ML20006E792

Amend 2 to License NPF-85,revising Tech Specs to Remove Onsite & Offsite Organizational Charts from Tech Specs 6.2.1 & 6.2.2 & Making Administrative Changes,Per Generic Ltr 88-06

ML20006E792
Person / Time
Site:	Limerick  (NPF-85-A-002, NPF-85-A-2)
Issue date:	02/08/1990
From:	Butler W Office of Nuclear Reactor Regulation
To:
Shared Package
ML20006E791	List: ML20006E789 ML20006E792 ML20006E794
References
GL-88-06, GL-88-6, NUDOCS 9002260355
Download: ML20006E792 (18)

Text

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I UMTED STATES E"

NUCLEAR REGULATORY COMMISSION

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PHILADELPHIA ELECTRIC COMPANY

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DOCKET NO. 50-353 LIMEP.ICK GENERATING STATION. UNIT 2

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AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 2 License No. NPF-85 1.

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

The application for amendment by Philadelphia Electric Company (thelicensee)datedNovember3,1989,complieswiththe standards and requirements of the Atomic Energy Act of 1954, as 1

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; l

C.

There is reasonable assurance (1) 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 Comission's regulations; D.

The issuance of this amendment will not be inimical to the comon 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 is amended by changes to the Technical Specifications-1 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:

Technical Specifications The Technical Specifications contained in App'endix A and the Environmental Protection Plan contained in Appendix B, as revised through Amendment No. 2

, are hereby incorporated into this license. Philadelphia Electric Company shall operate the facility in accordance with the Technical Specifications and the Environmental l

Protection Plan.

9002260355 900200 PDR ADOCK 05000353' P-PNV

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2 3.

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

FOR THE NUCLEAR REGULATORY COMMISSION i

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/s/

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

Attachment:

Changes to the Technical Specifications Date of Issuance:

February 8, 1990 r

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

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FOR THE NUCLEAR REGULATORY COMMISSION

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Walter R. Butler Director

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Project Directorate I-2 Division of Reactor Projects I/II

Attachment:

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Charges to-the Technical

'Specificatiens Date of Issuance: February 8, 1990 i

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' ATTACHMft1T TO LICENSE AMENDMENT NO. 2 -

FACILITY OPERATING LICENSE N0. NPF-85 DOCKET NO. 50-353

- Replace the fc110 wing 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.*

Remove-Insert xxV XxV*

- xxvi-xxvi 6-1 6-1 6-2 6-2 6-3 6-3 6-4 6. 5 6-5*

6-6 6-6 6-9 6-9 6-10 6-10*

6-11 6-11 6-12 6-12 21-6-21*-

6-22 6-22 9

4 9

4 6

4 e

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INDEX DESIGN FEATURES l

SECTION' PAGE FUEL STORAGE (Continued)

Drainage.....................................................

5-8 Capacity.....................................................

5-8 5.6 COMPONENT CYCLIC 00 TRANSIENT LIMIT..........................

5-8 Tabli 5.6.1-1 Component cyclic or Transient Limits.....

5-9 a

LIMERICK - UNIT 2 xxv h

._m__m__m._-.--.m.m-m_ma_

__-_mm.mm_

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INDEX.

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' ADMINISTRATIVE CONTROLS SECTION PAGE

. 6.1 RESPONSIBILITY...............................................

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

6-1

" ' 6.2.1 OFFSITE AND ONSITE ORGANIZATION.........................

6-1 Figure 6.2.1-1 DELETED.................

6-3 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 6.2.3-INDEPENDENT SAFETY ENGINEERING GROUP (ISEG)

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

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

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

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

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6.2.4

. SHIFT TECHNICAL ADVISOR................................

6-6 i

• 4-6~3' UNIT STAFF' QUALIFICATIONS................................,..

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

6-7 6.S-REVIEW AND AUDIT i

6.5.1

. Plant Operations Review Committee (PORC) i Function..............................................

6-7 l

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

6-7

-j Alternates.............................................

6-7 L

Meeting Frequency.....................................

6-7 1

Quorum.................................................

6-7 l

Responsibilities......................................

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

6-9

. LIMERICK - UNIT 2 xxvi Amendment Nn. 2

p 6.0 ADMINISTRATIVE CONTROLS 6.1 RESPONSIBILITY 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 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 6.2.1 0FFSITE AND ONSITE ORGANIZATIONS j

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 1.evels 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

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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 operotion and maintenance of the plant, j

l:

c..

The Vice President, Limerick Generating Station shall' have corporate j

responsibility for overall plant nuclear safety and shall take any l

measures needed to ensure acceptable performance of the staff in i

operating, maintaining, and providing technical support to the plant i

L to ensure nuclear safety.

a 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 l

I.

organizational freedom to ensure their independence from operating l*

pressures.

l -

l LIMERICK - UNIT 2 6-1 Amendment No. 2 l

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TDMINISTRATIVE CONTROLS 6.' 2. 2 UNIT STAFF l

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 fuellis 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 r'esponsibilities 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 Superintendent, 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;

=l f.

LAdministrative 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 overtimefto 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:

'l.'

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

1 LIMERICK - UNIT 2 6-2 Amendment No. 2 l

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-ADMINISTRATIVE CONTROLS' 6.2.2 UNIT STAFF (Continued)

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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 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 l

hours have not been assigned.

Routine deviation from the above guidelines is not authorized; and

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- g.~

The Plant Manager or the Superintendent Operations, and the Assistant Superintendent Operations shall hold a Senior Reactor Operator License.

The Superintendent Technical or the Technical Engineer. shall hold a Senior Reactor Operator License.

LIMERICK - UNIT 2 6-3 Amendment No. 2 l

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i LIMERICK -~ UNIT 2 6-4 Amendment No. 2 I-

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TABLE 6.2.2 1 MINIMUM SHIFT CREW CCMPOSITION TWO UNITS WITH A COMMON! CONTROL ROOM WITH UNIT-1-IN CONDITION 4 OR 5 OR DEFUELED POSITION NUMBER OF INDIVIOUALS REQUIRED TO FILL POSITION CONDITION 1, 2, or 3 CONDITION 4 or'5 SS 1*

1*

SR0 la la R0 2

1 NLO 2

2**

STA 1

None 4

WITH UNIT 1-IN CONDITION 1, 2, OR 3 POSITION NUMBER OF INDIVIDUALS REQUIRED TO FILL POSITION CONDITION 1, 2, or 3 CONDITION 4 or 5 SS la la SR0

'1*

1a R0 2**

1 NLO 2**

1 STA 1*

None TABLE NOTATIONS

• Individual may fill the same position on Uni: 1.

• • 0ne of the two required individuals may fill the same' position on Unit 1.

SS

-Shift Superintendent-or' Shift: Supervisor with a Senior Operator license on Unit'2.

SRO

. Individual with a Senior Operator license on Unit 2.

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 Shift Supervision (SS), the shift crew cceposition may be one less

than.the minimum requirements of-Table 6.2.2-1 for a period df 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 accommodate unexpected absence of on-duty shift crew

-members provided immediate 1ction 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 oncoming-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 individual (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, anLindividual with a valid Senior Operator license or Operator license

.shall be designated to assume the control room command function.

LIMERICK - UNIT 2 6-5

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• .*.1-ADMINISTRATIVE CONTROLS 6.2.3' INDEPENDENT SAFETY ENGINEERING GROUP (ISEG)

FUNCTION 6.2.3.1 The ISEG shall function to examine unit operating characteristics, NRC issuances, industry advisories, Licensee Event Reports,-and other sources of unit design and operating experience information, including units of simi-lar design,.which may indicate areas for improving unit safety.

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

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

COMPOSITION 6.2.3.2 The Limerick ISEG shall be. composed of at least five, dedicated, full-l time engineers, including the ISEG Superintendent, located onsite.

Each shall I

have a bachelor's degree in engineering or related science and at least two years professional level experience in his or her field.

The Limerick ISEG Superintendent shall have at least six years of experience in the nuclear field, The LGS ISEG reports to the General Manager - Nuclear Quality Assurance.

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

• that these activities are 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 General Manager - Nuclear Quality Assurance.

6.2.4 SHIFT TECHNICAL ADVISOR 6.2.4.1 The Shift Technical Advisor shall-provide 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 and shall have received specific training in the response and. anal-ysis of the unit for transients and accidents, and in unit design and layout, including the capabilities of instrumentation and controls in the control room.

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 specified in Sections A and C of Enclosure 1 of the March 28, 1980 NRC letter to all licensees.

• Not responsible for sign-off function.

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

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E ADMINISTRATIVE CONTROLS >

' RESPONSIBILITIES ~(Continued)

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, c.

Limerick Generating Station and the Nuclear Review Board of disagree-ment between the PORC and the Plant Manager; however, the Plant Manager shall have responsibility for resolution of such-disagreements 4

pursuant to Specification 6.1.1.

j 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.

i 6.5.2 NUCLEAR REVIEW BOARD (NRB)

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

4 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 Executive Vice President - Nuclear

'on those areas of responsibility in Specifications 6.5.2.7 and 6.5.2.8.

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5 COMPOSITION

'6.5.2.2 -Th'e Chairman, members, and alternates of the NRB shall be appointed cin writing by the Executive Vice President - Nuclear, 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 NR8 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 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.

LIMERICK - UNIT 2 6-9 Amendment No.2 l

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ADMINISTRATIVE' CONTROLS ALTERNATES 6.5.2.3' All alternates shall be appointed in writing by the NRB Chairman to serve on a continuing basis.. They sr.all receive correspondence sent to NRB

-members with regard to NRB activities and shall be invited to attend all NRB meetings.' Alt 6rnates 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 calendar quarter during the initial year of unit operation following fuel loading and at least once per 6 months

.thereafter.

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:

The safety-evaluations for (1) changes to procedures, equipment, a.

faciliti the prov,es or systems;;and-(2) tests or experiments completed under ision 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 unrevipwed safety question as defined in 10 CFR 50.59; Proposed tests or experiments which involve an unreviewed safety c.

, uestion as defined in 10 CFR 50.59;'

q d.

Proposed changes to Technical' Specifications or this Operating License; Violations of codes, regulations, orders, Technical Specifications, e.

license requirements, or of internal procedures or instructions' having nuclear safety significance; f.

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

All REPORTABLE EVENTS; LIMERICK - UNIT 2 6-10

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L ADMINISTRATIVE CONTROLS b

REVIEW-(Continued).

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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.

AUDITS 6.5.2.8 Audits of un'it 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; The results of actions taken to correct deficiencies occurring _ in c.

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

The performance of activities required by the'0perational Quality Assurance Program to meet the criteria of Appendix B, 10 CFR Part 50,. at-least once per 24 months;

- The Emergency Plan and implementing procedures at least once per e.

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 or the Executive Vice President - Nuclear.

h.

The Fire Protection Program and implementing procedures at least once per 24 months, i.

An independent fire protection and loss prevention inspection and-audit shall be performed at least once per 12 months 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, LIMERICK - UNIT 2 6-11

4 ADMINISTRATIVE CONTROLS AUDITS (Continued) k.

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

1.

The OFFSITE DOSE CALCULATION MANUAL and implementing procedures *at least once'per'24 months, m.

The' PROCESS CONTROL PROGRAM and implementing precr.,dures at least once per 24 months.

n.

The performance of activities required by the Quality Assurance-Program to-meet the criteria cf Regulatory Guide 4.15, December,1971, at least once per 12 months.

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 Executive Vice President - Nuclear within 14 days following each

meeting, b.

Reports of reviews encompassed by= Specification 6.5.2.7_shall be prepared, approved, and forwarded to the Executive Vice President -

Nuclear within 14 days following completion of the review, c.

Audit reports encompassed by Specification 6.5.2.8 shall be forwarded 1

to the Corporate Officer (s) and management positions responsible for l

2 the areas-audited within 30 days after completion of the audit by 2

the auditing organization.

m m

+ 6.6 REPORTABLE EVENT ACTION q

6.6.1 The.following actions shall be taken for REPORTABLE EVENTS:

l 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:

4 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 Vice 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 />.

LIMERICK - UNIT 2 6-12 Amendment No. 2 g

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1 Al a ADMINISTRATIVE CONTROLS HIGH RADIATION AREA 1(Continued) b.

~ A radiation monitoring device which continuously integrates the-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 levels in the area have been.estab-lished'and personnel have been made knowledgeable of them.

c.

A health physics qualif~,ed individual (i.e., qualified in-radiation protection-procedures) with a radiation dose rate monitoring device who is responsible for providing positive control over the activi--

ties within the area and shall perform periodic radiation surveil-lance at the frequency specified by the Health Physicist in the RWP.

6.12.2 In addition to the requirements of Specification 6.12.1,-areas accessible to personnel with radiation levels such that a major portion of the body could receive in 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> a' dose greater than 1000 mrems shall be provided.with locked doors to prevent unauthorized entry, and the keys shall be maintained under the administrative control of Shift Supervision on duty and/or the health physics supervision. - Doors shall remain locked except-during periods of_ access by personnel under an approved RWP which shall'specify the dose rate levels in the immediate. work area and the maximum allowable stay time for' individuals in that area.

For individual areas accessible to personnel with: radiation levels

' such that'a major portion of the body could receive in 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> a dose in excess

<of 1000 aress* that are located within large areas, such as the containment, where no enclosure-exists for purposes of locking, and no enclosure can be, reasonably constructed around the individual areas, then that. area shall be

-roped o,ff, conspicuously posted, and a flashing-light shall be activated-as a warning-device.

In lieu of the stay time specification of the RWP, continuous surveillance direct or remote (such as use of closed circuit TV cameras), may be made by personnel qualified-in radiation protection procedures to provide positive exposure control over the activities within the area.

6.13 PROCESS CONTROL PROGRAM (PCP) i 6.13.1 The PCP shall be approvou by the Commission prior to implementation.

6.13.2 Licensee-initiated changes to the PCP:

a.

Shall be submitted to the Commission in the Semiannual Radioactive Effluent Release Report for the period in-which the change (s) was made effective.

This submittal shall contain:

1.

Sufficiently detailed information to totally support the rationale for the change without benefit of additional or a

supplemental information.

• Measurement made at 18 inches from source of radioactivity.

LIMERICK - UNIT 2 6-21 s

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ADMINISTRATIVE CONTROLS

-PROCESS CONTROL PROGRAM (Continued) 2.

A determination that the change did not reduce the overall conformance of the solidified waste product to existing criteria for solid wastes; and 3.

Documentation of the fact that the change has been reviewed and found acceptable by the PORC.-

b.

Shall become effective upon review and. acceptance by the PORC.

6.14 0FFSITE DOSE CALCULATION MANUAL (ODCM) 6.14.1. The ODCM shall be approved by the Commission prior.to implementation.

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6.14.2 Licensee-initiated changes to the ODCM:

a.

Shall be submitted to the Cor. nission _in the Semiannual Radioactive Effluent Release Report for the-period in which the change (s) was made effective. -This submittal shall contain:

1.

Sufficiently detailed information to totally. support.the.

I rationale for the change without benefit of additional or supple-i mental information.

Information submitted should consist of a package of those pages of the ODCM to be changed with each page numbered and provided with an approval and date-box, together with appropriate analyses or evaluations justifying the change (s);

A 2.

A determination that-the change will not reduce the accuracy or t,

reliability of dose calculations or setpoint determinations; and 3.

Documentation of tne fact that the change has been reviewed H

and found acceptable by the PORC.

b.

Shall become effective upon review and acceptance by the PORC,

[

l 6.15 MAJOR CHANGES TO RADI0 ACTIVE' WASTE TREATMENT SYSTEMS 6.15.1'_ Licensee-initiated major changes to the radioactive waste systems l

j (liquid, gaseous, and solid):

a.

Shall,be reported to the Commission in the Semiannual Radioactive Effluent Release Report fur the period in which the change was made effective.

The discussion of each change shall contain:

1 1.

A summary of the evaluation that led to the determination that the change could be made in accordance with 10 CFR 50.59; r

l s

LIMERICK - UNIT 2 6-22 Amendment No. 2

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