.

Make a determination as to whether or not proposed tests or experiments and changes to equipment or systems involve an unreviewed safety question.

c.

Direct the Plant Operations Review Committee to review saf ety-evalutions of proposed changes to equipment or systems and safety-evaluations of proposed tests and experiments to determine whether or not such changes, tests or experiments involve unreviewed safety questions.

NOTE:

Each determination that a proposed test, experiment, or change to a system or equipment that does not involve an unreviewed saf ety question shall be revicwed by the independent Safety Review Groups to verify that the determination" was correct.

This review shall be documented but is not a pre-requisite of the test, experiment, or change to a system or equipment.

6.5.1.3 RECORDS Any saf ety eval uations done in accordance with 6.5.1.1 (b) and (c) and any determinations made pursuant to 6.5.1.2(b) must be documented. Copies of these determinations shall be provided to the ISRG Coordinator and the Chairman of the General Office Review Board.

Records of all tests and experiments performed and all changes to equipment or systems made under the provisions of 10 CFR 6-8 Amendment No. M [ [

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Part 50.59 shall also be maintained at the station.

6.5.2 PLANT OPERATIONS REVIEW COMMITTEE (PORC) 6.5.2.1 FUNCTION The PORC shall function to advise the Vice President & Director.

6.5.2.2 COMPOSITION The PORC shall consist of the following plant personnel:

Safety Review Manager Plant Operations Director Plant Engineering Director Manager Plant Maintenance Mgr/ Deputy Radiological Controls The Vice President & Director shall desig'nate the Chairman and Vice-Chairman from among the PORC members.

6.5.2.3 ALTERNATES 7,,

Alternate members shall be appointed in writing by the PORC Chairman and will have the type of experience and training required of regular members.

However, they need not have the extensive longevity in the designated fields as long as in the opinion of the

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Chairman, their experience and judgement are adequate.

6.5.2.4 MEETING FREQUENCY The PORC shall meet at least once per calendar month and as' convened by the PORC Chairman or the Vice President & Director..

l 6.5.2.5 QUORUM A quorum of the PORC shall consist of the Chairman or Vice Chairman and three members / alternates. No more than two alterna.te members shall be counted in establishing a quorum.

6.5.2.6 RESPONSIBILITIES The responsibilities of the PORC are included in Table 6.5.1.

6.5.2.7 AUTHORITY a.

The PORC shall be advisory to the Vice President & Director.

Nothing herein shall relieve the Vice President & Director of his responsibility or authority for overall safety operations including taking irr.nediate emergency action. Determinations on items a and b of Table 6.5-1 shall be documented in writing.

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6.5.2.8 RECORDS The PORC shall mal'ntain written minutes of each meeting and copies

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of minutes and determinations shall be provided to the Vice' President & Director, ISRG Coordinator, and the Chairman of the GOR 8.

6.5.3 INDEPENDENT SAFETY REVIEW GROUPS (lSRG) 6.5.3.1 FUNCTION AND COMPOSITION The ISRG shall function under the direction of an ISRG Coordinator, i

who shall be appointed by the Vice President & Directgr to provide l safety reviews.

The ISRG Coordinator shall have available the competence to review problems in the following area:

a.

Nuclear Power Plant Operations b.

Nuclear Engineering c.

Chemistry and Radiochemistry d.

MetalIurgy e.

Instrumentation and Control f.

Radiological Safety g.

Mechanical and Electrical Engineering h.

Quality Assurance Practices The Coordinator shall establish, as needed, groups of two or more individuals with the expertise required for each topic to be reviewed.

so-6.5.3.2 CONSULTANTS Consultants shall be utilized as necessary to supplement the expertise available in the GPU Nuclear Corporation.

6. 5.'3. 3 RESPONSIBILITIES The speci fic responsibility to ensure accomplishment of the independentsafetyreviewofthe.VicePresident& Director.l determinations involving saf ety questions is assigned to the ISRG Coordinator and is accomplishd by utilizing, as necessary, the f ul l scope of expertise available, in the GPU Nuclear Corporation staff, consultants, contractors and vendors as appropriate.

Table 6.5-1 defines the specific Independent safety" review responsibilities.

6.5.3.4 AUTHORITY The ISRG advises the Vice President & Director, it has the authority to conduct reviews and investigations, which will be documented.

6.5.3.5 AUDITS Audits of facility activities shall be performed under the cognizance of the Vice President Nuclear Assurance.

Ttrese audits shall encompass:

6-10 Amendment No. )0$ )

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9 a.

The conformance of facility operation to all provisions contained within the Technical Specifications and applicable license conditions at least once per year.

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b.

The performance training and qualifications of the entire facility staf f at least once per year.

c.

The results of all actions taken to correct deficiences occurring in f acilly equipment, structures, systems or method of operation that af feet nuclear safety at least once per six months, d.

The Facility Emergency Plan and implementing procedures at least once per two years.

e.

The Facility Security Plan and implementing procedures at least once per two years.

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f.

Any other area of facility operation considered appropriate by l the GORB or the Vice President & Director.

6.5.3.6 RECORDS Written documentation of all Independent safety reviews and investigations will be forwarded to the Vice President & Director l and the Chairman of the General Office Review Board. In addition, any reportable occurrence or item involving an unreviewed saf ety question which is Identifled by the iSRG wIII be documented and reported imediately to the above mentioned persons.

The audit f'Indings which result from all audits conducted in acccedance with Section 6.5.3.5 shalI be documented and reported to the above mentioned persons within 30 days af ter completing the audit. Reports documenting corrective action will receive the same distribution and they will also be forwarded to the ISRG Coordinator.

6.5.4 GENERAL OFFICE REVIEW BOARD (GORB) 6.5.4.1 FUNCTION The technical and administrative function of the GORB is to provide independent review of major safety issues, to foresee potentially significant nuclear and radiation safety problems, and to advise the Office of the President on these matters.

6.5.4.2 COMPOSITION Members of the General Office Review Board shall possess extensive experience in their individual specialities and collectively have the competence in the foilowing areas:

a.

Nuclear Power Plant Operations b.

Nuclear Engineering

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Chemistry and Radiochemistry l

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d.

Metallurgy e.

Instrumentation and Control f.

Radiological Safety g.

Mechanical and Electrical Engineering The Chairman and Vice Chairman shall be appointed by the Of fice of the President. (Neither shall be an Individual with line responsibility for operation of the plant).

The Chairman shall designate a minimum of six additional members.

No more than a minority of the Board shalI have iIne responsIbIIIty for operation of Oyster Creek Nuclear Generating Station.

6.5.4.3 ALTERNATES Alternate members shall be appointed in writing by the GORB Chairman and will have the type of experience and training required of regular members, however, they need not have the extensive longevity

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In the designated fields as long as, in the opinion of the Chairman, their experience and judgement are adequate.

6.5.4.4 EETING FREQUENCY The GORB shall meet at least semi-anually and any time at the request of the Chairman or the Office of the President.

6.5.4.5 QUORUM

• C" A quorum shall consist of the Chairman or Vice Chairman and three members /al ternates.

No more than one alternate member shall be counted when establishing a quorum and no more than a minority of the quorum shal l hold line responsibility for operations of the Oyster Creek Station.

6.5.'.6 RESPONSIBILITIES 4

a.

The primary responsibility of the GORB is to foresee potentially significant nuclear and radiation safety problems and to recommend to the Of fice of the President how they may be avoided or mitigated.

b.

Carry out the specific Independent safety revlew responsibilities listed in Table 6.5-1.

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6.5.4.7 AljTHORITY The GORB shall be advisory to the Of fice of the President and shall have the authority to conduct reviews, audits, and investigations requested by the Of fice of the President or as deemed necessary by the GOR 8 in the fulfillment of its responsibilities.

6.5.4.8 g lTS The report of the management review of the QA Plan, initiated by the VicePresident&DirectorinaccordancewiththeOperationalQualItyl Assurance Plan, shall be reviewed by the GORB with respect to safety and administrative safety issues.

6.5.4.9 RECORDS Minutes of each GORB meeting shall be recorded and approved by the

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GORB Chairman. Copies of approved minutes will be forwarded to the Of fice of the President, Vice President & Director, PORC Chairman, and others designated by the GORB Chairman. GOR 8 recommendations to the Of fIce of the President will be documented in a letter from the GORB Chairman to the Office of the President.

Included with each letter will be any dissenting opinions of members of the Board.

6.6 REPORTABLE OCCURRENCE ACTION 6.6.1 The following actions shall be taken in the event of a: Reportable Occurrence:

a.

The Commission shall be notified and/or a report submitted pursuant to the requirements of Specification 6.9.

b.

Each Reportable Occurrence Report submitted to the Commission shall be reviewed by the Plant Operations Review Committee and submitted to the ISRG Coordinator and the Vice President & Director. l 6.7 SAFETY LIMIT VIOLATION 6.7.1 The following actions shall be taken in the event a Safety Limit is violated:

a.

If any Safety Limit is exceeded, the reactor shalI be shut down immediately untti the Commission authorizes the resumption of operation.

b.

The Safety Limit violation shall be reported to the Commission and the Vice President & Olrector.

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TABLE 6.5-1 SAFETY REVIEW RESPONSIBILITIES

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INDEPENDENT RrvirW ITLM INiilAL Affl0N PORC ISRG CORR a) ProposcJ change to espsipment, Initiator: Must prepare a complcte Hast review items to Hust re' view all deter-May review any deter-or systems subject to the description of the proposed changes determine whether or not alnations by the mination, but must Psovisions of Section 50.59, and ensure a safety evaluation of an unreviewed safety Vice President 4 review those fer which Part 50, Title 10 Code of the change is included.

question is involved. If Director.

the*Vice President &

FeJeral Regulations.

Vice President & Director (1) requested by the Vice Director has re-Must determine if the item is an President & Director, quested 00R8 review.

actual change to equipment or systems as described in the FSAR.

I (2) Must determine if the item involves an unreviewed safety question. (3) May request the PORC to assist in the above determina-t ion s.

b) Proposed tests and esperiments.

Initiatort Must prepare a complete Must review item ta As above.

As above.

(subject to provisions of)

Jescription of the proposed test determine whether or not 50.59. Part 50, Tittu 10. Code or esperiment and ensure a safety an unreviewwJ safety of Federal Regulations, evaluation of the test or experi-question is involved. If ment is included.

requested by the Vice Vice President & Director (I)

President 4 Director.

a Must Jotermine if the item involves an unroviewed safety question.

(2) May request the PORC to assist in the above determinations.

c) ProposcJ changes in Technical Initiator: Hust prepare a com-(1) Must review the iten kust review change and May review any iten Specifications or in the NRC plate description of the proposed for nuclear and radiolo-PORC recommendation but must review those Operating License.

change and ensure a safety evalu-gical safety. (2) Must prior to submittal to for which the Vice i

ation of the change is included.

make recommendations to the NRC.

President & Director or j

the Vice President 4 his supervisor have Director as to whether requested CORS review, or not the change is safe.

d) Reportable occurrences Vice PresidcLt & Director:

Hust lust review Reportable 7bsst review Reportable As above.

have investigations perforacJ for lecurrences Report for Occurrence Report s for all Reportable Occurrences and a

.afety significance and safety significance and 1

report pscpared including the eaLe recommendations to review PORC recommenda.

safety significance of the inclJent. the Vice PiestJent 4 tions.

Director ' on how to avoid Y

recurrence?

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Page 2 of 2 TABLE 6.S-3 (Ghi'T) i,

.t SAFETY SEVIEk RESPONSIBILITIES e

,e INtWPI.NDENT REVII'W ITEM INITIAL. ACTI(W Pnpf" ISRG (MR8

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j e) Facility operations including Continuing responsibility See Ites ! below As above Security Plan. Emergency Plan and Implementing procedures; review is to detect potential safety hatards.

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() Significance operation Vice President F. Director Report Revlev natter and report Perform indepenJent As above l

.g atinormalities or deviations free such matters to the PORC ISRG tvatustion of safety review of IURC 8

normal anJ espected performance.

Coordinator and the Chairman Ques.

significance to the ISaC evaluation.

and COR$.

g) Any inJication of an sanan-As above As above As above As above ticipatcJ deficiency in some aspect of design or operation of safety related stria:tures, systems or components.

h) IVAC minutes and reports.

Review to determine if As above any matters Jiscussed involve unrelated 9

safety questions.

l) Audit Reports and NBC Review to Jetermine if The report of the Inspection Seports.

any matters reported management revleu of involve Violations of

• the QA Plan, latti-rechalcal Specification, ated by the Vice

,f License requirements or PreslJent. and Director regulations or have any Oyster Creek in accor-inuclear or radiation dance with the Opera-safety implications.

tional Qiality As-g surance Plan. shall be reviewed by the GHis with respect to teshnical and aJaint.

strative safety tunes.

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. l 6-n Amendment No.

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c.

A Safety Limit Violation Report shall be prepared.

The report shall be reviewed by. the Plant Operations Review Committee and submitted to the Vi'ce President & Director. This report shall l

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describe (1) applicable circumstances preceding the violation, (2) effects of the violation upon facility components systems or structures, and (3) corrective action taken to prevent recurrence.

d.

The Safety Limit Violation Report shall be submitted to the Commis sion within 10 days of the violation.

It shall also be submitted to the ISRG Coordinator.

6.8 PROCEDURES 6.8.1 Written procedures shall be established, implemented, and maintained that meet or exceed the requirements of Section 5.1 and 5.3 of Americsn National Standard N18.7-1972 and Appendix "A"

of the Nuclear Regulatory Connaission's Regulatory Guide 1.33-1972 except as provided in 6.8.2 and 6.8.3 below.

6.8.2 Each procedure and administrative policy of 6.8.1 above, and changes thereto, shall be reviewed by the Plant Operations Revie.w Conunittee and approved by the Vice President & Director prior to l implementation and periodically as specified in the Administrative Procedures.

so-6.8.3 Temporary changes to procedures 6.8.1 above may be made provided:

a.

The intent of the original procedure is not altered.

b.

The change is approved by two members of the supervisory staf f, at least one of whom possesses a Senior Reactor Operator's License.

I c.

The change is documented, subsequently reviewed by the Plant Operations Review Committee and approved by the Vice President &

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Director as specified in the Administrative Procedures.

6.9 REPORTING REQUIREMENTS In addition to the applicable reporting requirements of 10 CFR, the following identified reports shall be submitted to the Director of the appropriate Regional Office of Inspection and Inforcement unless otherwise noted.

6.9.1 ROUTINE REPORTS a.

Startup Report. A summary report of plant startup and power escalacion testing shall be submitted following (1) receipt of an 6-16 Amendment No. %)5',40$ %

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Office of The President General Office Vice President Vice President 4 4 Director Oyster Director Radiological Creek Controls Deputy Director Oyster Creek i

i ISRG Mgr Environmental f~~~~~~~~ Coordinator Controls I'

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Legend:

Direct Responsibility Advisory Capacity FIGURE 5-1 ORGANIZATION F3R THE IMPLEMENTATION OF THE ENVIRONMENTAL TECHNICAL SPECIFICATIONS 5-3 Amendment No. )RI.J'f, 65, i

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