ML20236R930

Amend 55 to License NPF-86,modifing TS Sections 6.0, Administrative Control, to Reflect Recent Organizational Changes & Changes to Approval Title for Section Qualified Reviewer Program & Correcting Incorrect Ref in TS 6.4.3.9.b

ML20236R930
Person / Time
Site:	Seabrook
Issue date:	03/26/1998
From:	Thomas C NRC (Affiliation Not Assigned)
To:
Shared Package
ML20236R932	List: ML20236R930 ML20236R933
References
NUDOCS 9807240030
Download: ML20236R930 (17)

Text

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8 UNITE 3 STATES 3

NUCLEAR REGULATORY COMMISSION h

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WASHINGTON, D.C. 305064001 NORTH ATLANTIC ENERGY SERVICE CORPORATION. ET AL?

DOCKET NO. 50-443 SEABROOK STATION UNIT NO.1.

AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 55 License No. NPF-86 1.

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

A.

The application for amendment filed by the North Atlantic Energy Service Corporation, l

et al. (the licensee), dated February 12,1997, complies with the standards and l

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

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.

• North Atlantic Energy Service Corporation (NAESCO) is authorized to act as agent for:

North Atlantic Energy Corporation, Canal Electric Company, Connecticut Light and Power Company, Great Bay Power Corporation, Hudson Light & Power Department, Massachusetts Municipal Wholesale Electric Company, Montaup Electric Company, New England Power Company, New Hampshire Electric Cooperative, Inc., Taunton Municipal Light Plant, United liluminating Company, and Vermont Electric Generation and Transmission Cooperative, Inc., and has exclusive responsibility and control over the physical construction, operation and maintenance of the facility.

9907240030 980326

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PDR ADOCK 05000443 ur P

PDR y

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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-86 is hereby amended to read as follows:

(2) Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No.55, and the Environmental Protection Plan contained in Appendix B are incorporated into Facility License No. NPF-86. NAESCO shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.

l 3.

This license amendment is effective as of its date of issuance, to be implemented within 60 days.

FOR THE NUCLEAR REGULATORY COMMISSION 0

W

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Cecil O. Thomas, Director l

Project Directorate 1-3 l

Division of Reactor Projects - 1/11 i

Office of Nuclear Reactor Regulation I

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Attachment:

Changes to the Technical Specifications Date of Issuance: March 26, 1998 l

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. ATTACHMENT TO LICENSE AMENDMENT NO. m; FACILITY OPERATING LICENSE NO. NPF-88 DOCKET NO. 50-443 Replace the following pages of the Appendix A, Technical Specifications, with the attached pages as indicated. The revised pages are identified by amendment number and contain vertical lines indicating the area of change. Overleaf pages have been provided.*

Remove bW S1

&1 6-2*

6-2*

6-3*

6-3*

6-4 6-4 I

6-5*

6-5*

64 64

&7

&7 l

&B

&8 6-BA 6-8A 6-8B 6-8B 6-10 6-10 6-11 6-11 6-12 6-12 6 21 6-21 6-22*

6-22*

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6.0 ADMINISTRAffVE cnNMot R 6.1 RFSPON M lH 6.1.1 The Station Director shall be responsible for overall station operation l

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

l 6.1.2 The Shift Manager (or during his absence from the control room a designated individual) shall be responsible for the control room comma,nd l

function.

A management directive to this effect, signed by the Executive Vice President & Chief Nuclear Officer shall be reissued to all station personnel on i

l an annual basis.

63 ORGANIZATION 6.2.1 0FFSITE AND ONSITE ORGANf7ATf0NS 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.

l Lines of authority, responsibility, and connunication shall be i

a.

established and defined for the highest management levels through intermediate levels to and including all operating organization l

positions.

These relationships shall be documented and updated. as appropriate, in the form of organization charts, functional descriptions for departmental responsibilities and relationships.

and job descriptions for key personnel positions, or in equivalent

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forms of documentation. These requirements shall be documented in the FSAR and updated in accordance with the requirements of 10 CFR 50.71.

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l b.

The Station Director shall be responsible for overall unit safe 1

L operation and shall have control over those onsite activities l

necessary for safe operation and maintenance of the plant.

The Executive Vice President & Chief Nuclear Officer shall have c.

l corporate responsibility for overall plant nuclear safety and shall i

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.

i 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.

SEABROOK - UNIT 1 6-1

~ Amendment No. 55

80 ADMINISTRATE!VE CONTROLS j

l 6.2.2 STATION STAFF 1

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ji i

Each on-duty shift shall be composed of at least the minimum shi a.

crew composition shown in Table 6.2-1; l

i b.

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

at least one licensed Senior Operator shall be l

2, 3, or 4 control roo,m; l

c.

A Health Physics Technician

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

All CORE ALTERATIONS shall be observed and directly ' supervis{

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t either a licensed Senior Operator or licensed Senior Operator Limited to Fuel Handling who has no other concurrent responsibilities during this operation; and i

Administrative procedures shall be developed and implemented to e.

limit the workin functions, e.g.,g hours of station staff who perform safety-related i

licensed Senior Operators, licensed,0perators, i

health physicists, auxiliary operators, and key maint' nance e

personnel.

The amount of overtime worked by station staff members performing safety-related functions shall be limited in accordance i

i with the NRC Policy Statement on working hours (Generic Letter No.

l 82-12).

l

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f.

The Operations Manager shall have held a Senior Reactor Operator L

license for Seabrook Station prior to assuming the Operations Manager position.

1 l

The Assistant Operations Manager shall hold a senior reactor g.

operator license.

1 l

1 l

• The Health Physics Technician 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.

SEABROOK - UNIT 1 6-1 Amendment No. 20 l

h?R 2 61993

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I 1

e l

l I

L 1

I L

i f

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FIGURES 6.2-1 and 6 2-2 are not used.

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I SEABR00g UNIT 1 i

6-3 l

m____________________

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j

TABtF & 7-1 MfNTMLN EHfFT CREW COMPDMITION '

U POSITION NUMBER OF INDIVIDUALS REQUIRED TO FILL POSITION MODE 1. 2. 3. or 4 MODE 5 or 6 I

3gu.c 3

3 g

SR0"'

1 None R0 2

1 NSO STA 2"'

1

[

i 1

None SM Shift Manager with a Senior Operator license on Unit 1 SRO -

Individual with a Senior Operator license on Unit.1

.l RO -

Individual with an Operator license on Unit 1 NSO -

Nuclear Systems Operator STA - Shift Technical Advisor TAB 1F NOTATIONS (1)

The shift crew composition may be one less than the minimum requirements of Table 6.2-1 for a period of time not to exceed 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> in order to accommodate unexpected absence of on-duty shift crew members provided l

imediate action is taken to restore the-shift crew composition to within the minimum requirements of Table 6.2-1.

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

l l

(2)

Durin a absence of the Shift Manager from the control room while the l

unit s MODE 1. 2. 3. or 4. an individual with a valid Senior Operator license shall be designated to assume the control room comand function.

l During any absence of the Shift Manager from the control room while the

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unit is in MODE 5 or 6. an individual with a valid Senior 0)erator license or Operator license shall be designated to assume t w control l

room comand function.

(3)

The STA position shall be manned in MODES 1, 2. 3. and 4 unless the Shift Manager or the individual with a Senior Operator license meets the l

qualifications for the STA as required by the NRC.

l (4)

While the unit is in MODE 1. 2. 3 or 4. a licensed s either the SM or SRO. shall be on shift having had at leas ths of I

hot operating experience.

SEABROOK - UNIT 1 6-4 Amendment No.55

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ADMINISTRATIVE CONTROLS

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6.2.3 INDEPENDENT TECHNICAL REVIEWS A Technical Review Pr ran shall be established,t lamented and maintained to encompass the followin Technical Review respons ities.

FUNCIl0N 6.2.3.1 The Technical Review Program responsibilities shall encompass:

a.

NRC issuances industry advisories sourcesthatmayIndicateareasforimp,rovingplantsafety; Licensee Event Re b.

indicate areas for improving plant safety; Internal and external l

plant operating characteristics c.

maintenanceandsurveillancetoverl lant operations i

lhatthesemodifications, l

activities are performed safel independent 1 reduced as much as practical, y and correctly and t at human errors are and d.

Making detailed recommendations to the Senior Site Official for i

procedure revisions nuclear safety and p,lant reliability. equipment modifications or other means l

The Technical Review Program shall utilize several on-site personnel who are independent of the plant management chain to perform the reviews.

i RECORDS

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6.2.3.2 Written records of technical reviews shall be maintained.

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minimum these records shall include the results of the activities conducted, As a the status of recommendations made oursuant to Specification 6.2.3.1 and an assessment of compan;r operations related to the reviews performed.

the month 1r Technica A copy of Site Official.

Review Program report shall be provided to the Senior QUALIFICATIONS 6.2.3.3 Personnel performing reviews pursuant to Technical Specification 6.2.3.1 shall have either a bachelor's degree in engineering or related science and at least 2 years professional level experience at least 1 year of which shall be in the nuclear field orequivalenteducalionandexperienceas defined in ANSI /ANS 3.1, 1981,, Section 4.1.

6.2.4 SHIFT TECHNICAL ADVitot 6.2.4.1 to the Control Room Comander in the areas of thermal hydraulicsThe l

nearing, and plant analysis with regard to the safe operation of,the station. reactor engi-6.3 TRAINING 6.3.1 A retraining and replacement licensed training program for the station staff shall be maintained under the direction of the Trainin Manager and shall meet or exceed the requirements and recommendations of Secti n 5.5 of ANSI N18.1 1971 and the supplemental requin.aents specified in NUREG-1021, and shall

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include familiarization with relevant industry operational experience.

I SEABROOK - UNIT 1 6-5 Amendment No. 35 t

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l ADMINTSTRATIVF CONTROL 4

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RFRPONSIBilITIFR 6.4.1.6 The 50RC shall be responsible for:

a.

Review of:

(1) all proposed procedures required by Specification 6.7 and changes thereto (2 all proposed programs required by Specification 6.7 and change)s thereto. and (3) any other prop procedures or changes thereto as determined by the Station Director l

t to affect nuclear safet Specification 6.7 that y.

Procedures and programs required by Station Qualified Reviewer Program in accordance with Specifi 6.4.2 do not require 50RC review.

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t b.

Review of all proposed tests and experiments.that af.fect nuclear safety:

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Review of all proposed changes to Appendix "A" Technical c.

Specifications:

d.

Review of all proposed changes or modifications to station systems 1

or equipment that affect nuclear safety; Investigation of all violations of the Technical Specifications..

e.

including the preparation and forwarding of reports covering evalua-l tion and recommendations to prevent recurrence, to the Executive Vice President & Chief Nuclear officer and to the Nuclear Safety Audit Review Committee (NSARC):

f.

Review of all REPORTABLE EVENTS:

g.

Review of station operations to detect potential hazards to nuclear safety:

h.

Performance of special reviews investigations. or analyses and reports thereon as requested by the Station Director or the NSARC:

l L

1.

Not used:

1 j.

Not used:

k.

Review of any accidental, unplanned, or uncontrolled radioactive release includin l

recommendations,g the preparation of reports covering evaluation.

and disposition of the corrective action to prevent recurrence and the forwarding of these re> orts to the Executive Vice President & Chief Nuclear Officer and to the NSARC:

1.

Review of changes to the PROCESS CONTROL PROGRAM OFFSITE DOSE CALCULATION MANUAL, and the Radwaste Treatment System; and Review of the Fire Protection Program and implementing instructions m.

and submittal of recomended Fire Protection Program changes to the NSARC.

SEABROOK - UNIT 1,

6-7 Amendment No. 34. 39.55 7

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l ADMINISTRATIVE CONTROLS 6.4.1.7 The 50RC shall:

Recomend in writing to the Station Director approval or disapproval a.

of items considered under Specification 6.4.1.6a. through d:

b.

Render determinations-in writing with regard to whether or not each item considered under Specification 6.4.1.6a. through e. constitutes an unreviewed safety question; and 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 Executive Vice c.

President & Chief Nuclear Officer and the NSARC of disagreement between the SORC and the Station Director however, the Station Director shall have responsibility for resolution of such disagreements pursuant to Specification 6.1.1.

RECORDS 6.4.1.8 The 50RC shall maintain written minutes of each SORC meeting that, at a minimum, document the results of all 50RC activities performed under the responsibility provisions of these Technical Specifications. Copies shall be provided to the Executive Vice President & Chief Nuclear Officer and the NSARC.

6.4.2 STATION OUALIFIED REVIEWFR PROGRAM l

FUNCTION 6.4.2.1 The Station Director may establish a Station Qualified Reviewer Program l

whereby required reviews of designated procedures or classes of procedures required by S> edification 6.4.1.6.a are performed by Station Qualified Reviewers and approved )y the designated department heads. These reviews are in lieu of l

reviews by the 50RC. However, procedures which require a 10 CFR 50.59 evaluation must be reviewed by the 50RC.

RESPONSIBILITIES 6.4.2.2-The Station Qualified Reviewer Program shall:

t Provide for t'he review of designated procedures, programs, and a.

changes thereto by a Qualified Reviewer (s) other than the individual who prepared the procedure, program, or change.

b.

Provide for cross-disciplinary review of procedures, programs, and changes thereto when organizations other than the preparing organization are affected by the procedure, program, or change.

c.

Ensure cross-disciplinary reviews are performed by a Qualified Reviewer (s) in affected disciplines, or by other persons designated l

by cognizant department heads as having specific expertise required to assess a particular procedure, program or change. Cross-disciplinary reviewers may function as a comittee.

SEABROOK - UNIT 1 6-8 Amendment No. 34,55

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d.

Provide for a screening of designated procedures, programs and changes thereto to determine if an evaluation should be performed in accordance with the provisions of 10 CFR 50.59 to verify that an unreviewed safety question does not exist. This screening will be

>erformed by personnel trained and qualified in performing 10 CFR 30.59 evaluations.

Provide for written recommendation by the Qualified Reviewer (s) to e.

the responsible department head for approval or disapproval of a

procedures and programs considered under Specification 6.4.1.6a and I

that the procedure or program was screened by a qualified individual and found not to require a 10 CFR 50.59 evaluation.

l 6.4.2.3 If the responsible departmeht head determines that a new orogram, procedure, or change thereto requires a 10 CFR 50.59 evaluation.'that designated department head will ensure the required evaluation is performed to determine if the new procedure, The new procedure, program, or change involves an unreviewed safety question.

l program. or change will then be forwarded with the 10 CFR 50.59 evaluation to 50RC for review.

6.4.2.4 Personne1' recomended to be Station Qualified Reviewers shall be designated in writing by the Station Director for each procedure. program. or l

class of procedure or program within the scope of the Station Qualified Reviewer Program.

6.4.2.5 Temporary procedure changes shall be made in accordance with Specification 6.7.3 with the exception that changes to procedures for which reviews are assigned to Qualified Reviewers will be reviewed and approved as described in Specification 6.4.2.2.

1 EECQBDS 6.4.2.6 The review of procedures and programs performed under the Station Qualified Reviewer Program shall be documented in accordance with administrative procedures.

TRAINING AND QUALIFICATION 6.4.2.7 The training and qualification requirements of personnel designated as a Qualified Reviewer in accordance with the Station Qualified Reviewer Program shall be in accordance with administrative procedures. Qualified reviewers shall have:

a.

A Bachelors degree in engineering, related science, or technical discipline. and two years of nuclear power plant experience:

OR b.

Six years of nuclear power plant experience:

OR i

Anegesignateddepartmenthead.uivalent combination of education j

c.

the SEABROOK - UNIT 1 6-8A Amendment No. 34. 55

C-ADMINTSTRATIVF COMTROI K 6 4 't NUClFAR RAFFTY AUDIT RFVfFW COMMITTFF (NSARC)

EuEnoti designated activities.6.4.3.1 The NSARC shall function to provide inde 4

President & Chief Nuclear Officer on those areas of resp Specifications 6.4.3.7 and 6.4.3.8.

COMPOSITION i

6.4.3.2 The NSARC shall be com>osed Chairman. Vice Chairman and mem>ers, of at least five (5) individuals. The appointed in writing by the Executive Vice President & Chief Nucl Collectively, the individuals appoi expertise in the following areas: nted to the NSARC should have experience and l

i i

Nuclear power plant o a.

Nuclear engineering, perations, b.

Chemistry and radiochemistry.

c.

d.

Metallurgy.

l Instrumentation and control.

l e.

f.

Radiological safety.

Mechanical and electrical en g.

Quality assurance practices.gineering, and h.

Each member shall meet the qualifications of ANSI 3.1-1978. Section 4.7.

AtTFRNATFS 6.4.3.3 All alternate members shall be appointed in writing by the Executive Vice President & Chief Nuclear Officer to serve on a temporary basis: howe l

no more than a minority shall participate as voting members in NSARC activities at any one time.

CONSULTANTS 6.4.3.4 Consultants shall be utilized as determined by the NSARC to provid expert advice to the NSARC.

MFFTING FRF00FNCY 6.4.3.5 The NSARC shall meet at least once per 6 months t 6 weeks.

DUQBLti 6.4.3.6 The quorum of the NSARC necessary for the performance of the NSARC review and audit functions of these Technical Specifications shall consist of the Chairman or Vice-Chairman and at least four NSARC members including alt nates.

No more than a minority of the quorum shall have line responsi))1lity for operation of the unit.

The Vice Cnairman, or his designated alternate, can participate as an NSARC member when the Chairman is in attendance.

SEABROOK - UNIT 1 6-8B Amendment No. 34.55 j

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ADMINISTRATIVE CONTR01%

AUDlIS 6.4.3.8 Audits of station activities shall be performed under the cognizance of the NSARC.

The audits shall be performed within the specified time interval with a maximum allowable extension not to exceed 25% of the specified interval provided the combined time interval for any three consecutive intervals shall not exceed 3.25 times the specified interval.

These audits shall encompass:

The conformance of station " operation to provisions contained within a.

the Technical Specifications and applicable license conditions at least once per 12 months:

b.

The performance. training, and qualifications of the entire station staff at least once per 12 months:

The results of actions taken to correct deficiencies occurring in c.

station equipment, structures, systems, or method of operation that affect nuclear safety. at least once per 6 months:

d.

The performance of activities required by the Operational Quality Assurance Program to meet the criteria of Appendix B. 10 CFR Part

50. at least once per 24 months:

The fire protection programmatic controls including the implementing e.

procedures at least once per 24 months by qualified licensee QA personnel:

f.

The fire protection equipment and program implementation at least once per 12 months utilizing either a qualified offsite licensee fire protection engineer or an outside independent fire protection consultant.

An outside independent fire protection consultant shall be used at least every third year:

The Radiological Environmental Monitoring Program and the results g.

thereof at least once per 12 months:

h.

The OFFSITE DOSE CALCULATION MANUAL and implementing procedures at least once per 24 months:

1.

The PROCESS CONTROL PROGRAM and implementing procedures for processing and packaging of radioactive wastes at least once per 24 months:

j.

The performance of activities required by the Quality Assurance Program for effluent and environmental monitoring at least once per 12 months:

k.

Not used:

1.

Not used; and Any other area of station operation considered appropriate by the m.

f NSARC or the Executive Vice President & Chief Nuclear Officer.

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SEABROOK - UNIT 1 6-10 Amendment No. 34. 39. 55

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ADMINISTRATIVE CONTR01%

RECGEi 6 5.3.9 Records of NSARC activities shall be prepared and distributed as indicated below:

Minutes of each NSARC meeting shall be prepared and forwarded to a.

Executive Vice President & Chief Nuclear Officer within 30 working days following each meeting:

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b.

Reports of reviews encompassed by Specification 6.4.3.7 shall be I

included in the minutes where applicable or forwarded under separate cover to the Executive Vice President & Chief Nuclear Officer within 30 working days following completion of the review; and i

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c.

~ Audit reports encompassed by Specification 6.4.2.8 shall be forwarded to the Executive vice President & Chief Nuclear Officer and to the management positions responsible for the areas audited l

within 30 days after completion of the audit by the auditing 1

organization.

6.5 RFPORTABLF EVENT ACTf0N The following actions shall be taken for REPORTABLE' EVENTS:

The Commission shall be notified and a re> ort submitted pursuant to a.

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

Each REPORTABLE EVENT shall be reviewed by the 50RC and the results l

of this review shall be submitted to the NSARC and the Executive Vice President & Chief Nuclear Officer.

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6 6 SAFFTY LIMIT VIOLATION i

The following actions shall be taken in the event a Safety Limit is 1

violated:

i The NRC Operations Center.shall be notified by telephone as soon as a.

possible and in all cases within I hour. The Executive Vice l

President & Chief Nuclear Officer and the NSARC shall be notified within 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />s:

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b.

A Safety Limit Violation Re> ort shall be prepared. The report shall l

be reviewed by the SORC. T11s report shall describe: (1) applicable l

circumstances preceding the violation. (2) effects of the violation i

upon facility components, systems, or structures, and (3) corrective action taken to prevent recurrence:

The Safety Limit Violation Report shall be submitted to the c.

Comission, the NSARC and the Executive Vice President & Chief Nuclear Officer within 14 days of the violation: and d.

0)eration of the station shall not be resumed until authorized by tie Commission.

SEABROOK - UNIT 1 6-11 Amendment No. 34.55 I

ADMINISTRATIVE CONTR0t%

6.7 PROCFDURFK AND PRnr, RAMS 6.7.1 Written procedures shall be established implemented, and maintained covering the activities referenced below:

The applicable procedures recommended in Appendix A of Regulatory l

a.

Guide 1.33. Revision 2. February 1978:

i b.

The emergency operatina procedures required to imslement the requirements of NUREG-1737 and Supplement I to NUREG-0737 as stated in Generic Letter No. 82-33:

l c.

Not used:

d.

Not used:

e.

PROCESS CONTROL PROGRAM implementation:

i f.

OFFSITE DOSE CALCULATION MANUAL 1 implementation:

g.

Quality Assurance Program for effluent and environmental monitoring; h.

Fire Protection Program implementation: and 1.

Technical Specification Improvement Program implementation.

6.7.2 The Station Director may designate specific procedures and prgrams or classes of procedures and programs to be reviehd in accordance with.he Station l

i Qualified Reviewer Program in lieu of review by the SORC. The review per the Qualified Reviewer Program shall be in accordance with Specification 6.4.2.

6.7.3 Procedures and programs listed in S> edification 6.7.1. and changes thereto, shall be a> proved by the Station )1 rector or by cognizant department head or Directors wie are designated as the Approval Authority by the Station Director, as specified in administrative procedures. The Approval Authority for each procedure and program or class of procedure and program shall be specified in administrative procedures.

6.7.4 Each procedure of S> edification 6.7.1, and changes thereto, shall be reviewed by the 50RC and s1all be approved by the Station Director, or be l

reviewed and approved in accordance with the Station Qualified Reviewer Program, prior to implementation.

Each procedure of Specification 6.7.1 shall be reviewed periodically as set forth in administrative procedures.

i 6.7.5 Chances to procedures of Specification 6.7.1 may be made prior to SORC review provided:

a.

The intent of the original procedure is not altered:

b.

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

The change is documented, reviewed by the SORC and approved by the Station Director. or reviewed and a Station Qualified Reviwer Program,pproved in accordance with the l

within 14 days of implementation.

SEABROOK - UNIT 1 6-12 Amendment No. 34. 39.55

ADMINISTRATE W CONTROtt HIGH RADIATION AREA 6.11.1 (Continued) radiation areas. Any individual or group of individuals permitted to enter such areas shall be provided with or accompanied by one or more of the following:

A radiation monitoring device that continuously indicates the a.

radiation dose rate in the area: or b.

A radiation monitoring device that 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 l

established and personnel have been made knowledgeable of them: or An individual qualified in radiation protection procedures with a c.

radiation dose rate monitoring device, who is responsible for providing positive control over the activities within the area and shall perform )eriodic radiation surveillance at the frequ'

.y l

specified in t1e Radiation Work Permit.

6.11.2 In addition to the requirements of Specification 6.11.1. areas accessible to personnel with radiation levels greater than 1000 mR/h at 45 cm (18 in.) from the radiation source or from any surface that the radiation penetrates shall be provided with locked doors to prevent unauthorized entry, and the keys shall be maintained under the administrative control of the Shift Manager on duty and/or health physics supervision. Doors shall remain locked 1

i except during periods of access by personnel under an approved RWP that shall i

specify the dose rate levels in the immediate work areas and the maximum allowable stay time for individuals in that area.

In lieu of the stay time specification of the RWP l

continuous surveillance m. direct or remote (such as closed circuit TV camer ay be made by personnel qualified in radiation arotection procedures to provide

.>eing performed within the area. positive exposure control over the activities For individual high radiation areas accessible to personnel with radiation i

l levels of greater than 1000 mR/h that are located within large areas. such as l

PWR containment, where no enclosure exists for purposes of locking and where no i

enclosure can be reasonably constructed around the individual area, that individual area shall be barricaded. conspicuously posted, and a flashing light shall be activated as a warning device.

6 12 PROCFSS CONTROL PROGRAM (PCP) l 6.12.1 The PCP shall be approved by the Commission prior to implementation.

6.12.2 Licensee-initiated changes to the PCP:

l Shall be submitted to the Comission in the Annual Radioactive a.

Effluent Release Report for the period in which the change (s) was made.

This submittal shall contain:

SEABROOK - UNIT 1 6-21 Amendment No. 33.55

ADMINISTRATIVE CONTROLS

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PROCESS CONTROL PROGRAN (PCP) 6.12.2 (Continued) l 1) sufficiently detailed information to totally support the rationale for the change without benefit of additional or i

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)

supplemental information; 2)

A determination that the change did not reduce the overall conformance of the solidified waste product to existin5 criteria for solid wastes; and i

3)

Documentation of the fact that the' change has been reviewed

~

and found acceptable by the 50RC.

b.

Shall become effective upon review and acceptance by the 50RC.

6.13 0FFSITE DOSE CALCULATION MANUAL (ODCN) 6.13.1 The OCDM shall be approved by the Commission prior to implementation.

I 6.13.2 Licensee-initiated changes to the ODCM:

Changes to Part A shall be submitted to and approved by the NRC a.

staff prior to implementation.

b.

Changes to Part 5 shall be submitted to the Commission in the Anni::1 Radioactive Effluent Release Report for the period in which j

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 supplemental information.

Information submitted should consist of a package of those pages of the 00CM to be changed with each page numbered, dated and containing the revision number, together with ap justifyingthechange(s)propriateanalysesorevaluations 2)

A determination that the change will not reduce the accuracy or reliability of dose calculations or Setpoint determinations; and 3)

Documentation of the fact that the change has been reviewed and found acceptable by the 50RC.

Changes to Part 8 shall become effective upon review and acceptance c.

by the 50RC.

s

)

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