ML20058G418

Amend 132 to License DPR-35,revising Tech Specs to Make Nomenclature Changes Consistent W/Sts & Remove Requirements That Technical Section Manager Must Hold SRO License & Head Operations Review Committee

ML20058G418
Person / Time
Site:	Pilgrim
Issue date:	11/05/1990
From:	Wessman R Office of Nuclear Reactor Regulation
To:
Shared Package
ML20058G421	List: ML20058G418 ML20058G426
References
NUDOCS 9011130135
Download: ML20058G418 (19)

Text

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[(jnPE80g I*g UNITED STATES g

NUCLEAR REGULATORY COMMISSION

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WASHINGTON, D. C. 20665

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BOSTON EDISON COMPANY DOCKET _N0_._50-293

$1. GRIM _ NUCLEAR _ POWER _ STATION AMENDMENT _T0_FAC_lLITLOPERATINGLICENSE Amendment No. 132 License No. DPR-35 1.

The Nuclear Regulatory Comission (the Comission or the NRC) has found that:

A.

The application for amendment filed by the Boston Edison Company (the licensee) dated August 9,1990, complies with the standards and i

requirements of the Atomic Energy Act of 1954, as amended (the Act),

and the Comission'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 Comission; C.

There'is-reasonable assurance: (1)thattheactivitiesauthorizedby this amendment can be conducted without endangering the health and safety of the public and (ii) that such activities will be conducted i

in compliance with the Comission's regulations set forth in 10 CFR Chapter.I; D.

The issuance of.this amendment will not be inimical to the common j

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 4

satisfied.

i 2.

Accordingly, the license is amended by changes to the Technical Specifica-tions as indicated in the attachment to this license amendment, and paragraph 3.8 of Facility Operating License No. DPR-35 is hereby amended to read as follows:

Techni_ cal Specif_icat_ ions The Technical Specifications contained in Appendix A, as revised through Ameniment No. 132, are hereby incorporated in the license.

The licensee shall operate the facility in accordance with the Technical Sr.ecifications.

L 9011130135 901105 PDR ADOCK 05000293 P

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This license amendment is effective as of its date of issuance and shall be implemented within 30 days.

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FOR THE NUCLEAR REGULATORY COMMIS$10N Richard H. Wessman, Director Project Directorate I-3 Division of Reactor Projects - 1/11 Office 6f Nuclear Reactor Regulation Attachnent:

Charges to the Technical Specifications Date of Issuance:

November 5,1990 e

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., s.g ETACHMENT TO LICENSE AMENDMENT NO.132 FACILITY OPERATING LICENSE NO. DPR-35 DOCKET NO. 50-293 Replace the following pages of the Appendix A Technical Specifications with the attached pages. The revised pages are identified by Amendr.ent nusber and contain vertical lines indicating the area of change.

Remove Insert iii iii 208 208 208a 209 209 210 210 211 211 212 212 213 213 214 214 215 P15 216 216 217 217 PIB 218 219 220 220 221 221 222 222 223 224 225 226 221 228 t

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Pace No.

4.0.

MISCELLANEOUS RADIOACTIVE MATERIALS SOURCES 206k 4.1 Sealed Source Contamination 206k 4.2 Surveillance Requirements 206k 4.3 Reports 2061 4.4 Records Retention 2061 5.0 MAJOR DESIGN FEATURES 206m 5.1 Site Features 206m 5.2 Reactor 206m S.3 Reactor Vessel 206m 5.4 Containment 206m 5.5 Fuel Storage 207 5.6 Seismic Design 207 6.0 ADMINISTRATIVE CONTROLS 208 6.1 Responsibility 208 6.2 Organization 208 6.3 Unit Staff Qualifications 209 6.4 Training 209 6.5 Review and Audit 211 6.6 Reportable Event Action 215 6.7 Safety Limit Violation 216 6.8 Procedures 216

'6.9 Reporting Requirements 217 6.10 Record Retention 219 6.11 Radiation Protection Program 221 6.12

.(Deleted) 6.13 High Radiation Area 221 6.14 Fire Protection Program 222 Ooerational Obigu;1hn Surveillantt 7.0 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM 8.0 229 17.1 Mor.itoring Program 8.1 229 7.2 Dose - Liquids.

8.2 232 7.3 Dose - Noble Gases 8.3 233 7.4-Dose - Iodine-131 Iodine-133, 8.4 234 Radioactive Material in Particulate Form, and Tritium 7.5 Total Dose 8.5 234 Amendment No. 35, 45, 88, 89, 95,122,132 lii

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6.0 ADMINISTRATIVE CONTROLS 6.1 RESPONSIBILITY The Station Director shall be accountable for overall facility operation.

In his absence, the Station Director shall designate, in writing, the individual to assume this responsibility.

6.2 ORGANIZATION A.

OFFSITE AND ONSITE ORGANIZATIONS Onsite and offsite organizations shall be establish 1 for unit i

operation and corporate management, respectively. The onsite and offsite organicitions shall include the positions for activities affecting the,afety of the nuclear power plant.

1.

Lines of authority, responsibility, and communication shall be established and defined for the highest management levels through intermediate levels to and including all operating organization positions. These relationships shall be documented and apdated, as appropriate, in the form of organization charts, functional descriptions of departmental responsibilities and relationships, and job descriptions for key personnel positions, or in equivalent forms of documentation.

These requirements shall be documented in Pilgrim Station Final Safety Analysis Report.

2.

The Station Director shall be responsibve for overall unit safe operation and shall have control over those onsite activities necessary for safe operation and maintenance of the plant.

3.

The Senior Vice President - Nuclear shall have corporate responsibility for overall plant nuclear safety and shall take any measures needed to ensure acceptable performance of the staff in operating, ma'O.ining, and providing technical support to the plant to ensure nuclear safety.

4.

.The individuals who train the operating staff and those who carry out health physics and quality assurance functions may report to the appropriate onsite manager; however, they shall have sufficient organizational freedom to ensure their independence from operating pressures, l

B.

UNIT STAFF l

1.

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

l Amendment No. 69, 80, 88, 722, 125, 132 208

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6.0' ADMINISTRATIVE CONTROLS

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. When the unit is in an operational mode other than cold shutdown

'or refueling,-a person holding a Senior Reactor Operator License x

shall be present in the control room at all-times.

In CJdition to this Senior Operator, a Licensed Operator or Senior Operator 4,

shall be present at the controis when fuel is in the vessel.

L At least two' Licensed Operators shall be present in~ the control room during reactor startup, scheduled reactor shutdown and 3

during recovery from reactor trips.

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m 4.

An individual qualified in radiation protection procedures shall

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be on site when fuel is in the reactor.

S.,

ALL CORE ALTERATIONS performed while fuel is in the reactor vessel after the initial fuel loading shall~be directly M"e supervised by either a licensed Senior Reactor Operator or y

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Senior. Reactor Operator Limited to Fuel Handling who has no

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o Wer concurrent responsibilities during this operation.

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6.

A Fire Brigade of 5 members including a Fire Brigade Leader shall be. maintained on site at all times.

This excludes 3 members of the minimum-shift crew necessary for safe shutdown; and any personnel required for ~other essential functions during i

al fire emergency.

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7.-

The: Chief Operating Engineer, Nuclear Watch balneers, and

-l Nuclear Operations. Supervisors.shall hold a h or Reactor 4

e i0perator License. The Nuclear Plant Operators shall hold ~a Reactor. Operator License.

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. 6.3 K UNIT STAFF OUALIFJCATIONS

. The qualifications with; regard to educational and experience backgrounds

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(1 L of the unit' staff.at the; time of appointment to the active position sh W l

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' meet the:requirementscasadescribed in the American National Standards-Institute N18.1-1971,.'" Selection, and Training of Personnel for~ Nuclear.

u Power Plants."? Iniaddition, the individual performing the-function of (Radlation: Protection Manager shhl1 meet or exceed the qualifications of.

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Regulatory Guide 1;8,4 September, 1975.

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TRAINING p

A1 retraining and replacement training program for the: Unit staff shall~b~e. "l' maintained under the' direction of the Nucleat. Training Department W

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Manager.' ~The! training l programs-for.the-lictnsed, personnel shall meet or La

. exceed the requirements and: recommendations of Section 5.5 of ANSI j

N18'.1-1971/and Appendix A of 10CFR Part 55.' The training programs for

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M the. Fi re : Br'.gade t shallLmeet ot exceedithe requirements of WFPA Standard 4

No. 27-1976," Private Fire Brigade". ' Fire Protection Training. sessions 1

gV willJbe. held quarterly.-

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. Amendment No - 47, 46, 69,'88, 722, 125, 132 209 l

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PILGRIM NUCLEAR POWER STATION MINIMUM OPERATING SHILT CREW COMPOSITION TECHNICAL SPECIFICATION-t TABLE 6.2-1 5

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' STATION CREW (a)

MINIMUM NUMBER ON DUTY CONDITION

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t, OFERATING-Licensed Senior Reactor Operator 2 (b) a Licensed Reactor Operator 2

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o Unlicensed Operator 2

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Shift Technical Advisor 1

'I COLD SHUTDOHN Licensed Senior Reactor Operator 1

y Licensed Reactor Operator 1

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!and:

REFUELING Unlicensed Operator

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o Shift Technical Advisor None Required N

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Notes:

P grade. licensed operators may take the place of Iower-(a)' Higt.:

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,i grade-11cer. sed or unlicensed personnel.-

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- (b)f A: Shift Technica1LAdvisor -(STA).with a. Senior. Reactor Operator y

'M license may simultaneously serve as STA and SRO.-

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'6.5 REVIEW AND AUDIT.

A '.

OPERATIONS REVIEW COMMITTEE (ORC)

'1.

FUNCTION The ORC shall function to advise the Station Director on all matters related to safety.'

2.

COMPOSITION The ORC shall be composed of a Chairman, and at least six, members, who shall be appointed in writing by the Station.

Director from. senior experienced onsite individuals, at the manager level or equivalent, representing each of the following

, disciplines: plant operations, plant maintenance, plant technical, reactor engi noring, radiation protection, and chemistry,

3. ' ALTERNATES Alternates,shall be appointed in writing by the Station Director to serve on a temporary basis.

n 4.

MEETING FRE00ENCY

-The ORC shall meet at least once par calendar month and as 3,

convened by the ORC Chairman.

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5.

000 RUM i quorum of the 0RC shall consist of the Chairman or designated alternate-and.a majority of members / designated alternates;'

however, no'more than two alternates shall be allowed to meet m

quorum requirements.

6.

RESPONSIBILITIEji.

e ihe ORC shall.be responsibl'e for:-

a.' -Review of'1).'all procedures required by'Specificationl6.8 w

and changes'thereto, 2)Lany other proposed procedures or

changes thereto that affeet nuclear: safety.-

<D b.

Review all proposed tests.and experiments that affect

e nuclear safety.

c.

Review of;all: proposed changes to the Technical

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. Specifications.

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d.

Review of.all propc;ed changes-or modifications to plant

-systems or equipment that affect nuclear safety.

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. Amendmant No. 46, 69, '88' 722,132 211 l

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'6.5.A.6 RESPONSIBILITIES (Continued)

e.. Review of facility operations to_ detect potential. safety hazards.

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f.

Review of-the Station Security Plan and implementing procedures and changes to the plan and procedures.

g.

Review of the Emergency Plan and-implementing procedures and v

changes to the plan and procedures.

.h.

Performance of special reviews and investigations and reports thereon as requested by the Nuclear Safety Review and Audit. Committee (NSRAC) Chairman.

i.

Investigation of all violations of the Technical J

Specifications and-shall prepare and forward a report._

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covering evaluation and recommendations to prevent recurrence to the -Station Director, the NSRAC Chairman, and the Senior n

Vice President - Nuclear, j.

Review the Station Fire Protection Plan and implementing-procedures and changes to the plan and procedures.

The ORC Chairman may appoint subcommittees composed of personnel

'who'are not members;of ORC to perform staff work necessary to Lthe~ efficient functioning of ORC.

=7.--AUTHORITY

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. Recommend in writing to<thi Station Director the approval a,

-or; disapproval of. items' considered under 6.5.A.6(a) through1(d) above.

ce b.' ! Render determinationsLin writing with. regard to whether or

,'i not,each item considered:under 6.5.A.6(a),through (d) above e J*

constitutesian'unreviewed. safety. question.-

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Provide written notification.within'24: hours--to the Station

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Oirector.cthe.NuclearfSafety Review and Audit Committee, W.

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and the Senior Vice' President:- Nuclear ofidisagreement

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'between the ORC Members and the ORC Chairman.::The Station Directorcshall'have responsibility for resolution;of such g' ;g s disagreements.

8.

RECORDS

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The ORC shall maintain written minutes'of each meeting and copies s

shall be forwarded to the Station Director and the NSRAC Chairman.

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TAmendment No. 29, 46, 69, 88,122,J132 212 l

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'.5.8.

NUCLEAR' SAFETY REVIEW AND AUDIT COMMITTEE (NSRAC) l 6

n.

1.'

FUNCTION The NSRAC shall function to provide independent review and audit of designated activities in the areas of:

1.

nuclear power plant operations; 2.

nuclear engineering;-

1 3.

chemistry and radiochemistry; 4..

metallurgy; 5.

instrumentation and control; 6.

radiological safety; 7.

mechanical and electrical engineering; 8.

quality assurancs practices 1

-9, fire protection 2.

COMPOSITIDN-The NSRAC Chairman'and other members shall b6 appointed by the Senior Vice President - Nuclear.

The membership shall collectively possess a broad based-level of experience and competence ensbling the Committee to review and audit-h those activities designated in 6.5.B.1 above and to recognize when it is;necessary to obtain technicel advice and counsel. The collective

. competence of the Committee will be maintained as. changes to the membership'are made.. The membership shall consist of a minimum-ofc

~ finpersons of:whom no more than a. minority are members of the plant

-staff.i

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3. ALTERNATESn ha jAlternate members, shall be appointed in writing by the Senior-Vice.

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. J President -LNuclear or the Chairman to serve on a temporary basis.

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-4.

>CONSULTANIS

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Consultants shall be utilized as determined by the'NSRAC Chairman to W

. provide expert advice'to;the NSRAC'..

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'The'NSRAC shal,1 meet at-least.once per six months.

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na 14 m1 A# quorum of the NSRAC shall' consist of the Chairman or his designated g

alternate and at least four NSRAC members including. alternates. The.

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V1ce. Chairman is?.the' designated alternate to-the Chairman. No~more a

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-than a minor 1ty'of the quorum shall-have line responsibility for,-

3i4 operation of the facility.; No more than tw'o alternates shall'

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-participate lin a quorum at any one. time.

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l Amendment No.' $9, pp,.799, 132 q

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..;+w 6.5.B-L(Continued)~

-w 7.; REVIEW The NSRAC shall review:

a.

The written safety evaluations for:

(1) changes in the facility as described in the Final Safety-Analysis Report; (2)- changes in the procedures described in Chapter 13 of the-Final Safety Analysis Report; (3) - test and experiments not described in the Final Safety Analysis-Report to verify that such changes, tests or experiments did not involve a change in the-Technical Spec;fications or an unreviewed safety question as defined-in 10CFR50.59(a)(2).

ze b.s Proposed changes to procedures, equipment or systems'which involve

-an unreviewed safety question as defined in Section 50.59,10 CFR.

c '. ' Proposed tests or experiments ~which involve an unreviewed safety

' question as_ defined-in Section 50.59, 10 CFR.

d. LProposed changes in Technical Specifications or operating. license..

4

.e.

Violations'of. applicable statutes, codes, regulat'ons, orders, f

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. Technical Specifications, license requirements...or of internal f

- procedures 3or; instructions having. nuclear safetyz significance.

f. -Significant operating abnormalities or deviations from normal and

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expected performance of. plant equipment that effect nuclear safety,

-A'l events which1are required by 10.CFR 50.73 to'be reported to, l

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'the NR_Cjin' writing.-

4 j.a [Any other matter involving safe operation;of: the. nuclear plant :

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which NSRAC deems appropriate for consideratio; r which.is' referred to'NSRAC forLthe onsite operating oro nization or by f

other functional organizational' units within Boston: Edison'.

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11b ReportsLand meeting minutes of the Operations Review. Committee.

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Audit's ofifacility.' activities shall be _ performed under the cognizance, of the NSRAC." These audits snall encompass-m w"

a.t The?c6nformance of. facility operation'to provisions contained withinthe TechnicaltSpecifications and' applicable license j

'conditio' seat;leastonceperyear.

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..f L he training and'_ qualifications of'the entire unit staff'at least' l

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once per year.

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i 6'.S.B 8. AUDITS (Continued)

' c.

The results of all actions required by deficiencies occurring in

~ ~ facility equipment, structures, systems or method of operation that affect nuclear safety at least once per six months.

-d..The performance of all activities required by the Quality Assurance Program to meet the criteria of Appendix "B",

10 CFR 50, i

at least once per two years, e.

The Emergency Plan.and it,11ementing procedures at least once per two years.

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f.

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

-g.

Any other area of facility operation considered appropriate by the

'NSRAC or the Senior Vice President - Nuclear.

b.

The Fir's Protection Program and implementing rrocedures at least

~g" On:e per two years.

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j9. AUTHORITY

The NSRAC shall report to and advise the Senior Vice President -

Nuclear on those areas of responsibility specified in Section 6.5.B.7

. and. 6. 5'. B. B.

L10,: RECORDS; 4-Records'of NSRAC activities shail be prepared, approved and g'

distributed:as indicated below:

i

at ; Minutes of each NSRAC meeting shall be prepared,; approved and p'

forwarded to the. Senior, Vice. President - Nuclear, NSRAC members.

' and othersithe Chairman may designate.

b.[ Reports of' reviews encompassed by Section"6.5.th7.e f,.g and h

-above,ishallibe' prepared,: approved and-forwarded to-the: Senior-

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Vice President

. Nuclear..with a copy tolthe Station Director

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Ewithin 21 days following the completion of the review.'

1 c.

Audit : reports encompassed by'Section 6.S.B.8' above shall be forwarded..to the Senior Vice President : Nuclear,and to the=

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, tmanagement positions: responsible:for:the areas; audited within 30.

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tdayssafter completion of.the audit.

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6l.6LREPORTABLE' EVENT ACTION

~.The following actionsLshallLbe t'aken for.each reportable event:

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.A.

The Commission shall be notified and/or a report submitted pursuant to

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thI requirements of' either 10 CFR 50.72 or 10 CFR'50.73.

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B; Each Reportable' Event Report submitted to'the Commission shall be

,a reviewed:by the ORC and submitted to the NSRAC Chairman -and the t

Station >0irector.

Amendment No; < d6i 69, 74, 88,: 104,1122,,132 215

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g,; e 6.7 SAFETY LIMIT VIOLATION 4

The following actions shall be taken in the event a Safety Limit is violated:

A.

The provisions of 10 CFR 50.36(c) (1) (i) (A) shall be complied with l

Imediately.

1 B.

The Safety Limit Violation shall be reported to the Commission within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> per 10CFR50.36(c)(6) and 50.72, and to the Station Director and the NSRAC Chairman imediately.

C.

A Safety Limit Violation. Report shall be prepared. The report shall be reviewed by the ORC.

This report shall 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.

cThe Safety Limit Violation Report shall be submitted to the Comission within 30 days in accordance with 10CFR50.36(c)(7) and'50.73 and to the NSRAC Chairman and the Station Director, c

6.8.PROCEDUJES A.

Written procedures and administrative policies shall be established, Limplemented and maintained that meet or exceed the requirements and "recomendations of Sections 5.1 and 5.3 of ANSI N18.7 - 1972 and L Appendix "A" of USNRC Regulatory Guide 1.33, except as provided in

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,.6.8.B:and 6'.8.C below.

Bi Each procedure of 6.8 A above, and changes thereto,:shall.be reviewed by the' ORC and approved by the responsible department manager prior to

, implementation.. These procedures shall be reviewed. periodically as 1

1 set forth in administrative procedures..

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~ 0RC; review and approval of' procedures'for vendors / contractors, tiQlE:.

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who have a QA. Program approved.by Boston Edison Company; is not j

required!for.. work performed at the vendor / contractor. facility.

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..C.

Temporary changes to procedures of: 6.8,A' above"may: be made provided:.

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TheLintent of. the original procedure is not altered.

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'2.

The change is approved by two members.of the plant' management'.

staff, at least one of whom holdsLa(Senior Reactor Operator's-

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license'on:the unit affected.

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The change is documented, subsequently reviewed by '6e' ORC within p] ', M c14 days of implementation, and' approved by the,rmp uible-

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department manager.

D.

- Hritten procedures to implement the Fire Protection Program shal1 be 4

established, implemented and maintained, t

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I L6.9 REPORTING REOUIREMENTS In' addition to the applicable reporting requirements of Title 10 Code of

-N Federal Regulations, the following identified reports shall be submitted 4

4 to the Commission, q

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A..

Routine Reports

1. -

Startuo Renort. A summary report of plant startup and power escalation testing _shall be submitted following (1) receipt of an operating li_ cense, (2) amendment to the license involving a planned increase-in power level,'(3) installation of fuel that has a e,

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different' design or has been manufactured by a different fuel supplier, and (4) modifications that may have significantly altered the. nuclear', thermal,- or hydraulic performance of the plant. The report'shall address-each of the tests identified in the FSAR and shall in general include a description of the measured values of the operating concitions or characteristics obtained during the test g

program and a comparison of'these values with design predictions and A

specifications.. Any corrective actions that were required to obtain' 1

satisfactory operation shall also be described. Any additional

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specific details required in license conditions based on other

' commitments shall be included in this report, l'.

y Startup reports shall be submitted within (1) 90 days following

< completion of the:startup test program, (2) 90. days following resumption or~ commencement of comercial power operation, or (3) 9 L

months'following; initial criticality, whichever is earliest.

If the

.Startup Report does not cover all three events (i.e., initial l criticality,: completion of-startup test program, and resumption or commencement of commercial power operation), supplementary reports i

.shall'be submitted at"least every three months until all three events (have been completed..

I

's 2.

Monthlv Ooeratina Reoort.

Routinetreports of operatin statistics, y,

shutdown-experience and forced reductions in power sha 1 be submitted ~

oniaimonthly basis 1 to thelCommi.sion to arrive no later than'the 15th j

of each' month following the: calendar month covered by the report.

.w The Monthly Operating Report'shall' include'a narrative summary of

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operating experience that describes the operation of the facility,

' including safety-related maintenance, for the monthly report period.

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3." 10ccuoational Exocsure' Tabulation. A tabulation of the t. umber of

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. station,7 utility and other personnel (including contractors) l W

ireceiving exposures greater than 100 mrem /yr and their associated '

man-rem exposure according to-work andzjob functions, e'g. reactor

.y operationstand' surveillance inservice inspection, routine V

' maintenance,.special maintenance (including a description) waste:

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processing.nand refueling shall be submitted on an annJa1 basis.

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c This: tabulation supplements' the requirements of 20.407 of'.10 CFR 20.

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The dose assignment'to various duty funct_ ions may be estimates based

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on pocket'dosimeterJ TLD, or film badge measurements.. Small exposures totalling less than 20% of the individual total dose need

not be accounted for.

In the aggregate, at least 80% of the total wholetbody dose-received from external sources shall be assigned to

.p l specific major work functions.

B.: (Deleted:by Amendment No. 88)

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.6.9.C.

Uniaue Reoorti,e Reauirements 1.

Semi-Annual Radioactive Effluent Releae ReDort l

a.

Routine radioactive effluent release reports covering the j

operation of the unit during the previous 6 months of operation 3

shall be submitted within 60-days after Jancary 1 and July 1 of each year. The report should be in accordance with Appendix B of Regulatory Guide 1.21 (Revision 1) dated June, 1974. A supplemental report-containing dose assessments for the previous year shall be submitted annually within 90 days after January 1.

I b.

Any changes to the Offsite Dose Calculation Manual (00CN) shall 1

6 be submitted to the Commission in the Semi-Annual Radioactive Effluent Release Report.

2.-

Annual Radioloaical Environmental Monitorina Reoort 4

A report on the radiological environmental surveillance. program for the, previous _ calendar year of operation-shall be submitted to the Commission prior to May 1 of the year.. The reports shall include summaries, interpretations, and statistical evaluation of the results of the radiological environmental surveillance activities for the o

, report period, operational. controls and-previous environmental R:

y surveillance reports, and an assessment of the' observed, impacts of the plant operation on the environment. The reports'shall also W ~

. include the resultsLof-any land use surveys which' affect the choice l

i of samplet ocations,. If harmful effects or-evidence of irreversible -

l Ti dama p are: detected by the monitoring, the licensee,shall provide an analysis of the problem and a proposed course of action to alleviate y

Lthe. problem.

The Annual Radiological Environmental Monitoring Report shall include l

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' a summary of the results of: analysis of all radiological

. environmental ~ samples and of.al1 environmental radiation measurementsL taken during the period pursuant; to;the locations specified in the table:and figures in the Offsite Dose Calculation Manual (00CM) as

-f well as summarized and tabulated results of these analyses and

~

3:

measurementsnin the: format of the -table?inithe Radiological ~

h LAssessment' Branch TechnicaloPosition, Revision 1,7 November 1979.

L In the event that some results are not'available prior to May 1.of L

M the: year,'the report.shall be submitted, noting and explaining the reasons _ for the missing results.

The missing. data shall be submitted N'

1 as soon.as'possible in a supplementary report.:

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,s a summary description

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The report shall also. include the following:

s

-of the. radio logical environmental monitoring program;; at least. two 1

0'

' legible maps covering all sampling locations keyedito a.. table giving; i

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distances and directionsLfrom the centerline of the-reactor; a

discussion efL all deviations from the sampling schedule of, Table:

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8.1-1; and.diseussion of all analyses in'which the lower' limits of detection (LLD) required by Table 8.1-4 were' not achievable.

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0ne. map shal.1; cover stations near the' site boundary; a

second shall include the more distant stations.

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Amendment' No. 23, 57, 89,103. JI6,132 218.

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'6.9.C Uniaue Renortina Reauirements (Continued) l~

3.

Snecial Reports Special reports shall be submitted as indicated in Table 6.9.1.

6.10 RECORD RETENTION ~

A._

The,following ?ecords shall be retained for at 19ast five years:

1. _

Records of facility operation covering time interval at each power level, i

2.

Records of principal. maintenance activities, inspections, repair and replacement of principal items of equipment related t

to nuclear safety.-

3.

Reportable Event Reports,

n. -

4.-

Records-of' surveillance activities, inspections-and calibrations required by these Technical Specifications, t

l

.5.

Records of reactor tests and experiments.

6. -

Records of changes made to Operating Procedures.

}

-7..

Records of radioactive shipments.

8.

Records of sealed source leak tests and results.

9..

Records of; annual ph/sical inventory of all source material of

.I record.-

B.

lThe following records shall be retained for th? dvation of the l

Operating License.

i(

- 1.

Recor'd a'nd: drawing. changes reflecting facility design -

modifications made:to systems andLequipment described in the

. Final' Safety. Analysis ~ Report, a

2.-

Records of new and.. irradiated fuel inver: tory, fuel transfers 3

and1 assembly burnup histories.

30 Records-of facility: radiation.and contamination surveys.

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4.

. Records'of radiation exposure for all individuals entering f

radiation control arean B v*n.

5.

' Records:of the service lives of;all hydraulic and mechanical l~

snubbers listed in'PNPS procedures including theidate at which_

i M'C the'servic' tlife commences and associated installation and; J

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maintenance records.

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Amendment No. 20, 60, ' f B, 93.132--

219 l ;

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TABLE 6.9.1 k

Ar.11 Reference submittal Datg

a.

Secondary Containment 4.7.C.1.c Upon completion of Leak' Rate Testing (1) each tett (2) is b.

(Deleted) c.

(Deleted) s d.

(Deleted)

_e.

Standby Liquid Control 3.4.C.3 Fourteen days after solution enrichment out receipt of a non-of specification complying enrichment

.c report or lack of receipt of such a report within the required thirty days, if enrichment compliance cannot be achieved within seven days.

~'

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. NOTES:

1.

Each integrated leak rate test of the secondary containment shall49 the subject of a rummary technical report. This report; shall'

1c!Je data on the wind speed, wind direction, outside, and int,ide temperatures during the test, concurrent reactor' building pressure, and emergency ventilation flow rate.. The report shall also include analyses and interpretations of those l data which: demonstrate compliance with the specified leak rate J

limits, m.

2..

Thefreportshall.be. submitted'approximately90 days'after completion of each test.

Test periods'shall be based onithe1 i;

commercial service date as the' starting point.

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Amendment No. 702,- 713, 132 220

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76.10.8 ' RECORD RETENTION (Continued) 6 Records of. gaseous and liquid radioactive material released to the environs.

7.

Records of transient or operational cycles for those facility components designed for a limited number of transients or cycles.

8.

Records ~of training and qualification fcc :urhint members of the plant staff.

-9.

Records of in-service inspections performed pursuant to these Technical Specifications.

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10.

Records of Quality Assurance activities required by the QA Manual.

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11. Records of reviews performed for changes made to procedures or.

t equipment or reviews of tests and experiments pursuant to 4

-10 CFR 50.59.

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12., Records of meetings of the ORC and the NSRAC.

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13; -Records for, Environmental Qualification.

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f6.11..BADIATION PROTECTION PROGRAE Procedirres for personnel radiation protection shall be prepared' consistent:with the. requirements of 10 CFR Part 20 and shall be

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approved;: maintained-and adhered to for a11' operations involving

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4, personnel radiation: exposure, j

6.121 (Deleted)-

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.6.'13i.HIGH RADIATION AREA (OPTIONAL)-

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6.1301 ;In-lieu of the:"contro11 device"Jor " alarm signal _"Lrequired by.

paragraph 20.203(c)(2):of?10 CFR 20.-each high; radiation area in which i

N 1,

- the intensity of radiation is greater than 100 arem/hr buthless= than -

1000! mrem /hr shal.1 be-barricaded and: conspicuously posted as a high.

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, radiation = area and, entrance' thereto shalli.be. controlled by. r$quirir 4

issuance of a Radiation Hork Permit *. AnyLindividual or, group of' fs,.

Lindividualstpermitted to enter such areas shall be provided_with or i

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.3 raccompanied by?one or more of the following::

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LA' radiation monitoring: device which continuously indicates the-4 f n7 radiation'doseirate:in~the area.

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• " Health; Physics personnel or personnel ' escorted by Health Physics personnel shall.

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be; exempt from the RWPaissuance requirements.during the performance'of this.

cassigned radiation protection. duties, provided they comply with' approved' 4

, radiation protectionLprocedures for entry into high= radiation areas.-

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- 221 L;l.'

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6.13.1 tgGf RADIATION AREA (Continued)

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bl A radiation monitoring device which continuously integrates the i

radiation dose rate in the area and alarms when a preset integrated dose is received. Entry into such areas with this monitoring device'may be made after the dose rate level in the area has been established and personnel have been made

' knowledgeable of them.

c.

An-ind1Yidual qualified in radiation protection procedures who is equipped with a radiation dose rate monitoring device. This individual shall be responsible for providing positive control

?

over the activities within the area and-shall perform periodic radiation surveillance at the frequency specified by the Radiation Protection Manager in the Radiation Work Permit.

~

6.13.~ 2 ' The requirements of 6.13.1, above, shall also apply to each high radiation area.in which the intensity of radiation is greater than 1000 mrem /hr. 'In addition, locked doors shall be provided to prevent f"

unauthorized entry into such areas and the keys shall be maintained i

under the administrative control of the Nuclear Hatch Engineer on duty and/or the' Radiation Protection Manager, b,,

.6.1'4 FIRE' PROTECTION PROGRAM i

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1 1

The following' inspections and audits shall be performed:

h 1.

An independentsfire protection. inspection and audit shall be A

performed annually utilizing either qualified off-site licensee personnel'_or an outside fire protection firm.

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'2.

An inspection and audit by an outside qualified fire consultant shall A

beiperformed at intervals no greater than 3 years..

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(The next page.is.229)'

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'AmendmentNo.30.45,122,132 222

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