ML20205P851

Amend 10 to License NPF-39,modifying Tech Specs to Reflect New Corporate & New Plant Staff Organizational Structure & Revised Composition of Plant Operations Review Committee

ML20205P851
Person / Time
Site:	Limerick
Issue date:	10/31/1988
From:	Butler W Office of Nuclear Reactor Regulation
To:
Shared Package
ML20205P856	List: ML20205P851 ML20205P863
References
NUDOCS 8811080330
Download: ML20205P851 (17)

Text

/'va a'%.,

[

'%)

UNITED STATES NUCLEAR REGULATORY COMMISSION y,

q.

l WAssiNoToN, p. c. 20sss

\\.....,e PHILADELPHIA ELECTRIC COMPANY DOCKET NO. 50-352 LIVERICK GENERATING STATION, UNIT 1 AMENCMENT TO FACILITY OPEPATING LICENSE Amendment No.10 License No. NPF-39 1.

The Nuclear Regulatory Cermission (the Comission) has found that A.

The application for amendment by Philadelphia Electric Company (the licensee) dated November 18, 1987, complies with the standards and 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; 8.

The facility will operate in conformity with the application, the provisiens of the Act, and the rules and regulations of the Cornission; C.

There is reasonable assurance (i) that the activities authorized by this amendment can be conducted withnut endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Cornmission'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 Comission's regulations and all applicable requirements have been satisfied.

2.

Accordingly, the license i amended by changes to the Technical Specifications as indicated in the attachment to this license amendtrent, and paragraph 2.C.(2) of Facility Operating License No. NPF-39 is hereby amended to read as folicws:

Technical Specifications The Technical Specifications contained in Appendix A and the Environmental Protection P'ian contained in Appendix B, as revised through Amendment No.10

, are hereby incorporated into this license.

Philadelphia Electric Company shall operate the facility in accordance with the Technical Specifications and the Envirormental Protection Plan.

f[Ogggy $$a$

g{

e

2 3.

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

FOR THE NUCLEAR REGULATORY COMMISSION

/N

((

v Walter R. Butler, Director Project Directorate I-2 Division of Reactor Projects 1/II Attachttent:

l Charoes to the Technical j

Specificatiens Date of Issuance: October 31. 1988 I

I l

ATTACHMENT TO LICENSE AMENDMENT NO.10 FACILITY OPERATING LICENSE NO.,NPF-39 00CKET NO. 50-352 Replace the following pages of the Appendix A Technical Specifications with the attached pages. The revised pages are identified by Amendment number and contain vertical lines indicating the area of change. Overleaf pages are provided to maintain document completeness.*

l Remove Insert I

6-1 6-1 6-2 6-2 l

l 6-3 6-3 6-4 6-4 6-5*

6-5*

6-6 6-6 l

6-7 6-7 6-8 6-8 i

6-9 6-9 6-10*

6-10*

6-11 6-11 6-12 6-12 6-13 6-13 6-14*

6-14*

l l

6.0 ADMINISTRATIVE CONTROLS 6.1 RESPONSIBILITY 6.1.1 The Plar.t Manager shall be responsible for overall unit operation and l

shall delegate in writing the succession to this responsibility during his absence.

6.1. 2 The Shif t Supervisor, or during his absence from the control room, a designated individual shall be responsible for the control room command function.

A management directive to this effect, signed by the Vice President, Limerick Generating Station shall be reissued to all station personnel on an annual basis.

6.2 ORGANIZATION OFFSITE 6.2.1 The offsite organization for unit management and technical support shall be as shown on Figure 6.2.1-1.

UNIT STAFF 6.2.2 The unit organization shall be as shown on Figure 6.2.2-1 and:

Each on duty shift shall be composed of at least the minimum shif t a.

crew composition shown in Table 6.2.2-1; b.

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

In addition, while the unit is in OPERATIONAL t

CON 0! TION 1, 2, or 3. at least one licensed Senior Operator shall be in the control room; c.

A Health Physics Technician

• shall be on site when fuel is in the reactor; d.

ALL CORE ALTERATIONS shall be observed and directly supervised by either a licensed Senior Or erator or licensed Senior Operator Limited to Fuel Handling who has n other concurrent responsibilities during i

this operation; e.

A site fire brigade of r. least five members shall be maintained on site at all times.

The fire brigade shall not include the Shift a

Superintendent, the Shif t Technical Advisor, nor the two other members of the minimum shift crew necessary for safe shutdown of the unit and any personnel required for other essential functions during a fire emergency; and "The Health Physics Technician and 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 />, in order to accomodate unexpected absence, provided immediate action is taken to fill the required positions, j

L1HERICK - UNIT 1 6-1 Arendment No.10

ADMINISTRATIVE CONTROLS UNIT STAFF (continued) f.

Administrative procedures shall be C sped and implemented to limit the working hours of unit staff who perform safety-related functions (e.g., licensed Senior Operators, licensed Operators, health physi-cists, auxiliary operators, and key maintenance personnel).

Adequate shift coverage shall be maintained without routine heavy use of overtime.

The objective shall be to have operating personnel work a normal 8-hour day, 40-hour week while the unit is operating.

However, in the event that unforeseen problems require substantial amounts of overtime to be used, or during extended periods of shut-down for refueling, major maintenance, or major unit modifications, on a temporary basis the following guidelines shall be followed:

1.

An individual should not be permitted to work more than 16 hours1.851852e-4 days <br />0.00444 hours <br />2.645503e-5 weeks <br />6.088e-6 months <br /> straight, excluding shif t turnover time.

2.

An individual should not be permitted to work more than 16 hours1.851852e-4 days <br />0.00444 hours <br />2.645503e-5 weeks <br />6.088e-6 months <br /> in any 24-hour period, nor more than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> in any 48-hour period, nor more than 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> in any 7-day period, all excluding shift turnover time.

3.

A break of at least 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> should be allowed between work periods, including shift turnover time.

4.

Except during extended shutdown periods, the use of overtime should be considered on an individual basis and not for the. entire staff on a shift.

Any deviation from the above guidelines sh&l! be authorized by the Plant Manager or the Superintendent Operations, (Nr operating per-sonnel) or the Superintendent Maintenance /Instrumertation and Controls (for key maintenance and instrument and control personnel), or the Superintendent-Plant Services (for chemistry and health physics per-sonnel) or the Superintendent-Technical (for technical personnel), or the Superintendent-Modifications (for construction personnel) or their designee or higher levels of management, in accordance with established procedures and with documentation of the basis for granting the devia-tion.

Controls shall be included in the procedures such that individual overtime shall be reviewed monthly by the Plant Manager, or the appro-priate superintendents or their designees to assure that excessive hours have not been assigned.

Routine deviation from the above guide-lines is not authorized.

LIMERICK - UNIT 1 6-2 bend ent No. 10

PHILADELPHI A ELECTRIC COMPANY

.I C;

NUCLEAR MANAGEMENT ORGANIZ ATION CH ART E

=

h l

80ARD OF DIRECTORS l

I e

e CH AIRMAN Of IHE 110ARD 2

8 CHIEF EXECUTIVE OfrICER e

PREstDENT 8 CHIEF OPERAilNC OfflCER i

NUCliAR SENIOR VICE PRESIDENT REvi[W B04RD NUCL E AR DNSI TE OFFSITE I

e e

e e

e i

i e

e i

i e

l VICE PRESIDENT VICE PRESIDEMI GENERAE MANAGER l

VICE PREST DE NI VICE PRESIDENT e

e WCRM NUC R M NUCLEAR OHAllIY e

e L IMIRICK PF ACH 110!IOM l

l SERylCES ENGINEERING ASSURANCE e

e e

e i

e l

M A R e

MANAGE R MANAGE R s ',

e I

PL ANI PLANT e

e PflAPS e

MmCE R MmMR leu U AR MurMAR

1. III MAINI.

EleCissEERING e

e e

e l LIIIEHICK MANAGER e

e e

e

~

PROJE C I

~

PROJECI e

e MANACER asAe6AC[R MANAGE R l

l ENGI8E E RI NG l

OUAL I T Y l

~

e o

e e

P e

e e

MANAGE R e

e e

e t'ANa qE R l

MANAGE R d

OUMI T T ggy 9,, PORI e

s NUCl> q l

PROJEC T e

a e

e MANAQ R MANAM R e

e g

TR M NI _sc

,1 MANAGE tE NT e

e e

e l

v2 SiAR!ur l

l

= = cta MmCR PtRrORMANCC e

M =ActR e

e e

,E #

~

y e

MA8eAGE R e

e N. Up OMUAN e

e e

,, ir s, e

8 e

e e

e l

@THIS POSITIO86 MAY BE COttSi' NANAGER o

IbEO DitE IID Af ILR UNII ? e e

ggpg,LC$.7 e

s e

itAt LOAO.

e e

e e

e e

n

=

e e

s e

LCS PBAP.

e ist G istc l

l l

n --.

---

s t-------~~------------------

---

------- -e i1816HICE IMil 1 NUCLEAR MANAGEMENT CRGANIZATION CHART

v.

ORGANI Z ATIOt1 FOR CONOUCT OF Pt. ANT OPERATI ONS r-LIMERICK GENERATING STAllON E

vict en[51 star Li bel l41 CK e

E 3

g I

E 182 51 ARIlif*

PtANI SIIITORI P90JECI asA06ACIH g

NANAC[R MA80ACER MmEff

__ a Dri.

It?.l Aft lHP tt? STAftlte

,,$,gp g,g$

IftA4eeetec 9a*I. as*5 usPl 51s Timet g asu m55 m ism l

I I

l 88P8-e sEnE,%.

seri.

MR5mes[L 9,,

9,,

9,,

8841 NI.ti SC 1[CilM CAL OPf R4110085

~

g y,g g

e I

E

$[CURIIT WOSif AhlM A55g A551 Ott 18151 pg y g',

9s*I.ISC Elect esf1R 0,.c -

m SIFI.

sr.

5,,,,-

A551.

wC#. C.

.50 l

Sgrg.tM I t seCINE F R Manon 98E F I SHlf i 7

set AL 108 IS INI.

IAC RECIILA300lf 5tsPt. Sae0 LECH. ADV.

N" FIITSICISI

[......

s 2

wirr 45,1

~

50n 5.- =.

M. 20 M_L E seGI8stI N

~

asal asI.

IstC i

2 Copelse0L

@IllNER IHE Pt Affi MAf8ACER OR O

OPENAIOR RO SUPI. Of GPtAAIIONS 5HAtL HetD ASSI. CNille.

v OPERA 1988 840

@ [tINER lett WatIIIMIfIIDENI ItOtNICAL Oft IfCH8PCAL t4GipsI[R $NALL H0t D ggg IIC GPE RAleft ASSI. PL Asel

@ lHESE P058 TIO885 ISAT HE Mi[I[D OPl IIAlcet AfIlR 8888I 7 I15i IOAD.

Apult I mety I I(2384[ G.7.2 I I

ORGA80ll AflON f Det CsINilWCI Of Pt A808 fmTNAllOsti liIKHIfR t#H I I z.,.33-.

9-e f

v-

--e

'\\

TA8LE 6.2.2-1 MJNIMUMSHIFTCREWCOMPOSITION TWO UNITS WITH A C0$e40N CONTROL ROOM WITH UNIT (2) IN CONDITION 4 OR S OR DEFUELED POSITION NUMBER OF INDIVIOUALS REQUIRED TO FILL POSITION CON 0! TION 1, 2, or 3 CONDITION 4 or S SS la la SRO 1

la R0 2

1 NLO 2

2**

STA 1

None

~

WITH UNIT (2) IN CON 01110N 1, 2, OR 3 POSITION NUMBER OF IN0!VIOUALS REQUIRED TO FILL POSITION CONDITION 1, 2, or 3 CONDITION 4 or S SS 1*

1a SRO l*

la R0 2**

1 NLO 2**

1 STA 1*

None TABLE NOTATIONS

• Individual may fill the same positten on Unit 2.

• • 0ne of the two required individuals may fill the same position on Unit 2.

SS - Shift Superintendent or Shif t Supervisor with a Senior Operator license on Unit 1.

SR0 - Individual ytth a Senior Operator license on Unit 1.

RO - Individual with an Operator license on Unit 1.

NLO - Non-licensed operator properly qualified to support the unit to which assigned.

STA - Shift Technical Advisor Except for Shift Supervision (55), the shift crew composition may be one less than the minimum requirements of Table 6.2.2-1 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 /> ir. order to accommodate unexpected absence of on-duty shif t crew members provided immediate action is taken to restore the shif t crew compa-i sition to within the minimum requirements of Table 6.2.2-1.

This provision does not permit any shif t crew position to be ur.sanned upon shif t change due to an onioming shift crewman being late or absent.

During any absence of Shift Supervision (SS) from the control room while the unit is in OPERATIONAL CONDITION 1, 2, or 3, an indiviuv41 (other than the Shift Technical Advisor) with a valid Senior Operator license shall be designated to assume the control room command function.

During any absence of Shift Supervision from the control room while the unit is in OPERATIONAL CONDITION 4 or 5, an individual with a valid Senior Operator license or Operator license shall be designated to assume the control room command function.

LIMERICK - UNIT 1 6-5

%t ADMINISTRATIVE CONTROLS 6.2.3 INDEPENDENT SAFETY ENGINEERING GROUP (ISEG)

FUNCTION 6.2.3.1 The ISEG shall function to examine unit operating charac'. eristics, NRC issuances, industry advisories Licensee Event Reports, and other sources of unit design and operat' y experience information, including units of sial-lar design, which may ino..; ate areas for improving unit safety.

The ISEG shall make detailed recommendations for revised procedures, equipmerit modifications, maintenance activities, operations activities, or 'ther means of improving unit safety.

Such recommendations shall be submitted tnrough the General Manager-Nuclear Quality Assurance to the Senior Vice President-Nuclear.

COMPOSITION 6.2.3.2 The Limerick ISEG shall be composed of at least three, dedicated, full-time engineers, including the ISEG Superv!sor, located onsite. Each shall have a bachelor's degree in engineering or related science and at least two years i

professional level experience in his or her field.

The Limerick ISEG Supervisor shall have at least six years of experience in the nuclear field.

The orporato ISEG shall be composed of two dedicated full time enginests each with JacMi m degree in engineering or related science and at least 2 years profes> 1a1 el experience in his or her field, at least 1 year of which experience shall N

.n the nuclear field.

The LGS ISEG reports to the Independent Safety Engineering Manager.

RESPONSIBILITIES 6.2.3.3 The ISEG shall be responsible for maintaining surveillance of unit activities to provide independent verification

• that these activities cre per-formed correctly and that human errors are reduced as much as practical.

RECORDS 6.2.3.4 Records of activities performed by the ISEG shall be prepared, main-tained, and forwarded each calendar month to the Independent Safety Engineering Manager.

6 2.4 SHIFT TECHNICAL ADVISOR 6.2.4.1 The Shift Technical Advisor shall prnvide advisory technical support to Shift Supervision in the areas of thermal hydraulics, reactor engineering, and plant analysis with regard to safe operation of the unit.

The Shift Technical Advisor shall have a bachelor's degree or equivalent in a scientific or engineer-ing discipline arid shall have received specific training in the response and anal-ysis of the unit for transiants and accidents, and in unit design and layout, includi g the cap;bilities of instrumentation and controls in the control room.

n t

6.3 UNIT STAFF QUALIFICATIONS 6.3.1 Each member of the unit staff shall meet or exceed the minimum qualifica-tions of ANSI /ANS 3.1-1978 for comparable positions, except for the Senior Health Physicist who shall meet or exceed the qualifications of Regulatory Guide 1.8, September 1975 The licensed Operators and Senior Operators shall also meet or exceed the minimum qualifications of the supplemental requirements specit ed in Sections A and C of Enclosure 1 of the March 28, 1980 NRC letter to all 1.censees.

i

• Not responsible for sign-off function.

l 1.IMERICK - UNIT 1 6-6 Arandment No. 10

i ', t ADMINISTRATIVE CONTROLS 6.4 TRAINING l

6.4.1 A retraining and replacement training program for the unit staff shall be maintained under the direction of the site Training organization and shall neet j

or exceed the requirements of ANSI /ANS 3.1-1978 and Appendix A of 10 CFR Part 55 and the supplemental requirements specified in Sections A and C of Enclosure 1 of the March. 28, 1980 NRC letter to all licensees, and shall include familiariza-i tion with relevant industry operational experience.

l 6.5 REVIEW AND AUDIT l

i 6.5.1 PLANT OPERATIONS REVIEW COMMITTEE (PORC)

FUNCTION 6.5.1.1 The PORC shall function to advise tra Plant Manager on all matters l

related to nuclear safety.

COMPOSITION 6.5.1.2 The PORC shall be composed of the:

f Chairman:

Superintendent-Operations l

Member:

Superintendent-Technical l

Member:

Superintendent-Maintenance / Instrumentation and Controls Member:

Superintendent-Plant Services Member:

Assistant Superintendent-Operations Member:

Regulatory Engineer Member:

Technical Engineer Member:

Shift Superintendent Member:

Maintenance Engineer l

l ALTERNATES l

6. 5.1. 3 All alternate members shall be appointed in writing by the PORC Chairman to serve on a temporary basis; however, no more than two alternates i

shall participate as voting members in PORC activities at any one time.

MEETING FREQUENCY l

l 6.5.1.4 The PORC shall meet at least once per calendar month and as convened by the PORC Chairman or his designated alternate.

i r

QUORUM 6.5.1.5 The quorum of the PORC necessary for the performance of the PORC responsibility and authority provisions of these Technical Specifications shall consist of the Chairman or his designated alternate and four members including alternates, e

I 1.IMERICK - UNIT 1 67 Amendment No. 10 t

'. t ADMINISTRATIVE CONTROLS RESPONSIBILITIES 6.5.1.6 The PORC shall be responsible for:

a.

Review of (1) all procedures required by Specification 6.8 and changes thereto, (2) all programs required by Specification 6.8 and changes thereto, and (3) any other procedures or changes thereto as determined by the Plant Manager to affect nuclear safety; l

b.

Review of all proposed tests and experiments that affect nuclear safety; c.

Review of all proposed chan*as to Appendix A Technical Specifications; d.

Review of all proposed changes or modtfications to unit systems or equipment that affect nuclear safety; e.

Review of the safety evaluations for procedures and changes thereco completed under the provisions of 10 CFR 50.59.

f.

Investigation of all violations of the Technical Specifications, including the preparation and forwarding of reports covering evalua-tion and recommendations to prevent recurrence, to the Vice President, Limerick Generating Station, Plant Manager, and to the Nuclear Review Board; g.

Review of all REPORTABLE EVENTS; h.

Review of unit cperations to detect potential hazards to nuclear safety; i.

Performance of special reviews, investigations, or analyses and reports thereon as requestcd by the Vice President, Limerick Generating Station, Plant Manager or the Chairman of the Nuclear Review Board; j.

Review of the Security Plan and implementing procedures and submittal of recommended changes to the Nuclear Review Board; and k.

Review of the Emergency Plan and implementing procedures and submittal of the recommended changes to the Nuclear Review Board.

1.

Review of every unplanned onsite release of radioactive material to the environs including the preparation and forwarding of reports cover-ing evaluation, recommendations and disposition of the corrective action to prevent recurrence to the Vice President, Limerick Generating Station, Plant Manager, and to the Nuclear Review Board.

m.

Review of changes to the PROCESS CO.1 TROL PROGRAM, OFFSITE DOSE CALCULATION MANUAL, and radwaste treatment systems.

6. 5.1. 7 The PORC shall:

a.

Recommend in writing to the Plant Manager apprtval or disapproval of l

items considered under Specification 6.5.1.6a. through d. prior to their implementation.

b.

Render determinations in writing with regard to whether or not each item considered under Specification 6.5.1.6a. through f. constitutes an unreviewed safety question.

i l

LIMERICK - UNIT 1 6-8 Amendmen t No. 10 gn,.-

y yw.----, - - - -

gn

- - - - -., - - - - :_ - - -~

-..e,-.

", t ADMINISTRATIVE CONTROLS RESPONSIBILITIES (Continued) 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, Limerick Generatir.g Station and the Nuclear Review Board of disagree-ment between the PORC and the Plant Manager; however, the Plant Mana-ger shall have responsibility for resolution of such disagreements pursuant to Specification 6.1.1.

RECORDS 6.5.1.8 The PORC shall naintain written minutes of each PORC meeting that, at a minimum, document t'1e results of all PORC activities performed under the responsibility provisions of these Technical Specifications.

Copies shall be provided to the Vice President, Limerick Generating Station, Plant Manager, and the Nuclear Review Board.

6.5.2 NUCLEAR REVIEW BOARD (NRB)

FUNCTION 6.5.2.1 The NRB shall function to provide independent review and audit of designated activities in the areas of:

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, and h.

Quality assurance practices.

The NRB shall report to and advise the Senior Vice President - Nuclear and the Office of the Chief Executive on those areas of responsibility in Specifica-tions 6.5.2.7 and 6.5.2.8.

COMPOSITION 6.5.2.2 The Chairman, members, and alternates of the NRB shall be appointed in writing by the Senior Vice President - Nuclear, and shall have an academic l

degree in an engineering or physical science field; and in addition, shall have a minimum of 5 years technical experience, of which a minimum of 3 years shall be in one or more areas given in Specification 6.5.2.1, The NRB shall be com-posed of no less than eight and nc more than 12 members.

The members and alternates of the NRB will be competent in the area of Quality Assurance practice and cognizant of the Quality Assurance requirements of 10 CFR Part 50, Appendix 8.

Additionally, they will be cognizant of the corporate Quality Assurance Program and will have the corporate Quality Assurance organization available to them.

LIMERICK - UNIT 1 6-9 denc ent No. 10

t ADMINISTRATIVE CONTROLS ALTERNATES 6.5.2.3 All alternates shall be appointed in writing by the NR8 Chairman to serve on a continuing basis.

They shall receive correspondence sent to NRB members with regard to NRB activities and shall be invited to attend all NR8 meetings.

Alternates shall vote only in the absence of those members for whom they are the alternate.

CONSULTANTS 6.5.2.4 Consultants shall be utilized as determined by the NRB Chairman to provide expert advice to the NRB.

MEETING FREQUENCY 6.5.2.5 The NRB shall meet at least once per calend.tr quarter during the initial r

year of unit operation following fuel loading and at least once per 6 months thereafter, i

QUORUM 6.5.2.6 The quorum of the NRB necessary for the performance of the NRB review and audit functions of these Technical Specifications shall consist of the Chairman or a designated alternate and at least four but not less than one half of the voting NRB members.

No more than a minority of the quorum shall have line responsibility for operation of the facility.

REVIEW 6.5.2.7 The NRB shall review:

a.

The safety evaluations for (1) changes to procedures, equipment, facilities or systems; and (2) tests or experiments completed under the provision of 10 CFR 50.59 to verify that such actions did not constitute an unreviewed safety question; b.

Proposed changes to procedures, equipment, or systems which involve an unreviewed safety question as defined in 10 CFR 50.59; c.

Proposed tests or experiments which involve an unreviewed safety question as defined in 10 CFR 50.59; d.

Proposed ct.anges to Technical Specifications or this Operating License; e.

Violations of codes, regulations, orders, Technical Specifications, license requirements, or of internal procedures o* instructions having nuclear safety significance; f.

Significant operating abnormalities or deviations from normal and expected performance of unit equipment that affect nuclear safety; i

g.

All REPORTABLE EVENTS; UNIT 1 6-10 I

LIMER:CN

t ADMINISTRATIVE CONTROLS REVIEW (Continued) h.

All recognized indications of an unanticipated deficiency in some aspect of design or operation of structures, systems, or components that could affect nuclear safety; and i.

Reports and meeting minutes of the PORC.

r AUDITS 6.5.2.8 Audits of unit activities shall be performed under the cognizance of the NRB.

These audits shall encompass:

a.

The conformance of unit operation to provisions contained within the Technical Specifications and applicable license conditions at least once per 12 months; b.

The performance, training and qualifications of the entire unit staff at least once per 12 months; c.

The results of actions taken to correct deficiencies occurring in l

unit equipment, structures, systems, or method of operation that affect nuclear safety, at least once per 6 months; d.

The performance of activities required by the Operat.onal Quality Assurance Program to eset the criteria of Appendix B, 10 CFR Part 50, at least once per 24 months; e.

The Emergency Plan and implementing procedures at least once per 12 months, f.

The Security Plan and implementing procedures at least once per 12 months.

g.

Any other area of unit operation considered appropriate by the NRB l

or the Senior Vice President - Nuclear.

l h.

The Fire Protection Program ana implementing procedures at least once per 24 months.

l 1.

An independent fire protection and loss prevention inspection and audit shall be performed at least once per 12 conths utilizing either qualified offsite licensee personnel or an outside fire protection firm.

j.

An inspection and audit of the fire protection and loss prevention program shall be performed by an outside qualified fire consultant at intervals no greater than 36 months, i

LIMERICK - UNIT 1 6-11 A. mend ent No.10 l,

-wr-w

,m w

m _. _,

_7

_,___,,.or

t ADMINISTRATIVE CONTROLS AUDITS (Continued) k.

The radiological environmental monitoring program and the results thereof at least once per 12 months.

1.

The OFFSITE 00SE CALCULATION MANUAL and implementing procedures at least once per 24 mcnths, The PROCESS CONTROL PROGRAM and implementing procedures at least m.

once per 24 months, n.

The performance of activities required by the Quality Assurance Program to meet the criteria of Regulatory Guide 4.15, December,1977, at least once per 12 months.

RECORDS 6.5.2.9 Records of NRB activities shall be preparel, approved, and distributed as indicated below:

a.

Minutes of each NRB meeting shall be prepared, approved, and fo marded to the Senior Vice President - Nuclear within 14 days following l

each meeting, b.

Reports of reviews encompassed by Specification 6.5.2.7 shall be prepared, approved, and fomarded to the Senior Vice President -

Nuclear within 14 days following completion of the review.

c.

Audit reports encompassed by Specification 6.5.2.8 shall be forwarded to the Senior Vice President - Nuclear and to the management positions l

responsible for the areas audited within 30 days af ter completion of the audit by the auditing organization.

l 6.6 REPORTABLE EVENT ACTION 6.6.1 The following actions shall be taken for REPORTABLE EVENTS:

a.

The Commission shall be notified and a report submitted pursuant tu the requirements of Section 50.73 to 10 CFR Part 50, and b.

Each REPORTABLE EVENT shall be re.iewed by the PORC and submitted to the NRB, Plant Manager and the Vice President, Limerick Generating Station.

6.7 SAFETY LIMIT VIOLATION 6.7.1 The following actions shall be taken in the event a Safety Limit is violated:

a.

The NRC Operations Center shall be notified by telephone as soon as possible and in all cases within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.

The Vic9 President, Limerick Generating Station, Plant Manager, and the NRB shall be notified within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

LIMtRICK - UNIT 1 6-12 Amendment No. 10

4 o

ADMINISTRATIVE CONTROLS SAFETY LIMIT V10LATION (Continued) b.

A Safety Limit Violation Report shall be prepared. The report shall be reviewed by the NRB. This report shall describe (1) applicable circumstances preceding the violation, (2) effects of the violation upon unit components, systems, or structures, and (3) corrective action taken to prevent recurrence, c.

The Safety Limit Violation Report shall be submitted to the Commission, the NRB, Plant Manager, and the Vice President, Limerick Generating Station, within 14 days of the violation.

d.

Critical operation of the unit shall not be resumed until authorized by the Commission.

6.8 PROCEDURES AND PROGRAMS 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, Revision 2, February 1978.

b.

The applicable procedures required to implement the requirements of NUREG-0737 and Supplement 1 to NUREG-0737.

c.

Refueling operations.

d.

Surveillance and test activities of safety-related equipment.

e.

Security Plan implementation.

f.

Emergency Plan implementation, g.

Fire Protection Program implementation, h.

PROCESS CONTROL PROGRAM implementation.

i.

OFFSITE 00SE CALCULATION MANUAL implementation.

j.

Quality Assurance Program for effluent and environmental monitoring, using the guidance of Regulatory Guide 4.15, February 1979.

6.8.2 Each procedure of Specification 6.8.1, and changes thereto, shall be reviewed in accordance with Specification 6.5.1.6 and shall be approved by the Plant Manager or designee prior to implementation and reviewed periodically as l

set forth in administrative procedures.

6.8.3 Temporary changes to procedures of Specification 6.8.1 may be made provided:

a.

The intent of the original procedure is not altered; b.

The change is approved by twc members of the unit management staff, at least one of whom holds a Senior Operator license on the unit affected; and c.

The change is documented, reviewed by the PORC, and approved by the Plant Manager or designee within 14 days of implementation.

l LIHERICK - UNIT 1 6-13 A endment No. 10 h

• .t ADMINISTRATIVE CONTROLS PROCEDURES AND PROGRAMS (Continued) 6.8.4 The following programs shall be established, implemented, and maintained:

a.

Primary Coolant Sources Outside Containment A program to reduce leakage from those portions of systems outside containment that could contain highly radioactive fluids during a serious transient or accident to as low as practical levels.

The systems include the core spray, high pressure coolant injection, reactor core isolation cooling, residual heat removal, post-accident sampling system, safeguard piping fill system, control rod drive scram discharge system, and containment air monitor systems.

The program shall include the following:

1.

Preventive maintenance and periodic visual inspection requirements, and 2.

Integrated leak test requirements for each system at refueling cycle intervals or less.

b.

In-Plant Radiation Monitorino A program which will ensure the capability to accurately determine the airborne lodine concentration in vital areas under accident conditions.

This program shall include the following:

1.

Training of personnel, 2.

Procedures for monitoring, and 3.

Provisions for maintenance of sampling and analysis equipment, c.

Post-accident Samplino*

A program which will ensure the capability to obtain and analyze reactor coolant, radioactive iodines and particulates in plant gaseous efflu-ents, and contsinment atmosphere samples under accident conditions.

The program shall include the following:

1.

Training of personnel, 2.

Procedures for sampling and analysis, and 3.

Provisions for maintenance of sampling and analysis equipment.

• Not required until prior to exceeding 5% of RATED THERMAL POWER.

LIMERICK - UNIT 1 6-14 g