Text

Amends 96 & 60 to Licenses NPF-39 & NPF-85,respectively, Make Changes Affecting Administrative Controls Section of TSs
	ML20086Q172
Person / Time
Site:	Limerick ; (NPF-039, NPF-085)
Issue date:	07/18/1995
From:	Stolz J; Office of Nuclear Reactor Regulation
To:	; Philadelphia Electric Co
Shared Package
ML20086Q175	List: ML20086Q172; ML20086Q183;
References
	NPF-39-A-096, NPF-85-A-060 NUDOCS 9507270324
	Download: ML20086Q172 (34)
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g UNITED STATES 2

S NUCLEAR REGULATORY COMMISSION E

f WASHINGTON, D.C. 20tWW0001

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PHILADELPHIA ELECTRIC COMPANY DOCKET N0. 50-351 LIMERICK GENERATING STATION. UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 96 License No. NPF-39 l

1.

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

A.

The application for amendment by Philadelphia Electric Company (the I

licensee) dated November 21, 1994, as supplemented by letters dated April 6, and July 3, 1995, 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.

9507270324 950718 PDR ADOCK 05000352 P

PDR

2.

Accordingly, the license is amended by changes to the Technical 3

Specifications as indicated in the attachment to this license amendment,

-and paragraph 2.C.(2) of Facility Operating License No. NPF-39 is hereby amended to read as follows:

Technical Specifications The Technical Specifications contained in Appendix A and the Environmental.

i Protection Plan contained in Appendix B, as revised through Amendment No.

96, are hereby incorporated into this license.

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

3.

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

FOR THE NUCLEAR REGULATORY COMMISSION i

N b

M John F. Stolz, Director

/

Project Directorate I-2 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical Specifications Date of Issuance:

July 18, 1995 i

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i ATTACHMENT TO LICENSE AMENDMENT NO.96 FACILITY OPERATING LICENSE NO. NPF-39 DOCKET 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.

Remove Insert xxvi xxvi xxvii xxvii 6-1 6-1 6-2 6-2 6-3 6-3 6-5 6-5 6-6 6-6 6-7 6-7 6-9 6-9 6-10 6-10 6-11 6-11 6-12 6-12 l

6-12a 6-12a 6-13 6-13 t

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P INDEX ADMINISTRATIVE CONTROLS SECTION E&E 6.1 RESPONSIBILITY...................................................-

6-1 6.2 ORGANIZATION.....................................................-

6-1 6.2.1 0FFSITE AND ONSITE ORGANIZATION.....................

6-1 Figure 6.2.1-1 Deleted........................... 3 5

6.2.2 UNIT STAFF......................................................

6-2 Figure 6.2.2-1 Deleted...........................

6-4 Table 6.2.2-1 Minimum Shift Crew Composition.......................

6,

6.2.3 DELETED; Refer to note on page..................................

6-6 6.2.4 SHIFT TECHNICAL ADVIS0R.........................................

6-6 6.3 UNIT STAFF 0UALIFICATIONS........................................

6-6 6.4 T RA I N I N G.........................................................

6-7 6.5 REVIEW AND AUDIT 6.5.1 Plant Operations Review Committee (PORC)

Function..................................................

6-7 Composition...............................................

6-7 Alternates................................................

6-7 Meeting Frequency.........................................

6-7 Quorum....................................................

6-7 Responsibilities..........................................

6-8 Records...................................................

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- LIMERICK - UNIT 1 xxvi Amendment No. 33,35,96 l

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s INDEX

&QgjNISTRAT'VE' CONTROLS i

I SffIl0E E8EE 6.5.2 NUCLEAR REVIEW BOARD (NRB)

Function..............................................

6-9 Composition...........................................

6-9 i

Alternates............................................

6-10' 1

Consultants...........................................

6-10 Meeting Frequency.....................................

6-10 Quorum................................................

6-10 t

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' DELETED; Refer to note on page........................

'6-10 Records...............................................

6-12 6.5.3 PROGRAM / PROCEDURE REVIEW AND APPR0 VAL................. 12 6.6 REPORTABLE EVENT ACTI0N......................................

6-12a 6.7 SAFETY LIMIT VIOLATION.......................................

6-12a 6.8 PROCEDURES AND PR0 GRAMS......................................

6-13 6.9 REPORTING REQUIREMENTS 6.9.1 ROUTINE REP 0RTS.......................................

6-15 Startup Report........................................

.6-15 Annual Reports........................................

6-15 Monthly Operating Reports.............................

6-16 t

Annual Radiological Environmental Operating Report....

6-16 Semiannual Radioactive Effluent Release Report........

'6-17 Lv CORE OPERATING LIMITS. REPORTS.........................

6-18a i

6.9.2 SPECIAL REP 0RTS.......................................

6-18a i

6.10 RECORD RETENTION............................................

6-19 6.11 RADIATION PROTECTION PR0 GRAM................................

6-20.

I 6.12 HIGH RADIATION AREA.........................................

6-20

'i LIMERICK. UNIT 1 xxvii Amendment No. 37, 47 96 i

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!6.0 ADMINISTRATIVE CONTROLS s

1 6.I RESPONSIBILITY-1 1

I 6.1.1.- The. Plant Manager shall be responsible for overall unit ' operation 'and shallidelegate in writing the succession to this responsibility during his

. absence.

'6.1.2 The Shift Manager,. or during his absence from the control room, a l

designated individual shall be responsible for the control:rdom 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.

t 6.2 ORGANIZATION 6.2.I 0FFSITE AND ONSITE ORGANIZATIDM l

Onsite and offsite organizations shall be established for unit operation and j

corporate management, respectively. The onsite and offsite organizations shall include the positions for activities affecting the safety of the nuclear 1

power plant.

a.

Lines of authority, responsibility, and-communication shall be established and defined for the highest management levels through.

intermediate levels to and including all operating organizational i

positions.

These relationships shall be documented and updated, 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 the Limerick Quality Assurance Program.

b.

The Plant Manager shall be. responsible for overall unit. safe-operation and shall have control'over those onsite activities i

necessary for safe operation and maintenance of the plant..

i c.

The Vice President, Limerick Generating Station shall have corporate responsibility for overall plant nuclear safety and shall take any measures needed to ensure acceptable performance of the. staff in operating, maintaining, and providing technical support to the plant to ensure nuclear safety.

j d.

The individuals who train the operating. staff and those who carry l

out health physics and quality assurance : functions may report to the appropriate onsite manager; however, they shall have sufficient r

organizational freedom to ensure their independence from operating i

pressures.

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LIMERICK - UNIT 1 6-1 Amendment No. 10, 35, 96

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I ADMINISTRATIVE CONTROLS i

6.2.2 UNIT STAFF a.

Each on duty shift shall be composed of at least the minimum shift 1

crew composition shown in Table 6.2.2-1; b.

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

In addition, while the unit is in 0FERATIONAL CONDITION 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 0)erator or licensed Senior Operator Limited to Fuel Handling w1o has no other concurrent responsibilities during this operation; e.

A site fire brigade of at least five members shall be maintained on site at all times *. The fire brigade shall not include the Shift Manager, the Shift 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; f.

Administrative procedures shall be developed 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 to permitted to work more than 16 hours1.851852e-4 days 0.00444 hours 2.645503e-5 weeks 6.088e-6 months straight, excluding shift turnover time.

2.

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

3.

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

4.

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

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 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months , in order to accommodate unexpected absence, provided immediate action is taken to fill the required positions.

LIMERICK - UNIT 1 6-2 Amendment No. 10,35,96

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ADMINISTRATIVE CONTROLS'

'l UNIT STAFF (Continued).

'a Any deviation from the above guidelines shall be cuthorized by the-Plant Manager or personnel designated.in administrative 1

procedures or higher levels of management,' in accordance with t

established procedures and with documentation of the basis for.

l granting the deviation. Controls shall be included in the procedures such that individual overtime shall-be reviewed monthly by the Plant Manager, or the appropriate designated-personnel to assure that excessive hours have not been assigned.

Routine deviation from the above guidelines is not authorized-

'and i

g.

The Sr. Manager - Operations or an Operations Manager shall hold a.

j

' Senior Reactor Operator License.

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LIMERICK - UNIT 1 6-3 Amendment No. 10,35,63.80,96

TABLc 6.2.2-1 i.

MINIMUM SHIFT CREW COMPOSITION TWO UNITS WITH A COMMON CONTROL ROOM WITH UNIT 2 IN CONDITION 4 OR 5 OR DEFUELED POSITION NUMBER OF INDIVIDUALS REQUIRED TO FILL POSITION CONDITION 1, 2, or 3 CONDITION 4 OR 5 SM 1*

1*

i SR0 2*

2*

R0 2

1 NLO 2

2**

L STA 1***

None i

I WITH UNIT 2 IN CONDITION 1, 2, OR 3 POSITION NUMBER OF INDIVIDUALS REQUIRED TO FILL POSITION CONDITION 1, 2, or 3 CONDITION 4 or 5 l

SM 1*

1*

SRO 2*

2*

R0 2**

1 NLO 2**

1 l

STA 1*,***

None BHLE NOTATIONS

Individual (s) may fill the same position on Unit 2.

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- One of the two required individuals may fill the same position on Unit 2.

- - The STA position may be filled by an on-shift Sd or SR0 provided the individual meets the 1985 NRC Policy Statement on Engineering Expertise on Shift.

SM - Shift Manager with a Senior Operator license on Unit 1.

SRO - Individual with a Senior Operator license on Unit 1.

R0 - 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 the Shift Manager (SM), the shift crew composition may be one less l

than the minimum requirements of Table 6.2.2-1 for a period of time not' to exceed 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months in order to accommodate unexpected absence of on-duty shift crew members provided immediate action is taken to restore the shift crew compo-sition to within the minimum requirements of Table 6.2.2-1.

This provision does not permit any shift crew position to be unmanned upon shift change due to an upcoming shift crewman being late or absent.

is in OPERATIONAL CONDITION 1, 2, or 3, an individual with a valid Senior Operato During any absence of the Shift Manager (SM) from the control room while the unit shall be designated to assume the control room command function. During any absence of the Shift Manager (SM) from the control room while the unit is in OPERATIONAL CONDITION /

or 5, an individual with a valid Senior Operator license or Operator license l

shall be designated to assume the control room command function.

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l LIMERICK - UNIT 1 6-5 Amendment No. 28,33,64,96

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' iL* ADMIN 1STRATIVE' CONTROLS

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+,LLI --; DELETED.. The information, from this. section is located in the UFSAR,-

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i LIMERICK - UNIT 1 6-6 Amendment No. 10,35,55,6(,96.

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ADMIN.ISTRATIVECONTROLS

~ 6.4 TRAINING 6.4.1 Training programs for the unit staff shall be maintained under the direction'of the site training organization. The retraining and replacement training programs _ for all affected positions except licensed operators shall meet

'cr exceed the standards of ANSI /ANS 3.1-1978. The retraining and replacement i

training programs for licensed operators shall comply with the requirements of 10

.CFR 55, and shall include familiarization with relevant industry operational experience.

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6.5 REVIEW AND AUDIT 6.5.1' PLANT ' OPERATIONS REVIEW COPMITTEE (PORC)

[

t FUNCTION 6.5.1.1 The PROC shall function to advise the Plant Manager on all matters j

related to nuclear safety.

l COMPOSITION i

6.5.1.2 The Plant Operations Review Committee is composed of nine regular members'from the Limerick Generating Station staff.

Members shall collectively have experience in the following areas:

l Plant Operations Engineering Maintenance Instrumentation and Controls J

Planning i

Radiation Safety Chemistry Experience Assessment 1

Members shall meet the requirements of ANSI /ANS 3.1-1978, Section 4.7,- for the applicable required experience and be appointed in writing by the Plant Manager.

4 The Chairman and alternate Chairman of the PORC shall be drawn from the PORC members and appointed in writing by the Plant Manager..

ALTERNATES 1

6.5.1.3 All alternate members shall be appointed in writing by the PORC Chairman l

to serve on a temporary basis; however, no more than two alternates shall participate as voting members'in PORC activities at any one time.

MEETING FRE0VENCY l

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

000 RUM 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 i

consist of the Chairman or his designated alternate and four members including alternates.

i LIMERICK -' UNIT 1 6-7 Amendment No. 10,33,55,96

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JADNIKISTRAIIVECONTROLS l

RESPONSIBILITIES

'(Continued).

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EProvide written notification ~within'24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months to the Vice President,-

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Limerick Generating Station and the Nuclear Review Board of disagree-j ment between the PORC and the Plant Manager; however, the Plant Man-i ager shall-have responsibility for resolution of such disagreements 1

E pursuant to Specification 6.1.1.

l RECORDS

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6. 5.1.8 '

The PORC shall maintain written minutes of each PORC meeting that, j

at a minimum, document the results of all PORC activities performed under the l

-responsibility provisions of these Technical Specifications. Copies shall be provided to the Vice President, Limerick Generating Station, Plant Manager, and the Nuclear Review Board.

j 6.5.2 NUCLEAR REVIEW BOARD (NRB)

FUNCTION l

i 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, j

b.

Nuclear engineering, c.

Chemistry and radiochemistry,

'l d.

Metallurgy, e.

Instrumentation and control,

' f.

Radiological safety, g..

Mechanical and electrical engineering, and h.

Quality assurance practices.

i The NRB shall report to and advise the Senior Vice President and Chief Nuclear Officer on those areas of responsibility pertaining to NRB Review and' Audits.

COMPOSITION 6.5.2.2

. The Chairman, members, and alternates of the NRB shall be appointed 1

in writing by the Senior Vice President and Chief Nuclear Officer, and shall have an academic l.

drgree-in an engineering or physical science field; and in addition, shall have l

.a ninimum 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 l

composed of no less than eight and no more than 12 members..

J The members ~ and ' alternates of the NRB will be competent in the area of Quality i

. Assurance practice and cognizant of the Quality Assurance requirements of 10 CFR l

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.

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i LIMERICK - UNIT 1 6-9.

Amendment-No. 10,35,96 i

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3 ADMINISTRATIVE CONTROLS ALTERNATES 6.5.2.3 All alternates shall be appointed in writing by the NR8 Chairman to l

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s:rve on a continuing basis.- They shall receive correspondence sent to NRB members with regard to NRB activities and shall be invited to attend all NRB.

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meetings. -Alternates shall vote only in the absence of those members for whos-they are the alternate.

CONSULTANTS 6.5.2.4 Consultants shall be utilized as determined by the NRB Chairman to l

provide expert advice to the NRB.

MEETING FREQUENCY q

6.5.2.5 The NRB shall meet at least once per calendar quarter during the initial l'

year of unit operation following fuel loading and at least once per 6 months-thereafter.

OUORUM q

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 i

have line responsibility for operation of-the' facility.

l REVIEW j

6.5.2.7 - DELETED. The information from this section is located in the UFSAR.

AUDITS 6.5.2.8 - DELETED. The information from this section is located in the UFSAR.

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1 LIMERICK - UNIT 1 6-10 Amendment No. 96 2

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LIMERICK - UNIT 1

'6-11 Amendment No. 70,35,96 j

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ADMINISTRATIVE CONTROLS RECORDS

!6.5.2.9 Records of NRB activities shall be prepared, approved, and distributed as

indicated below

a.

Minutes of each NRB meeting shall be prepared, approved, and forwarded to the Senior Vice President and Chief Nuclear Officer within 14 days following each l-h.

meeting..

b.

Reports of; Reviews shall be prepared, approved, and forwarded to the Senior Vice President and Chief Nuclear Officer within 14 days following completion of the review.

' c.

Audit reports shall be forwarded to the Corporate Officer (s) and management positions responsible for the areas audited within 30 days after conpletion of the audit by the auditing organization.

6.5.3 PROGRAM / PROCEDURE REVIEW AND APPROVAL All programs and procedures required by Specification 6.8 shall be reviewed and approved as described below.

6.5.3.1 Each new program, procedure, or change thereto shall be independently reviewed by a Station Qualified Reviewer (SQR) who is knowledgeable in the

~ functional area affected but is not the individual preparer. The SQR may be from the same organization as the preparer. The SQR shall render a determination in writing of whether or not cross-disciplinary review of a new program, procedure, or change thereto is necessary.

If necessary, such review shall be performed by appropriate personnel.

6.5.3.2 Each new program, procedure, or change thereto shall be reviewed by the Director or Manager designated by Administrative Procedures as the responsible L

Director or Manager for that program or procedure, and the review shall include a determination of whether or not a 10 CFR 50.59 safety evaluation is required.

If 1

I a 10 CFR 50.59 safety evaluation is not required, the new program, procedure..or change thereto shall be' approved by the. responsible Director or Manager or the Plant l

Manager prior to implementation.. Administrative Procedures shall be reviewed by PORC prior to approval. Administrative Procedures, Security Plan Implementing Procedures, and Emergency Plan Implementing Procedures shall be approved'by the Plant Manager or his designated alternate in accordance with Specification 6.1.1.

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LIMERICK - UNIT 1 6-12 Amendment No. 10,35,#7,96 l

__.-__---__.---__----___-----..-_--___a

ADMIN,ISTRATIVE CONTROLS 6.5.3.3 If the responsible Dir:ctor or Manager determines that a n:w progra:s, l

Eprocedure, or change thereto requires a 10 CFR 50.59 safety evaluation, the responsible Director or Manager shall render a determination in writing of whether or l

not the new program, procedure, or change thereto involves an unreviewed safety question (USQ), and shall forward'the new program, procedure, or change thereto

- with the associated safety evaluation to PORC for review.

If an USQ is involved.

NRC approval is required by 10 CFR 50.59 prior to implementation of the new program, procedure, or change.

[

6.5.3.4 Personnel recommended to be SQRs shall be approved and designated as such by the PORC Chairman. The responsible Director or Manager shall ensure that a l

sufficient complement of SQRs for their functional area is maintained in accordance with Administrative Procedures. The SQRs shall meet or exceed the qualifications described in Section 4.4 of ANSI /ANS 3.1-1978.

6.5.3.5 Temporary procedure changes shall be reviewed and approved in accordance with Specification 6.8.3.

6.5.3.6 Records documenting the activities performed under Specifications 6.5.3.1 through 6.5.3.5 shall be maintained in accordance with Specification 6.10.

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 to the requirements of Section 50.73 to 10 CFR Part 50, and b.

Each REPORTABLE EVENT shall be reviewed 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 I hour. The Vice President, Limerick Generating Station, Plant Manager, and the NRB shall be notified within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months , 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 the 14 days of the violation.

l LIMERICK - UNIT 1 6-12a Amendment No. 47,96

".iADMINISTRATIVECONTROLS-l SAFETY LINIT VIOLATION. (Centinued)

L

d. -

Critica1' operation of the unit shall not be resumed until authorized by the Commission.

6.8 PROCEDURES AND PROGRAMS l

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 f

1.33, Revision 2, February 1978.

j b.

.The applicable procedures required to implement the requirements of l

NUREG-0737 and Supplement 1.to NUREG-0737.~

c.

Refueling operations.

f 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 DOSE 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, and any other procedure or procedure change that the Plant Manager determines to affect nuclear

~

safety, shall be reviewed and approved in accordance with Specifications-6.5.1.6, 6.5.1.7 and/or 6.5.3, as appropriate, prior to implementation.

Each procedure of Specification 6.8.1 shall also be reviewed periodically as 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 two 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 an SQR in accordance with Specification 6.5.3.1, and approved by either the Plant Manager or his designated alternate in accordance with Specification 6.1.1, or the Director or Manager designated by Administrative Procedures as the responsible Director or Manager for that procedure within 14 days of implementation.

LIMERICK - UNIT 1 6-13 Amendment No. 10.47,96

f;3r aegy%, -

'-D UNITED STATES NUCLEAR REGULATORY COMMISSION N

f WASHINGTON, D.C. 20086 0001 0

94+...

4 PHILADELPHIA ELECTRIC COMPANY DOCKET NO, 50-351 LIMERICK GENERATING STATION. UNIT 2 L

AMENDMENT TO FACILITY OPERATING LICENC" Amendment No. 60 License No. NPF-85

[

1.

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

A.

The application for amendment by Philadelphia Electric Company (the licensee) dated November 21, 1994, as supplemented by letters dated April 6, and July 3, 1995, 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; t

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.

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. 2.

Accordingly, the license is amended by changes to the Technical

(

Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. NPF-85 is hereby amended to read as follows:

lechnical Soecifications The Technical Specifications contained in Appendix A and the Environmental Protection Plan contained in Appendix B, as revised through Amendment No.

I 60, are hereby incorporated into this license.

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

3.

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

FOR THE NUCLEAR REGULATORY COMMISSION ba~dJ. EA L-1 John F. Stolz, Director Project Directorate I-2 Division of Reactor Projects - I/II l

Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical Specifications Date of Issuance: July 18, 1995 i

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9 ATTACHMENT TO LICENSE AMENDMENT NO. 60 FACILITY OPERATING LICENSE NO. NPF-85 DOCKET NO. 50-353 Replace the following pages of the Appendix A Technical Specifications with the attached pages. The revised pages are 1dentified by Amendment number and contain vertical lines indicating the area of change.

82m2Yg Insert xxvi xxvi xxvii xxvii 6 6-1 6-2 6-2 6-3 6-3 6-5 6-5 6-6 6-6 6-7 6-7 6-9 6-9 6-10 6-10 6-11 6-11 6-12 6-12 6-12a 6-12a 6-13 6-13

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INDEX i

ADNINISTRATIVE CONTROLS l

SECTION E&E

=6.1 RESPONSIBILITY..~.....................................................

6-1 6.2 ORGANIZATION.........................................................

6-1 6.2.1'0FFSITE AND ONSITE ORGANIZATION.....................................

6-1 i

Figure 6.2.1-1 DELETED...............................

6-3 1

6.2.2 UNIT STAFF..........................................................

6-2 Figure 6.2.2-1 DELETED...............................

6-4 Table 6.2.2 Minimum Shift Crew Composition...........................

6-5 j

6.2.3 DELETED; Refer to note on page.....................................

6-6 l

6.2.4 SHIFT TECHNICAL ADVIS0R.............................................

6-6 6.3 UNIT STAFF QUALIFICATIONS............................................

6-5 6.4 TRAINING.............................................................

6-7

~

r 6.5 REVIEW AND AUDIT 6.5.1 Plant Operations Review Committee (PORC)

Function......................................................

6-7 i

Composition...................................................

6-7 Alternates....................................................

6-7 Meeting Frequency.............................................

6-7 Quarum........................................................

6-7 Responsibilities..............................................

6-8 Records.......................................................

6-9 l

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LIMERICK - UNIT 2 xxvi Amendment No. 2.60

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1 INDEX i

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ADMINISTRATIVE CONTROLS SECTION EAGE l

6.5.2 NUCLEAR REVIEW BOARD (NRB) y Function......................................................

6-9 Composition...................................................

6-9

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Alternates,...................................................

6-10 i

l Consultants...................................................

6-10 Meeting Frequency.............................................

6-10 Quorum........................................................

6-10 DELETED; Refer to note on page................................

6-10 l

Records.......................................................

6-12 6.5.3 PROGRAM / PROCEDURE REVIEW AND APPR0 VAL.........................

6-12 6.6 REPORTABLE EVENT ACTI0N..............................................

6-12a 6.7 SAFETY LIMIT VIOLATION...............................................

6-12a 6.8 PROCEDURES AND PR0 GRAMS..............................................

6-13 6.9 REPORTING RE0VIREMENTS 6.9.1 ROUTINE REP 0RTS...............................................

6-15 Startup Report................................................

6-15 An n u a l Re po rt s................................................

6-15 Monthly Operating Reports.....................................

6-16 Annual Radiological Environmental Operating Report............

6-16 Semiannual Radioactive Effluent Release Report................

6-17 CORE OPERATING LIMITS REP 0RTS.................................

6-18a 6.9.2 SPECIAL REP 0RTS...............................................

6-18a 6.10 RECORD RETENTION....................................................

6-19 6.11 RADIATION PROTECTION PR0 GRAM........................................

6-20 6.12 HIGH RADIATION AREA.................................................

6-20 LIMERICK - UNIT 2 xxvii Amendment No, 4, 60

l 6.0 ADMINISTRATIVE CONTROLS 6.1 RESPONSIBILIIY 6.1.1 The Plant Manager shall be responsible for overall unit operation and shall delegate in writing the succession to this responsibility during his absence.

6.1.2 The Shift Manager, or during his absence from the control room, a l

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 6.2.1 0FFSITE AND ONSITE ORGANIZATIONS Onsite and offsite organizations shall be established for unit operation and corporate management, respectively.

The onsite and offsite organizations shall include the positions for activities affecting the safety of the nuclear power plant, a.

Lines of authority, responsibility, and communication shall be established and defined for the highest management levels through intermediate levels to and including all operating organizational positions. These relationships shall be documented and updated, as appropriate, in the form of organizational 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 the Limerick Quality Assurance Program.

b.

The Plant Manager shall be responsible for overall unit safe operation and shall have control over those onsite activities necessary for safe operation and maintenance of the plant.

j c.

The Vice President, Limerick Generating Station shall have corporate responsibility for overall plant nuclear safety and shall take any measures needed to ensure acceptable performance of the staff in operating, maintaining, and providing technical support to the plant to ensure nuclear safety.

d.

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.

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LIMERICK - UNIT 2 6-1 Amendment No. 2, 60

1 ADMINISTRATIVE CONTROLS 6.2.2 UNIT STAFF a.

Each on duty shift shall be composed of at least the minimum shift 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 CONDITION 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 Operator or licensed Senior Operator Limited to-Fuel Handling who has no other concurrent responsibilities during this operation; e.

A site fire brigade of at least five members shall be maintained on site at all times *. The fire brigade shall not include the Shift Manager, the Shift Technical Advisor, nor the two other l

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; f.

Administrative procedures shall be developed 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 guidolines shall be followed:

1.

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

2.

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

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 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months , in order to accommodate unexpected absence, provided immediate action is taken to fill the required positions.

LIMERICK - UNIT 2 6-2 Amendment No. 2, 60

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'i ADMINISTRATIVE CONTROLS 6.2.2 UNIT STAFF (Continued)

'3.

A break of at least 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months 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 shall be authorized by the Plant Manager or personnel designated in administrative procedures or higher levels of management, in accordance with established pro-cedures 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 appropriate designated personnel to assure that excessive hours have not been assigned. Routine deviation from the above guidelines is not authorized; and g.

The Sr. Manager - Operations or an Operations Manager shall hold a Senior Reactor Operator License.

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Amendment No. 2,28,41,60 LIMERICK - UNIT 2 6-3

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.O-TABLE 6.2.2-1 MINIMUM SHIFT CREW COMPOSITION TWO UNITS WITH A COMMON CONTROL ROOM WITH UNIT I IN CONDITION 4 OR 5 OR DEFUELED POSITION NUMBER OF INDIVIDUALS REQUIRED TO FILL POSITION CONDITION 1, 2, or 3 CONDITION 4 OR 5 SM 1*

1*

r SR0 2*

2*

R0 2

1 NLO 2

2**

STA 1***

None WITH UNIT 1 IN CONDITION 1, 2, OR 3 POSITION NUMBER OF INDIVIDUALS REQUIRED TO FILL POSITION f

CONDITION 1, 2, or 3 CONDITION 4 or 5 SM 1*

1*

SR0 2*

2*

R0 2**

1 NLO 2**

1 STA 1*,***

None TABLE NOTATIONS

Individual (s) may fill the same position on Unit 1.

l

- One of the two required individuals may fill the same position on Unit 1.

- - The STA position may be filled by an on-shift SM or SR0 provided the individual y

meets the 1985 NRC Policy Statement on Engineering Expertise on Shift.

l SM - Shift Manager with a Senior Operator license on Unit 2.

SRO - Individual with a Senior Operator license on Unit 2.

i RO - Individual with an Operator license on Unit 2.

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

STA - Shift Technical Advisor Except for the Shift Manager (SM), the shift crew composition may be one less l

than the minimum requirements of Table 6.2.2-1 for a period of time not to exceed 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months in order to accommodate unexpected absence of on-duty shift crew members provided immediate action is taken to restore the shift crew compo-sition to within the minimum requirements of Table 6.2.2-1.

This provision d::es not permit any shift crew position to be unmanned upon shift change due to an upcoming shift crewman being late or absent.

During any absence of the Shift Manager (SM) from the control room while the unit l

1s in OPERATIONAL CONDITION 1, 2, or 3, an individual with a valid Senior Operator license shall be designated to assume the control room command function.

During any absence of the Shift Manager (SM) from the control room while the unit is l

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 2 6-5 Amendment No. 29,60 o

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.: ADMINISTRATIVE CONTROLS 6.2.3' DELETED. The.information from this section is located in the UFSAR.

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LIMERICK - UNIT 2 6-6 Amendment No. 7,20,29,60 I

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P ADMINISTRATIVE CONTROLS

~6.4 TRAINING 6.4.1 Training programs for the unit staff shall be maintained under the direction of the site training organization. The retraining and replacement-training programs for all r.ffected positions except licensed operators shall meet or exceed the standards o' ANSI /ANS 3.1-1978. The retraining and replacement training programs for li'.ensed operators shall comply with the requirements of 10 CFR 55, and shall include familiarization with relevant industry operational experience.

l 6.5 REVIEW AND AUDIT

-6.5.1 PLANT OPERATIONS REVIEW COMMITTEE (PORC) i FUNCTION 6.5.1.1 The PORC shall function to advise the Plant Manager on all matters i

related to nuclear safety.

COMPOSITION l

t 6.5.1.2 The Plant Operations Review Committee is composed of nine regular members from the Limerick Generating Station staff. Members shall collectively i

have experience in the following areas:

Plant Operations Engineering Maintenance Instrumentation and Controls Planning Radiation Safety l

Chemistry i

Experience Assessment Members shall meet the requirements of ANSI /ANS 3.1-1978, Section 4.7, for the applicable required experience and be appointed in writing by the Plant Manager.

The' Chairman and alternate Chairman of the PORC shall be drawn from the PORC members and appointed in writing by the Plant Manager.

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

MEETING FRE0VENCY 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.

000 RUM i

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.

LIMERICK - UNIT 2 6-7 Amendment No. 20,60 5

r ADMINISTRATIVE CONTROLS

\\

RESPONSIBILITIES (Continued) c.

Provide written notification within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months to the Vice President, Limerick Generating Station and the Nuclear Review Board of disagree-ment between the PORC and the Plant Manager; however, the Plant Manager shall have responsibilit/ for resolution of such disagreements pursuant to Specification 6.1.1.

RECORDS 6.5.1.8 The PORC shall maintain written minutes of each PORC meeting that, at a minimum, document the 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, l

b.

Nuclear engineering, c.

Chemistry and radiochemistry, d.

Metallurgy, e.

Instrumentation and control, f.

Radiological safety, i

g.

Mechanical and electrical engineering, and h.

Quality assurance practices.

The NRB shall report to and advise the Senior Vice President and Chief Nuclear Officer on those areas of responsibility pertaining to NRB Review and Audits.

t COMPOSITION 6.5.2.2 The Chairman, members, and alternates of the NRB shall be appointed in writing by the Senior Vice President and Chief Nuclear Officer, and shall have an academic 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 composed of no less than eight and no more than 12 members.

The members and alternates of the NRB will be competent in the area of Quality J

Assurance practice and cognizant of the Quality Assurance requirements of 10 CFR Part 50, Appendix B.

Additionally, they will be cognizant of the corporate

)

Quality Assurance Program and will have the corporate Quality Assurance organization available to them.

i LIMERICK - UNIT 2 6-9 Amendment No. 2,60

+

ADMINISTRATIVE CONTROLS t

ALTERNATES 1

6.5.2.3-All alternates'shall be appointed in writing by the NRB Chairman to serve on a continuing basis..They shall receive correspondence sent to NRB members with regard tc NR8 activities.and shall be invited to attend all NRB 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.

j MEETING FREDUENCY 6.5.2.5 The NRB shall meet at least once per calendar quarter during the initial year of unit operation following fuel loading and at least once per 6 months thereafter.

DMQlMi

6. 5.P. 6 The quorum of the NRB'necessary for the performance of the NRB review I

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 l

have line responsibility for operation of the facility.

REVIEW 6.5.2.7 DELETED.

The information from this section is located in the UFSAR.

AUDITS 6.5.2.8 DELETED. The information from this section is located in the UFSAR.

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LIMERICK - UNIT 2 6-10 Amendment No. 60 l

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THIS PAGE IS INTENTIONALLY LEFT BLANK..

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1 LIMERICK - UNIT 2 6-11 Amendment No. 60-1

-1

ADMINISTRATIVE CONTROLS RECORDS I

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

g a.

Minutes of each NRB meeting shall be prepared, approved, and forwarded to the Senior Vice President and Chief Nuclear Officer within 14 days following eachl meeting.

b.

Reports of Reviews shall be prepared, approved, and forwarded to the Senior Vice President and Chief Nuclear Officer within 14 days following completion of the review, c.

Audit reports shall be forwarded to the Corporate Officer (s) and management positions responsible for the areas audited within 30 days after completion of the audit by the auditing organization.

5 5.3 PROGRAM / PROCEDURE REVIEW AND APPROVAL All programs and procedures required by Specification 6.8 shall be reviewed and approved as described below.

6.5.3.1 Each new program, procedure, or change thereto shall be independently reviewed by a Station Qualified Reviewer (SQR) who is knowledgeable in the functional area affected but is not the individual preparer. The SQR may be from the same organization as the preparer. The SQR shall render a determination in writing of whether or not cross-disciplinary review of a new program, procedure, or change thereto is necessary.

If necessary, such review shall be performed by appropriate personnel.

6.5.3.2 Each new program, procedure, or change thereto shall be reviewed by the Director or Manager designated by Administrative Procedures as the responsible Director or Manager for that program or procedure, and the review shall include a determination of whether or not a 10 CFR 50.59 safety evaluation is required.

If a 10 CFR 50.59 safety evaluation is not required, the new program, procedure, or change thereto shall be approved by the responsible Director or Manager or the Plant Manager prior to implementation. Adrinistrative Procedures shall be reviewed by PORC prior to approval. Administrative Procedures, Security Plan Implementing Prccedures, and Emergency Plan Implementing Procedures shall be approved by the Plant Manager or his designated alternate in accordance with Specification 6.1.1.

I LIMERICK - UNIT 2 6-12 Amendment No. 2,10,60

z.

ADMINISTRATIVE CONTROLS 6.5.3.3 If the responsible Director or Manager determines that a new program, procedure, or change thereto requires a 10.CFR 50.59 safety evaluation, the responsible

~

Director or Manager shall render a determination in writing of whether or not the new

- program, procedure, or change thereto involves an unreviewed safety question (USQ)

' and shall forward the new program, procedure, or change thereto with the associated safety evaluation to PORC for review.

If an USQ is involved, NRC approval is rsquired by 10 CFR 50.59 prior to' implementation of the new program, procedure, or change..

..6.5.3.4 Personnel recommended to be SQRs shall be approved and designated as such by the PORC Chairman. The responsible Director or Manager shall ensure that a sufficient.

l complement of SQRs for their functional area is maintained in accordance with Administrative Procedures. The SQRs shall meet or exceed the qualifications-described in Section 4.4 of ANSI /ANS 3.1-1978.

6.5.3.5 Temporary procedure changes shall be reviewed and approved in accordance with Specification 6.8.3.

6.5.3.6 Records documenting the activities performed under Specifications 6.5.3.1 through 6.5.3.5 shall be maintained in accordance with Specification 6.10.

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 to the requirements of Section 50.73 to 10 CFR Part 50, and b.

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

6.7 SAFETY LIMIT VIOLATION-i 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 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months . The Vice President, Limerick Generating Station, Plant Manager, and the NRB shall be notified within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

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 the 14 days of the violation.

i LIMERICK - UNIT 2 6-12a Amendment No. 10,60 u.

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ADMINISTRATIVE CONTROLS-1AFETY LIMIT VIOLATION -(Continued)

'd.

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

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 I 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.

i h.

PROCESS CONTROL PROGRAM implementation.

1.

OFFSITE DOSE 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, and any other procedure or procedure change that the Plant Manager determines to affect nuclear safety, shall be reviewed and approved in accordance with Specifications 6.5.1.6, 6.5.1.7 and/or 6.5.3, as appropriate, prior to implementation.

Each procedure of Specification 6.8.1 shall also be reviewed periodically as 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 two 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 an SQR in accordance with Specification 6.5.3.1, and approved by either the Plant Manager or his designated alternate in accordance with Specification 6.1.1, or the Director or Manager designated by Administrative Procedures as the responsible Director or Manager for that procedure within 14 days of implementation.

LIMERICK - UNIT 2 6-13 Amendment No. 10,60

-

Person / Time
ML20086Q172
Site:	Limerick (NPF-039, NPF-085)
Issue date:	07/18/1995
From:	Stolz J Office of Nuclear Reactor Regulation
To:	Philadelphia Electric Co
Shared Package
ML20086Q175	List: ML20086Q172 ML20086Q183
References
NPF-39-A-096, NPF-85-A-060 NUDOCS 9507270324
Download: ML20086Q172 (34)
v • d • e

ML20086Q172

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