ML20070S097

Amend 75 to License DPR-20,changing Tech Specs App a, Section 6,Admininstrative Controls,To Reflect Addition of Nuclear Activities Plant Organization & Organizational Title Changes

ML20070S097
Person / Time
Site:	Palisades
Issue date:	01/28/1983
From:	Crutchfield D Office of Nuclear Reactor Regulation
To:
Shared Package
ML20070S098	List: ML20070S097 ML20070S102 ML20070S104
References
NUDOCS 8302040251
Download: ML20070S097 (14)

Text

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[(f3 fo UNITED STATES ~

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NUCLEAR REGULATORY COMMISSION r,,.

,4j WASHINGTON, D. C. 20555 go/

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-a CONSUMERS POWER COMPANY DOCKET NO. 50-255 PALISADES PLANT AMENDMENT TO PROVISIONAL OPERATING LICENSE Amendment No. 75 License flo. CPR-20 1.

The Nuclear Regulatory Comaission (the Commission) has found that: '

A.

The application 'for amendment by Consumers Power Company (the licensee) dated November 12, 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 Chapter I; B.

The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission:

C.

There is reasonable assurance (i) that the activities authorized 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 this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.

8302040251 830128 DRADOCK05000g

2.

Accordingly, the licdnse is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment and paragraph 3.B of Provisional Operating License No. DPR-20 is_hereby amended to read as follows:

B.

Technical Specifications The Technical Specifications contained in Appendices A and B (Envi.ronmental Protection Plan) as revised through Amendment No. 75, a~re-hereby incorporated in the license.

The. licensee shall operate the facility in accordance with the Technical Specifications.

3.

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

i FOR THE NUCLEAR REGULATORY COMMISSION

' $Y/

Dennis M. Crutchfiel /, Ch'ef Operating Reactors B'anch #5 Division of Licensing c

Attachment:

Changes to the Technical Specifications Date of Issuance: January 28, 1983 l

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ATTACHl1ENT TO LICENSE AMENDMENT.NO..75 PROVISIONAL OPERATING LICENSE NO. DPR-20 b3CKET50-f$5

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i Remove Pages Insert Pages 6-1 6-1*

6-la 6-la*

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6-lb 6-2 6-2 6-5 through 6-10 6-5 through 6-10 6-10a

• The provisions contained on these pages have not been changed; e

they are included for pagination purposes only.

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e 6

6.0 ADMINISTRATIVE CONTROLS.

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6.1 RESPONSIBILITY 6.1.1 The Plant General Sanager shall.b'e responsible for overall plant I

operation and shall delegate in w'riting the succession for'this responsibility during his absence.

6.2 ORGANIZATION 6.2.1 0FFSITE The offsite_ organization fcr plant management and technical support.

shall be as'shown on Figure 6.2-1.

6.2.2 PLANT STAFF

'The plant organization shall be as shown on Figure 6.2-2 and:

a.

Each on-duty shift shall be composed of at least the minimum shift crew composition shown in Table 6.2-1.

b.

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

c.

At least two licenced Operators shall be present in the contro's i

room during reactor start-up (through 15% power), cheduled 9

reactor shutdown and during recovery from reactor trips.

d.

An individual qualified in radiation protection procedures shall be on site when fuel is in the reactor.

All core alterations after the initial fuel loading sha'l either e.

l be performed by a licensed Reactor Operator. under the general supervision of a Senior Reactor Operator or directly supervised i

by a licensed Senior Reactor Operator (or Senior Operator limited to Fuel Handling) who has no other concurrent responsibilities during this operation.

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f.

A fire brigade of at least 5 members shall be maintained on site at all times.* This excludes 3 members of the minimum shift crew necessary for safe shutdown or any personnel required for other essential functions during a fire emergency.

• Fire brigade composition may be less than the minimum requirements for a period of time not to exceed 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> to accommodate unexpected absence of fire brigade members provided immediate action is taken to restore the i

fire brigade to the minimum requirements.

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i 6-1 Amendment No. 32,37, #, 75

l ADMINISTRATIVE CONTROLS 6.2.3 NUCLEAR ACTIVITIES PLANT ORGANIZATION (NAPO)

6. 2. 3.1 The NAP 0 shall functi[on tg.ex$mine plant operating characteristics, NRC issuances, industry advisories, Licensse Event Reports and other sources which may indicate areas for improving plant safety. The organization shall report to the Executive Engineer NAPO. With the concurrence of the Executive ~

Engineer, NAPU may function as staff to the onsite and offsite review organi-zations and provide technical support for problem resolution and General Office interface.

COMPOSITION 6.2.3.2 Th~e NAPO shall be composed of members located at other Consumers Power Company ~ Nuclear Power facilities, and at the General Office, and onsite members at the Palisades diant.

The NAPO on site shall consist of a minimum of five (5) technical personnel.l QUALIFICATIONS 6.2.3.3 At least three of the full-time members at the Palisades Plant shall have a bachelor's degree in engineering or a related science.

At least one of the three shall have a minimum of five years' professional experience.

which includes a minin:um of two years' experience in nuclear power plant operation and/or design. Those individuals comprising the minimum complement of five and not having bachelor's degrees in engineering or a related science shall have at least two years experience in the field for which they will provide expertise to NAPO.

Any NAP 0 member may be drawn upon to perform NAPO duties on a temporary basis at any nuclear plant location.

REPORTS 6.2.3.4 ' Reports of NAP 0 activities shall be submitted regularly to the NSB with copies to PRC.

r l The requir,ement f:r a minimum of five (5) technical personnel shall be effective on 1/1/83.

6-la Amendment No. 75 O

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6.3 PLANT. STAFF QUALIFICATIONS 6.3.1 Each member of the plant staff shall meet or exceed the minimum qualifications of ANSI N18.1-1971 for comparable positions. -

6.3.2 The Health Physicist shall. meet br ex~e(d the qualifications of Regulatory Guide 1.8, September 1975.ll.i 6.3.3 The Shift Technical Advisor (STA) shall have a bachelor's degree or equivalent in a scientific or engineering discipline with specific

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training in plant design, and response and analysis of the plant for transients and accidents.

6.4 TRAINING 6.4.1 A retrainind dnd replacement ' training program _for the plant staff.

shall be maintained under the direction of the Nuclear Training Administrator and shall meet or exceed the requirements and recom-

.mendations of Section 5.5 of ANSI N18.1-1971 and Appendix "A" of 10 CFR, Part 55.

6.4.2 A tr6ining program for the fire brigade shall be maintained under the direction of the Plant Training Coordinator and shall, as practical, meet or exceed the requirements of Section 27 of the NFPA Code.

,a (I)For the purpose of this section " Equivalent," as utilized in Regulatory Guide 1.8 for the bachelor's degree requirement, may be met w*th four years of any one or combination of the following; (a) Formal schooling in science or engineering, or (b) operational or technical experience /

training in nuclear power.

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'A end ent No.32,37,67,f(,75 6-lb m

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4 CONStt1ER'; IMER COMPANY 01.FS11F. ORCART7AIIC.N PRESIDENT i

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EXECITTIVh EXECitTIVE VICE PRESIDEttr VTCE PRESIDENT n

VICr PRFSli>ENT VICE PRESIDENT NtfCI. EAR SAFETY CF.ffER4f. SERVICES NUCTEAR OPERATIONS IOARii

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i DIRECTOR OF g

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Pit 0PFRTY l'knTECTION***

Pl.AriT.

OTilER EXECITTIVE DIRECTOR OF CENERAI. MCR CENERAL MCR e

m SERVICES DIRECTOR

• Q' FAT. TTY Mini.AND PAI.TSADES StJPERitri.YNDENT 8

N11 CLEAR ASstiRANCE Ric ROCK POlttr N

AcrTVITIES g*

I EXECirflVE ENGINEER **

NUC1. EAR ACTIVITIES PLANT ORGANIZATION k

• fM8L Chairman Q

• • NSB Vice Chairfran ant! Secretary ca.

• • • Responsthic for Overall Fire Protection Prostram b:s" Figurc 6.2-1 2

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6.5 REVIEW AND AUDIT 6.5.1 PLANT REVIEW COMMITTEE (PRC)

FUNCTION J-

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6.5.1.1 The Plant Review Comittee (PRC)'shall function to advise the Plant General Manager on all matters reTated to nuclear safety.

COMPOSITION 6.5.1.2 The PRC shall be composed of:

Chairman:

Plant General Manager or Designated Alternate Member:

Technical Superintendent Member:

Maintenance Superintendent Member:

Cperations Superintendent Member:

Instrument and Control Engineer Member:

Reactor Engineer Member:

Health Physicist Meniber:

Shift Supervisor Member:

Chemical Engineer Member:

Technical Engineer or Supervisory Engineer Member:

Shift, Senior or General Engineer ALTERNATES 6.5.1.3 Alternate members of the PRC shall be appointed'in. writing by the PRC Chairman to serve on a temporary basis.

However, no more tha, two alternates shall participate as voting members at any one time in PRC activities.

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6.5.1.4 MEETING FREQUENCY The PRC shall meet at least once per calendar month with special meetings as required.

6.5.1.5 QUORUM A quorum of the PRC_ shall consist of the Chairman and four members (including alternates).

6.5.1.6 RESPONSIBILITIES The PRC shall be responsible for:

a.

Review of:

(1) all procedures req 0 ired by Specification 6.8 and changes thereto and (2) any other proposed procedures or changes thereto as determined by the Plant Manager to affect l

nuclear safety.

b.

Review of all proposed tests and experiments that affect l

nuclear safety.

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6-5 Amendment No. 16,46,75

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c.

Review of all proposed changes to A*' Technical Specifications.

d.

Review of all proposed changes or modifications to. plant systems

-or equipment that affect' nuclear safety.

e.

Investigation of all violations of the Technical Specifications.

(A report shall be prepared covering evaluation and recommen-dations to.prhvent'recuPrence~and forwarded to the Vice President-

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Nuclearpperationsandto'theExecutiveEngineer-NAPO.)

f.

Review of plant operations to detect potential nuclear safety hazards.

g.

Performance of special reviews and investigations'and reports thereof as requested by the Plant General Manager or Chairman of NSB.

h.

Review of the Site Emergency Plan and implementing procedures.

1.' Review of events requiring 24-hour written notification to the Commission.

6.5.1.7 AUTHORITY The PRC shall:

a, Recontaend in writing to the Plant General Manager approval or disapproval of items considered under Specifications 6.5.1.6.a.

through d. above.

b.

Render deteEninations in writing with regard to whether or not each item considered under Specifications 6.5.1.6.a. through e.

above constitutes an unreviewed safety question.

e c.

Provide written notification within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> to the Vice President-Nuclear Operations and to the Vice Chairman of NSB of any disagreement between the PRC and the Plant General Manager; however, the Plant' General Manager shall have responsi-bility for the resolution of such disagreements pursuant to Specification 6.1.1 above.

RECORDS 6.5.1.8 The PRC shall maintain written minutes of each PRC meeting and shall provide copies to the NSB.

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6.5.2 NUCLEAR SAFETY BOARD (NSB)

RESPONSIBILITIES 6.5.2.1 The Nuclear Safety Board (NSB) is responsible for maintaining a continuing examination of nuclear safety-related Corporate and plant activities and defining opportunities for policy changes related to improved nuclear safety performance. The NSB shall operate in accordance with a written charter, approved by the Vice President-Nuclear Operations, which designates the member-ship, authority, and rules for conducting the meetings.

FUNCTION 6.5.2.2 The NSB shall function to provide review of designated activities in the areas specified in Specification 6.5.2.3.

6-6 Amendment No. N, 75

ADMINISTRATIVE CONTROLS N~hw 6.5.2.3 The NSB shall consist o

_ appointed by the Vice President -

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Nuclear Operations.

NSB shall:be chaired by tie'ExectitiveJirector of N jclea~r Activities, the Vice Chairman or a duly appointed alternate.

The Executive Engineer - NAP 0, shall be the Vice Chairman and Secretary.

Collectively, personnel appointed for NSB shall be competent to conduct reviews in the following areas:

a.

Nuclear Power Plant Operations b,' Nuclear Engineering c.

Chemistry and Radiochemistry d.

Metallurgy e.

Instrumentation and Control f.

Radiological Safety

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g.

Mechanical and Electrical Engineering h.

Quality Assurance Practices An individual appointed to NSB may possess expertise in more than one of the above specialties.

These individuals should, in general, have had professional experience in their specialty at or above the Senior Engineer. level.

ALTERNATE MEMBERS 6.5.2.4 Alternate members may be appointed in writing by the Vice President-Nuclear Operations to act in place of members during any legitimate and unavoid-able absences. The qualifications of alternate members shall be.similar to those of members.

CONSULTANTS 6.5.2.5 Consultants shall be utilized as determined by the NSB Chairman or Vice Chairman to provide expert advice to the NSB. NSB members are not

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restricted as to sources of technical input and may call for separate investi-gation from any competent source.

MEETING FREQUENCY 6.5.2.6 NSB shall meet at least once per calendar quarter during the initial year of facility operation following fuel loading and at least once every six-months thereafter.

6-7 Amendment No. 26, 75

1 ADMINISTRATIVE CONTROLS QUORUM 6.5.2.7 A quorum of NSB shall consis.t of the Chairman and four (4) members.

(The Vice Chairman may be-a voting;pember when not acting in the capacity of Chairman.) No more'than a minority of-the' quorum shall have line responsibility for operation of the facility.

It is the responsibility of the Chairman to ensure that the quorum convened f6r a meeting contains appropriately qualified

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members or has at its disposal consultants sufficient to carry out the review functions required by the meeting agenda.

6.5.2.8 RESPONSIBILITIES REVIEW 6.5.2.8.1 NSB shall be responsible for the review of:

a.

Significant operating abnormalities or deviations from normal and expected performance of plant equipment that affect nuclear safety.

b.

All events which are required by regulations or Technical -

Specifications to be reported to NRC in writing within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> and other Violations (of applicable statutes, codes, regulations, oroers, Technical Specifications, license requirements or of it,ternal procedures or instructions) having nuclear safety significance.

c.

Issues of safety significance identified by the Plant General Manager, the NSB Chairman, Executive Engineer NAPO or the PRC.

d.

Proposed changes'in the operating license or Appendix "A" Technical Specifications.

e.

The results of actions taken to correct deficiencies identified by the audit program specified in Specification 6.5.2.8.2 at least once every six months.

f.

Safety evaluations for changes to procedures, equipment, or systems and tests or experiments completed under the' provisions of 10 CFR 50.59, to verify that such actions did not constitute an unreviewed safety question.

g.

Maintain cognizance of PRC activities through NAP 0 attendance at scheduled PRC meetings or through review of PRC meeting minutes.

AUDITS 6.5.2.8.2 ' Audits of operational nuclear safety-related facility activities shall be performed under the cognizance of NSB.

These audits shall encompass:

a.

The conformance of plant operation to provisions contained within the Technicsl Specifications and applicable license conditions at least once per 12 months.

b.

The performance, training and qualifications of the entire facility

. staff at least once per 12 months.

6-8 Amendment No. 75

ADMINISTRATIVE CONTROLS The performance of activities required by the operatforal quality c.

assurance program (CPC-2A QAPC) to meet the criteria of Appendix "B", 30 CFR 50, at least once per 24 months.

..a d.

The Site Emergency Plan.a'nd implementing procedures at least once per 12 months.

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e.

The Site Security Plan and implementing procedures (as required by the Site Security Plan) at least once per 12 months.

f.

Any other area of plant operation considered appropriate by NSB or the Vice President-Nuclear Operations, g,' The plant Fire Protection Program and implementing procedures 7

at least once per 24 months.

h.

An independent fire protection and loss prevention inspection and audit shall be performed anaually utilizing either qualified offsite licensee personnel or an outside fire protection firm.

i. An inspection and aucit of the fire protection and less prevention program shall be performed by an outside qualified fire consultant at intervals no greater than 3 years.

Audit reports encompassed by Specification 6.5.2.8.2 above shall be forwarded to the NSB Vice Chairman and Secretary, and Management positions responsi310 for the areas audited within thirty (30) days after completion of the audit.

G AUTHORITY 6.5.2.9 The NSB Chairman shall report to and advise the Vice' President -

Nuclear Operations of significant findings associated with NSB activities and of recommendations related to improving plant nuclear safety performance.

l 6-9 Amendment No. 75

ADMINISTRATIVE CONTROLS RECORDS Records of NSB.acti'ities~ shall 'txi prepared and distributed as 6.5.2.10 v

indicated below:

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a.

Minutes of each NSB meeting shall be prepared and forwarded to the Vice President - Nuclear Operations and each NSB member within approximately two weeks following the meeting.

b.

If not included in NSB meeting minutes, reports of reviews encompassed by Specification 6.5.2.8.1 shall be prepared and forwarded to the Vice President - Nuclear Operations within

~ approximately two, weeks following completion of the review.

6.6 (Deleted) 6.7 SAFETY LIMIT VIOLATION 6.7.1 The following actions shall be taken in the event a safety limit is violated:

a.

The reactor shall be shut down immediately and not restarted until the Commission' authorizes resumption of operation (10 CFR 50.36(c)(1)(1)(A)).

b.

The safety limit violation shall be reported within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> to the Commission in accordance with 10 CFR 50.36, as.well as to the Vice 9,

President-Nuclear Operations and to the Chairman - NSB.

c.

A report shall be prepared in accordance with 10 CFR 50.36 and 6.9 of this specification.

(The safety limit violation and the report shall be reviewed by the PRC.)

d.

The report shall be submitted within 14 days to the Commission (in -

accordance' with the requirements of 10 CFR 50.36), to the Vice President - Nuclear Operations and to the Chairman -NSB.

6.8. PROCEDURES 6.8.1 Written procedures shall be established, implemented and maintained covering the activities referenced below:

a.

The applicable procedures recommended in Appendix "A" of Regulatory Guide 1.33 Quality Assurance Program Requirements, as endorsed by CPC-2A QAPD.

b.. Refueling operations.

c.

Surveillance and test activities of safety-related equipment.

6-10 Amendment No. 37, 75 e

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ADMINISTRATIVE CONTROLS d.

Site Security Plan implementation.

e.

Site Emergency' Plan:im'plementation.

f.

Site Fire Protection Program implementation.

6.8.2 PRC is respon.;ible for the review of each procedure of 6.8.1 above, and changes thereto (except for Security Implementing Procedures which are reviewed and approved in accordance with the Site Security Plan). The Plant General Manager shall approve such procedures and changes prior to implementation.

6.8.3 Temporary changes to procedures of Specification 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 (or designated alternates) of the PRC, at least one of whom holds a Senior Reactor Operator'.s License.

c.

The change is documented, reviewed by the PRC at the next regularly scneduled meeting and approved by the Plant General Manager.

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6-10a Amendment No. 75

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