ML20054J924

Proposed Changes to Tech Specs Revising App A,Section 6 & App B,Figure 5-1 Re Administrative Organization

ML20054J924
Person / Time
Site:	Oyster Creek
Issue date:	06/15/1982
From:	GENERAL PUBLIC UTILITIES CORP.
To:
Shared Package
ML20054J918	List: ML20054J917 ML20054J923 ML20054J924
References
NUDOCS 8206300208
Download: ML20054J924 (14)

Text

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ADMINSTRATIVE CONTROLS 6.1 RESPONSIBILITY 6.1.1 The Vice President & Director shall be responsible for ove rall facility operation. Those responsiblities delegated to tne Vice President & Director as stated in the Oys ter Creek Technical 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 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 on duty shift 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.

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c. Two licensed reactor operators shall be in the control room during all reactor startups, shutdowns, and other periods involving 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 Handling who has no other concurrent responsibilities during this operation.

e. An individual qualified in radiation 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 safe shutdown of the unit or any personnel required for other essential functions during a fire emergency.

t g. Each on duty shift shrli include a Shift Technical Advisor I

except that the Shif t Technf.i:a1 Advisors position need not be filled if the reactor is in the re. fuel or shutdown mode and the reactor is less than 212*F.

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VICE PRESIDENT a omECTOR OTs TE R CREEK FIGURE 6.2.2 - - - - - - - - - - - - - - - -

DEPUTV OIRECTOR ONSITE ORGANIZATION OTSTER CREEu iSRG .

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COORDINATOR 5

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SAiETY REVIEW MANAGE R l l I I ________ _ _ __ __ _ _ _ l PL ANT E NGINEERING , _ MANAGER PLANT _

PLANT OPERATIONS MANAGER PLANT MGR /0EPUTT DIRE C TOR MAINTENANCE DIRECTOR ADtRNISTRATION ~

RADIOLOGICAL I

CONT ROLS. O C.

FsRE PRO TECTION _ _

CORRE CTIVE M41NTENANCE _ MANAGER RADeASTE SUPERVISOg MANAGER OPERATIONS

• RADIOLOGICAL FiELO OPERATIONS MANAGER.

OC MANAGER PLANT PREVENTIVE MAINTE NANCE I

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MANAGER PLANT E NGINE E RING MANAGER OPER ATIONS , RADIOLOGICAL CONTROLS GROUP SUPE R VISOR MANAGER COME MT

_ GROUP SHIFT , . . . . ygegnicat ENGINE ER9tG gypggyg$gg ADOL.O EAL CONTROLS t ADVISORS TECHNICIANS I

CHEMISTRV _ CONTROL ROOM ,,

M ANAGE R OPE R ATORS RADIOLOGICAL E NGINE E plNG SHIFT STAFFING M ANAGER. 0.C.

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• I / SHIF T l GROUP SHIF T SUPE RVISOR REQUIRE SENIOR R8e e*2/SHH OPERATORS TECHNICAL REACTOR OPE RA TORS LICENSES. THE CONTROL *eeS/ SHIFT (1 MAT BE A RADWASTE OPERATOR) gyayr ROOM OPERATORS REQumE A REACTOR OPE R ATING L IC E NSE.

2-THE SUPERVISOR S T ATION INSTRUMENT 8 RADIOLOGICAL SUPPOR T E L E C TRIC AL MAINTENANCE REPORTS WITHIN MAN AGE R. 0 C.

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6.3 FACILITY STAFF QUAllFICATIONS 6.3.1 The members of the facility staf f shaii meet or exceed the -foilowing 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 ful filled by satisf actory 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 discipiine.

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 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.

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plant. A maximum of four years of this five year experience may be ful filled by related technical or academic trainlag.

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 shall meet or exceed the minimum qualifications specifled therein, or in the case of radiation protection 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 Control s, as quali f ied to perform assigned f unctions. This certification must be based on an MRC 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 6.4.1 A retraining program for operators shalI 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 r operators and Senior Reactor Operators.

l 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 f ice Revlew Board (GORB) function to accomplish nuclear safety review and audit of the Oyster l Creek Station.

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6.5.1 VICE PRESIDENT & DIRECTOR l i

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 proce:dures as described in the Safety Analysis Report.

b. All proposed changes to equipment or systems that constitute a change of the facility 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 evaluated to determine whether or not they involve unreviewed safety questions as defined in paragraph 50.59, Part 50, Title 10, Code of Federal Regulations.

6.5.1.2 AUTHORITY 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 f acility as described in the Safety Analysis Report,

b. Make a determination as to whether or not proposed tests or experiments and changes to equ ipment 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 ir.volve an unreviewed saf ety question shall be reviewed by the independent Safety Review Groups to verify that the determination was correct. This review l shall be documented but is not a pre-requisite of the test, l

experiment, or change to a system or equipment.

6.5.1.3 RECORDS l

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

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4 Part 50.59 shall al so 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 designate the Chairman and Vice-Chairman from among the PORC members.

6.5.2.3 ALTERNATES 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 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 alternate members shall be counted in establishing a quorum.

6.5.2.6 RESPONSIBILITIES The responsibilities of the PORC are incluced 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 immediate 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 maintain written minutes of each meeting and copies of minutes and determinations shall be provided to the Vice President & Director, ISRG Coordinator, and the Chairman of the GORB.

6.5.3 INDEPENDENT SAFETY REVIEW GROUPS (ISRG) 6.5.3.1 FUNCTION AND COMPOSITION The I SRG shall function under the direction of an ISRG Coordinator, who shall be appointed by the Vice President & Director 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. Metallurgy

e. Instrumentation and Control

f. Radiological Safety

g. Mechanical and Electrical Engineering

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

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 f ic respons i bi l ity to ensure accompl ishment of the independent safety review of the Vice President & Director l determinations involving saf ety questions is assigned to the ISRG Coordinator and is accomplishd by utilizing, as necessary, the f u l l scope of expertise available in the GPU Nuclear Corporation staf f, consultants, contractors and vendors as appropriate. Tab l e 6. 5-1 defines the specific independent safety review responsibilities.

6.5.3.4 AUTHORITY i

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. These audits shall encompass:

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

b. The performance training and qualifications of the entire facility staff at least once per year.

c. The results of all actions taken to correct deficiences occurring in facilly equipment, structures, systems or method of operation that af fect 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.

f. Any other area of facility operation considered appropriate by the GORB or the Vice President & Director, j 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 Of fice Review Board. In addition, any reportable occurrence or item involving an unreviewed safety question which is identified by the ISRG will be documented and reported imediately to the above mentioned persons.

The audit findings which result from all audits conducted in accordance with Section 6.5.3.5 shall 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 CFFICE 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 Of fice Review Board shall possess extensive experience in their Individual special ities and col lectivel y have the competence in the foilowing areas:

a. Nuclear Power Plant Operations

b. Nuclear Engineering

, c. 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 line 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 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 A quorum shall consist of the Chairman or Vice Chairman and three members /al ternates . No more than one atternate member shali 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.

6.5.4.6 RESPONSIBILITIES

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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 AUTHORITY The GORB shall be advisory to the Of fice of the President and shall I

have the authority to conduct reviews, audits, and investigations requested by the Of fice of the President or as deemed necessary by the GORB in the fulfillment of its responsibilities.

6.5.4.8 AUDITS The report of the management review of the QA Plan, initiated by the Vice President & Director in accordance with the Operational Quality l 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 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. GORB recommendations to the Of f ice of the President will be documented in a letter from the GORB Chairman to the Of fice 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 noti f ied 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 Coordinatcr 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 shall be shut down immediately until the Commission authorizes the resumption of operation.

b. The Saf ety Limit violation shall be reported to the Comission j and the Vice President & Director. l l

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• Page 1 of 2 TABLE 6.5-1 SAFETY REVILW RESPONSIBILITIES INDEPLNDENT R0 VIEW ITI'M INii!AL ACTION PORC ISRG Copp a) Proposed change to equipment, Initiator: Must prepare a complete >b s t review items to Must review all deter- DLly review any deter-or systems subject to the description of the proposed changes determine whether or not minations by the mination, but must Provisions of Section 50.59, and ensure a safety evaluation of an unreviewed safety Vice President 6 review those for which Part 50. Titic 10 code of the change is includcJ. question is involved, if Director. the* Vice President 4 Federal Regulations. Vice President G Director (!) requested by the Vice Director has re-Must determine if the item is an President G Director, quested GORB review, actual change to equipment or systems as described in the FSAR.

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

b) Proposed tests and experiments, Initiator: Must prepare a complete Must review item to %s above. As above.

(subject to provisions of) description of the proposed test determine whether or not 50.59. Part 50 Title 10, Code or experiment and ensure a safety an unreviewed safety of Federal Regulations. evaluation of the test or experi- question is involved, if ment is included. requested by the Vice Vice President 6 Director (1) President 4 Director.

Must determine if the item involves an unreviewed safety question.

(2) May request the PORC to assist in the above determinations, c) Proposed changes in Technical Initiator: Must prepare a com- (1) Must review the item >bst review change and Specifications or in the NRC bby review any item plete descr2ption 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 ation of the change is included.

prior to submittal to for which the Vice make recommendations to the NRC. President 4 Director or the Vice President G his supervisor have Director as to whether requested CORB review.

Or not the change is safe, d) Reportable occurrences Vice President G Director: Hust 'tust review Reportable Hust review Reportable As above.

have investigations performed for lecurrences Report for Occurrence Reports for all Reportable Occurrences and a safety significance and safety significance and report prepared including the aake recommendations to review PORC recommenda-safety significance of the incluent. the Vice President 6 tions.

Director on how to avoid ,

recurrence.

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TABLE 6.5 1 (O W T)

I sAftTV REvitw atSimsisILITIES t

INDfPl.NDENT RiivIIW ITI M INITIAL ACT!(N PORC ISPC 'MPR el l'acility operations including (untinuing responsibilit) See Item i below As above Security I'lan, fuergency Plan and laptementing procedures; review is to detect potential safet y ha:ards.

I fl Significance operation Vice PrestJent r. Director Repo rt Review matter and report Perform independent As above abnormalities or deviations from such matters to the l' ORC ISRC evaluation of safety review of IURC normal and expected gierformance. Coordinator and the Chairman Giku. significance to the ISRG e valua t hn, and CDRN.

g) Any indication of an unan- As atete As above 4s above As above t icip.eted Jeficiency in some aspect of design or operation of safety relatcJ st risetures, systems or component s.

h) IURC minuten and report s. Review to determine if As above any matters discussed involve unrelated safety questions.

1) Audit Reports anc RC briew to determine if The report of the Inspection Reports 2ny matters reported management review of involve Violations of the QA Plan, initi-Technical Specification ~ ated by the Vice license requirements or President, and Director f regulations or have any Oyster Creek in accor-maclear or radiation dance with the Opera-safety implicat ions, tional Quality As-surance Plan, shall tc reviewed by the G)RB with respect to l technical and admini-strative safety issues.

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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 Vice President & Director. This report shalll 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 precedures shall be established, implemented , and maintained that meet or exceed the requirements of Section 5.1 and 5.3 of American National Standard N18.7-1972 and Appendix "A" of the Nuclear Regulatory Conmission'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 Review Connittee and approved by the Vice President & Director prior to l implementation and periodically as specified in the Administrative Proced ure s .

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

a. The intent of the original procedure is not al te red .

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.

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

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 escalation testing shall be submitted following (1) receipt of an 6-16

e Office of The President General Office ,-(

Vice President Vice President 6 6 Director Oyster Director Radiological Creek Controls Deputy Director Oyster Creek i

i ISRG Mgr Environmental f~~~~~~~~ Coordinator Controls t

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' Safety Review g_______..

Manager Legend: Direct Responsibility Advisory Capacity i

l FIGURE 5-1 ORGANIZATION FOR THE UfPLEMENTATION OF THE ENVIRONMENTAL TECHNICAL SPECIFICATIONS 5-3