ML18011A510

Proposed Tech Specs Re Performance Based Nuclear Assessment Program

ML18011A510
Person / Time
Site:	Harris
Issue date:	07/22/1994
From:	CAROLINA POWER & LIGHT CO.
To:
Shared Package
ML18011A509	List: ML18011A508 ML18011A510
References
NUDOCS 9407290419
Download: ML18011A510 (28)

Text

ENCLOSURE< 5 SHEARON HARRIS NUCLE<AR POWER PLANT NRC DOCKET NO. 50-400/OPE<RATING LICENSE NO. NPF-63 REQUE<ST FOR LICE<NSE< AME<NDME<NT PERFORMANCE BASED NUCLEAR ASSE<SSMENT PROGRAM MARKED-UP TE<CHNICALSPECIFICATION PAGES 9407290419 940722 PDR ADOCK 05000400 PDR 2228nri.717 E5-1

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~ I INDEX

6. 0 ADMINISTRATIVE CONTROLS SECTION PAGE 6 o 1 RESPONS IBILITYo ~

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6. 2 ORGANIZATION...'.............................................

6.2.1 ONSITE AND OFFSITE.................

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

FIGURE 6.2-1 DELETED...........................................

FIGURE 6. 2-2 DELETED.....

TABLE 6.2"1 MINIMUM SHIFT CREW COMPOSITION.........

6"1 6-1 6"1 6"3 6-4 6"5 Ftf 4

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6. 2. 4 SHIFT TECHNICAL ADVISOR..

6"6 6-6 6-6 6-6

6. 3 UNIT STAFF UALIFICATIONS...................................

6-6 6.5 REVIEW AND AUDIT......

6.5.1 SAFETY AND TECHNICAL REVIEWS General Program Control.........

Technical Evaluations...........

qualified Safety Reviewers......

Safety Evaluations and Approvals 6.5.2 PLANT NUCLEAR SAFETY COMMITTEE ( PNSC)

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Compos 1tlon.

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Meeting Frequency.

quorum.

Responsibilities Records..

6.4 TRAINING...........................

6"7 6-7 6"7 6"7 6-7 6"8 6"9 6"9 6-9 6-9 6"ll SHEARON HARRIS " UNIT 1 XV111 Amendment No.

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INDEX ADMINISTRATIVE CONTROLS gudooo AooeasmprJ7 Socle>< ~~op ~o~~ ~+

'.5.3 Functlon ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~

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6-11 Organizat lOll ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~

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6"11 Revlev

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" Not responsible for sign-off function.

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SHEARON HARRIS - UNIT 1

6"6 Amendmenc No ~

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ADMINISTRATIVE CONTROLS ualified Safet Reviewers (Continued)

These individuals shall have a baccalaureate degree in an engineering or related field or equivalent, and 2 years of related experience.

Such designation shall include the disciplines or procedure categories for which each individual is qualified.

guali;fied individuals or groups not on the plant staff may be reLied upon to perform safety reviews if so designated by the Plant General Manager.

6.5.1.4 Safet Evaluations and A

rovals 6.5.1.4.1 The safety evaluation prepared in accordance with Specification 6.5.1.1.1 shall include a written determination, with basis, of whether or not the procedures or changes

thereto, proposed tests and experiments and changes

thereto, and modifications constitute an unreviewed safety question as defined in Paragraph 50.59 of 10 CFR Part 50, or whether they involve a change to the Final Safety Analysis Report, the Technical Specifications, or the Operating License.

6.5.1.4.2 The safety evaluation shall be prepared by a qualified individuals The safety evaluation shall be reviewed by a second qualified individuals 6.5.1.4.3 A safety evaluation and subsequent review that conclude that the subject action may involve an unreviewed safety question, a change to the Technical Specifications, or a change to the Operating License, will be referred to the Plant Nuclear Safety Committee (PNSC) for their review in accordance with Specification 6.5.2.6.

If the PNSC recoamendation is that an item is an unreviewed safety question, a change to the Technical Specifications, or a change to the Operating License, the action will be referred to the Commission for approval prior to implementation.

Implementation may not proceed until after review by the Nuclear Assessment

-Dey~aeaa in accordance with Specification 6.5.3.9.

Sacro N

6.5.1.4.4 If a safety evaluation and subsequent review conclude that the subject action does not invoLve an unreviewed safety question, a change to the Technical Specification, or a change to the Operating License, the action may be approved by the Plant General Manager or his designee or, as applicable, by the Manager of the primary functional area affected by the action.

The individual approving the action shall assure that the reviewers collectively possess the background and qualification in all of the disciplines necessary and important to the specific review for both safety and technical aspects.

+ f/< Q~c.'>L'i fy ~ descr'ib~

6.5.1.4.5 A safety evaluation and subsequent review that conclude that the a change<in the Final Safety Analysis Report shall be referred to the Nuclear Assessment for review in accordance with Specification 6.5.3.9, but impleme ~ation aIay proceed prior to the completion of that review.

See,lioH AodlgIcnlio0$

Pfecel&f'BS,-teGts or BXper'image 4)4'i eg ~/sf'~ top~

6 ~ 5.1.4 ~ 6 T e individual approving the procedure,

tests, or experiment or change thereto shall be other than those who prepared the safety evaluation or performed the safety review.

SHEARON HARRIS - ONIT 1

. 6-8 Amendment No.

p6

ADMINISTRATIVE CONTROLS RESPONSIBILITIES (Continued) bo Review of all proposed tests and experiments that affect nuclear safety and that have been initially determined to appear to consti" tute an unreviewed safety question or involve an unreviewed change to'he Technical Specifications',

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Review of all proposed changes to Appendix "A" Technical Specifications; d ~

Review of all proposed changes or modifications to unit systems or equipment that affect nuclear safety and that have been initially determined to appear to constitute an unreviewed safety question as defined in 10 CFR 50.59 or involve a change to the Technical Spec ifications; e.

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 - Harris Nuclear P744 f.

Review of all REPORTABLE EVENTS; ge Review of unit operations to detect potential hazards to nuclear safety',

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Performance of special reviews, investigations, or analyses and reports thereon as requested by the Plant General Manager or the Manager Nuclear Assessment Oep~seec;

~Get> o H Review of the Security Plan; j.

Review of the Emergency Plan>

k.

Review of any accidental, unplanned, or uncontrolled radioactive release including the preparation of reports covering evaluation, recommendations, and disposition of the corrective action"to'revent recurrence and the forwarding of these reports to the Vice President - Harris Nuclear VLav 5'eview, prior to implementation, of changes to the PROCESS CONTROL PROGRAM, the OFFSITE DOSE CALCULATION MANUAL, the Radwaste Treatment

Systems, and the Technical Specification Equipment List Program.

6.5.2.7 The PNSC shall:

a.

Render determinations in writing with regard to whether or not each item considered under Specification 6.5.2.6a.

through e. constitutes an unreviewed safety question; and SHEARON HARRIS. - UNIT 1

6-10 Amendment No.

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ADMINISTRATIVE CONTROLS RESPONSIBILITIES (Continued)

<PLY@'.

b.

Provide writtegnotification 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-Harris Nuclear ~~

~~~a of disagreement between the PNSC and the Plant General Manager.

However, the Plant General Manager shall have responsibility for resolution of such disagreements pursuant to Specification 6.1.1.

RECORDS 6.5.2.8 The PNSC shall maintain written minutes of each PNSC meeting that, at a minimum, document the results of all PNSC activities performed under the responsibility provisions of these Technical. Specifications.

Copies shall be provided to the Vice President - Harris Nuclear ~ea+

and the Manager Sk~ffold FUNCTION Spc fioA independent review of plant changes,

tests, and procedures; verify that REPORTABLE EVENTS are investigated in a timely manner and corrected in a manner that reduces the probability of recurrence of such events>

and detect trends that may not be apparent to a day-to-day observer.

ORGANIZATION 6.5.3.2 The individuals assigned responsibility for independent reviews shall be technically qualified in a specified technical. discipline or disciplines.

These individuals shall collectively have the experience and competence required to review activities in the following areas:

a.

Nuclear power plant operations, b.

Nuclear engineering, c.

Chemistry and radiochemistry, d.

Metallurgy, 4 Instrumentation and control,

'K. Q Radiological safety, y,. ~ Mechanical and electri:cal engineering,

'h. t Administrative controls, > ~<>~<< zQ Quality assurance practices, C Nondestructive testing, and L Other appropriate fields SHEARON HARRIS - UNIT 1

6-11 Amendment No.

26

ADMINISTRATIVE CON S

ORGANIZATION (Cont inued)

Spctiok 6.5.3.3 The Manager - Nuclear Assessment Lkq~aeea shall have a

degree in an engineering or related Eield and, in addition, shall have a minimum of 10 years'elated experience, oE which a minimum of 5

years shall be in the operation and/or design of nuclear power plants.

ba cAp Lot"N 6.5.3.4 The independent safety review program reviewers shall. each have a

degree in an engineering or related field or equivalent and, in addition, shall have a minimum of 5 years'elated experience.

Sec7'i o0 6.5.3.5 An individual may possess competence in more than one specialty area.

If suEficient expertise is not available within the Nuclear Assessment competent individuals from other Carolina Power 6 Light Company organizations or outside consultants shaLL be utilized in performing independent reviews and investigations, 6.5 dxviduals, q

1'E d

d ed in Specifica-tion 6.5.3.2 above shall review eac x

the requirements of gePL~ with 4m 5.5;9.4 a3~~Aed 6.5.3.7 Independent safety reviews shall be performed by individuals not directly involved with the, activity under review or responsible for the activit under review.

y Sec~iOH 6.5.3.8 The Nuclear Assessment 4apaa-aaeac independent safety review program shalL be conducted in accordance with written, approved procedures.

Re.PLnae L)tfh 4 5.3. l 5.3.9 The Nuclear Assessment Department shaLL perform reviews of the fol ing.

a ~

itten safety evaluations Eor all procedures and programs a'equired by cification 6.8 and other procedures that affect nuclear safety and cha es thereto, and proposed tests or experiments and proposed modificati

, any of which constitute a change to the Final Safety Analysis Repor Implementation may proceed prior to completion,of the review; be All procedures and progr required by Specification 6.8 and other procedures that affect nucle safety and changes thereto that con-stitute an unreviewed safety qu tion as defined in Paragraph 50.59 of 10 CFR Part 50 or involve a cha to the Technical Specifications>

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All proposed tests or experiments that const>

e an unreviewed safety question as defined i'n Paragraph 50.59 of CFR Part 50 or involve a change to the Technical. Specifications prx to implemen-tation; HAll proposed changes to the Technical Specifications and Opera g

License; SHEARON HARRIS - UNIT 1

6-12 Amendment No.

26

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INSERT TO PAGE 6-12.

6.5.3.6 The documents submitted under 6.5.3.9 shall be reviewed by individuals meeting the requirements of 6.5.3.2 and 6.5.3.4 to ensure disciplines are encompassed.

Multiple reviews willbe conducted on documents where required to meet applicable disciplines of 6.5.3.2.

2228nri.717

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INSERT TO PAGES 6-12 AND 6-13.

6.5.3.9 REVIEW The Nuclear Assessment Section shall perform reviews of the following:

Written safety evaluations of changes in the facility as described in the Safety Analysis Report, changes in procedures as described in the Safety Analysis Report, and tests or experiments not described in the Safety Analysis Report which are completed without prior NRC approval under the provisions of 10 CFR 50.59(a)(1).

These reviews are to verify that such

changes, tests, or experiments do not involve a change in the Technical Specifications or an unreviewed safety question as defined in 10 CFR 50.59(a)(2).

These reviews may be conducted after appropriate management

approval, and implementation may proceed prior to completion of the review.

b.

Proposed changes in procedures required by these Technical Specifications, proposed changes in the facility, or proposed tests or experiments, any of which involve a change in the Technical Specifications or an unreviewed safety question pursuant to 10 CFR 50.59 (a)(2) prior to implementation.

c.

Proposed changes to the Technical Specifications or this Operating License prior to implementation.

d.

Violations, deviations and REPORTABLE EVENTS, which require reporting to the NRC in writing, such as:

1.

violations of applicable

codes, regulations,

orders, Technical Specifications, license requirements or internal procedures or instructions having safety significance, 2.

significant operating abnormalities or deviations from normal or expected performance ofplant safety-related structures, systems, or components, and 3.

REPORTABLE EVENTS as specified in 10 CFR 50.73.

All recognized indications of an unanticipated deficiency in some aspect of design or operation of structures,

systems, or components that could affect nuclear safety.

Any other matter involving safe operation of the nuclear power plant that the Manager

- Nuclear Assessment Section deems appropriate for consideration or which is referred to the Manager - Nuclear Assessment

Section, by the on-site operating organization, Plant Nuclear Safety Committee (PNSC) or by other functional organizational units within CPAL.

2228nri.717

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INSERT TO PAGES 6-12 AND 6-13 (CONTINUED).

RECORDS 6.5.3.10 Results of Nuclear Assessment Section independent safety 'reviews shall be documented and retained.

2228nri.717

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ADMINISTRATIVE CONTROLS Se=hoa AsseSs<~T 6.5.4 NUCLEAR ASSESSMENT PROGRAM AUDITS 5 9 (LtTA~RQ 6..4.1 Audits of unit activities shall be performed by the Nuclear Ass sment Department.

These audits shall encompass:

a ~

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

C ~

The raining, qualifications, and performance as a group, of the entir unit staff, at least once per 12 monthsi The resu s of actions taken to correct deficiencies occurring in unit equip nt, structures,

systems, or method of operation that affect nucle r safety, at least.once per 6 months; d.

The performance f activities required by the Operational equality Assurance Program to meet the criteria of Appendix B, 10 CFR Part 50, at least o ce per 24 months>

e.

The fire protection pr raamatic controls including the implementing procedures, at least onc per 24 months, by qualified licensee gA personnel; The Radiological Environmenta Monitoring Program and the results thereof, at least once per 12 m

thsi The OFFSITE DOSE CALCULATION MANUA and implementing procedures, at least once per 24 months; h.

The PROCESS CONTROL PROGRAM and implemen ing procedures for processing and packaging of radioactive w

tes, at least once per 24 months; 1 ~

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The performance of activities required by the ality Assurance Program for effluent and environmental monitorin at least once per 12 months; I

The Emergency Plan and implementing procedures, at lea 't once per 12 months,'

The Security Plan and implementing procedures, at least onc per 12 months>

and Any other area of unit operation considered appropriate by the Nuclear Assessment Department or the, Vice President Harris Nucle r Project.

6.5.4.2 Personnel performing the quality assurance audits shall have access SHEARON HARRIS - UNIT 1

6-14 Amendment No. 26

INSERT TO PAGE 6-14.

6.5.4 Nuclear Assessment Section Assessment Program 6.5.4.1 Assessments of facility activities shall be performed by the Nuclear Assessment Section.

Assessments willbe performance based and willbe scheduled based on plant performance and importance to safety but at a frequency not to exceed 24 months.

These assessments shall encompass:

a.

The conformance of facility operation to provisions contained within the Technical Specifications and applicable license conditions.

b.

The performance, training and qualifications of the entire facility staff.

c.

The results of actions taken to correct deficiencies occurring in facility equipment, structures, systems or method of operation that affect nuclear safety.

d.

The performance of activities required by the QA Program to meet the criteria of Appendix B, 10 CFR 50.

e.

Any other area of facility operation considered appropriate by the Vice President - Harris Nuclear Plant.

The Fire Protection Program and implementing procedures.

g.

The Radiological Environmental Monitoring Program and the results thereof.

h.

The OFF-SITE DOSE CALCULATIONMANUALand implementing procedures.

The PROCESS CONTROL PROGRAM and implementing procedures for processing and packaging of radioactive wastes.

6.5.4.2 Assessments of activities prescribed by the Code of Federal Regulations will be performed at the frequencies prescribed by the applicable regulation.

These assessments shall encompass:

a.

Emergency Preparedness (per 10 CFR 50.54(t))

b.

Security (per 10 CFR 50.54(p))

2228nri.717

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INSERT TO PAGE 6-14 (CONTINUED).

6.5.4.3 The NAS shall include at least three individuals to perform the Independent Safety Engineering Group gSEG) function. Each reviewer shall have a bachelor's degree in engineering or related science or equivalent and at least two years professional level experience in his field, at least one year of which shall be in the nuclear field.

6.5.4.3.1 The NAS shall function to examine unit operating characteristics, NRC issuances, industry advisories, Licensee Event Reports, and other sources of unit design information which may indicate areas of improving unit safety.

Review responsibilities shall also include plant operations, modifications, maintenance, and surveillances to verify independently that these activities are performed safely and

'correctly and that human errors are reduced as much as practical.

2228nri.717

ADMINISTRATIVECONTROLS CORDS 6.5."4.

AaP~@e. mi 7h c s'-~ ~~~~4+

Records of audits shall be prepared and retained.

6.5.4.4 dit reports encompassed by Specification 6.5.4.1 shall be

prepared, ap oved by the Manager - Nuclear Assessment Department, and forwarded, with 30 days after completion of the audit, to the Executive Vice President " Power upply, Senior Vice President - Nuclear Generation, Vice President - Harris clear Project, PLant General

Manager, and the management positions responsible r the areas audited.

AUTHORITY 6.5.4.5 The Manager " Nuclear sessment Department shall be responsible for the following:

a.

Administering the Nuclear Ass sment Department Audit Program.

b.

Approval of the individuals select to conduct quality as'surance audits.

6.5.4.6 Audit personnel shall be independent of th area audited.

6.5.4.7 Selection of personnel for auditing assignments hall be based on experience or training that establishes that their qualific ions are cosmen-surate wit'h the complexity or special nature of the activities to be audited.

" In seLecting audit personnel, consideration shall be given to sp ial abilities, specialized technical training, prior pertinent experie e,

personal characteristics, and education.

6.5.4.8 Qualified outside consultants, or other individuals independent om those personneL directly involved in plant operation, shall be used to augme the audit teams when necessary.

OUTSIDE ACENCY INSPECTION AND AUDIT PROGRAM 6.5.5.1 An endent fire protection and loss prevention inspection and audit shall be per d at least once per 12 months using either qualified offsite licensee personne an outside fire protection firm.

6.5.5.2 An inspection and audit of fire protection and Loss prevention program shall be performed by an outside qua

'ed fire consultant at inter-vals no greater than 36 months.

6.5.5.3 Copies of the audit reports and responses to them s

be forwarded to the Vice President " Harris Nuclear Project and the Manager - Nuc Assessment Department.

6 '

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

SHEARON HARRIS - UNIT 1

6-15 Amendment No.

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ADMINISTRATIVE CONTROLS REPORTABLE EVENT ACTION (Con tinued )

a.

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

Each REPORTABLE EVENT shall be reviewed by the

PNSC, and the results of this review shal.l be submitted to the Hanager - Nuclear Bee-jeer.

Skchod PLY 6 ~ 7 SAFETY LIMIT VIOLATION 6.7.1 The following actions shall be taken in rhe event a Safety Limit is violated:

a ~

b.

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-Harris Nuclear D~~eat sh be notified within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />; PLaol A Safety Limit Violation Report shall be prepared.

The report shall be reviewed by the PNSC.

This report shall describe'(1) applicable circumstances'receding the violation, (2) effects of the violation upon facility components,

systems, or structures, and (3 ) corrective action taken to prevent recurrence; C ~

d".

The Safety Limit Violation Report shall be submitted, within 14 days of the violation, to the Commission, the Hanager Nuclear Assessment Deq~eeaeat, and the Vice President Harris Nuclear and SccTioW PLa~t'peration 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 recotmended in Appendix A of Regulatory Guide 1.33, Revision 2, February 1978i b.

The emergency operating procedures required to implement the requirements of NUREG-0737 and Supplement 1 to NUREG-0737 as stated in Generic Letter No. 82-33; C ~

d ~

e.

Security Plan implementation; Emergency Plan implementation',

PROCESS CONTROL PROGRAH implementation; f.

OFFSITE DOSE CALCULATION HANUAL implementation; SHEARON HARRIS - UNIT 1

6"16 Amendment No.

26

ADMINISTRATIVE CONTROLS RECORD RETENTION (Continued) h.

Records of annual physical inventory of all sealed source material of record.

6.10.3 The following records shal.l be 8ecained for the duration of the unit Operating License:

a.

Records and drawing changes reflecting unit design modifications made to systems and equipment described in the Final Safety Analysis Report; b.

Records of new and irradiated fuel. invencory, fuel transfers, and assembly burnup histories; C ~

Records of radiation exposure for all individuals entering radiacion'ontrol areas) d.

Records of gaseous and liquid radioactive material released to the environs'.

Recoi'ds of transient or operational cycles for those unit components identified in Table 5.7-1; f.

Records of reactor tests and experiments>

Records of training and qualification for currenc members of the unit staff; ho Records of inservice inspections performed pursuant to. these Technical. Specifications; 1 ~

Records of quality assurance activities required by the Corporate Quality Assurance Program',

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Records of reviews performed for changes made to procedures or equipment or reviews of tests and experiments pursuant to 10 CFR 50.59'o Records of meetings of the PNSC f

Records of the service lives of all hydraul.ic and mechanical snubbers required by Specification 3.7.8 including the date at which the service life commences and associated installation and maintenance records>

Records of secondary water sampling and water quality) n.

Records of analyses required by the Radiological Environmental Monitoring Program that would permic evaluation of the accuracy of the analysis at a later data.

This should include procedures SHEARON HARRIS " UNIT 1

6-25 Amendmenc No.

Z6

AQMIHI~iTIVECONTROLS RECORD RETENTION Continued)

C effective at specified times and gA records showing that these pracadures were followed; and o.

Records af facility radiation and contamination surveys.

Rue re& A Zud~deu>

Re.vleu

6. LL RADIATION PROTECTION PROGRAM 6.LLL Procedures for personnel radfatfon protection shall be prepared consistent with tha requirements of IO CFR Part 20 and shal1 be approved, maintained, and adhered ta for al.l opeWtfons involving personnel radiation exposure.

6. L2 HIGH RADIATION AREA 6.LZ.L Pursuant to Paragraph 20.203(cj(5} af IO CFR Part 20, in lieu of the "control device" or "alarm signal" required by Paragraph 20.203(c),

each high r adiation area, as deffned in LO CFR Part 20, in which the intensity of radia-tion is equal ta or less than IOOO mR/h at 45 cm (IS in.) fram the radiation source or from any surface which the radfatfan penetrates shall he barricaded and conspicuously posted as a high radiation area and entrance thereto shall be controlled by requir ing issuance of a Radiation Mark Permit (RMP).

Individuals qualified in radiation protection procedures (e.g., Health Physics Technicians) or personnel continuously escorted by such individuals may ba exempt from the RMP issuance requirement during the performance of their assigned duties in high radiatian areas with exposure rates equal ta or less than 1000 mR/h pro-vided they are otherwise fallawing plant radiation protection procedures for entry into such high radiation areas.

Any individual or group of individuals permitted ta enter such areas shall be provided with or accompanied by one or more of the fo11owing:

a.

A radiation monitoring device that continuously indicates tha radfatfon dose rata in the area; or b.

A radiation monitoring device that continuously integrates the radiation dose rata 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 tham; or c.

An fndfvidual qualified fn radiatian protection.'procedures, with a radfatian dose rate monitaring device, who is responsible far pro-viding positive control over the activities within the area and who sha11 perform periodfc radiation survei11ance at the frequency specf fied by the Radfatfon Control Supervisor in the RWP.

6. X2.2 In addfXfon to the requirements of Speci ffcation 6. 12. I, accessible areas with radiation levels greater than 1000 mR/h at 45 cm (IS in.) from the radfWfon source or from any surface which the radiatfon penetratas, shall be

'rovided with lacked daars ta prevent unauthorized entry, and the keys shall be maintained under the administrative control of the shift Foreman on duty SHEAROH HARRIS - UNIT' 6-26

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