Text

Proposed Tech Specs 6.0 Re Administrative Controls
	ML20134L868
Person / Time
Site:	Seabrook
Issue date:	02/12/1997
From:	; NORTH ATLANTIC ENERGY SERVICE CORP. (NAESCO)
To:	;
Shared Package
ML20134L862	List: ML20134L859; ML20134L868;
References
	NUDOCS 9702190325
	Download: ML20134L868 (25)
	v • d • e

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i 6.0 ADMINISTRATIVE CONTROLS 6.1 RESPONSIBILITY l

' D % d-o-6.1.1 The Station m s.all be responsible for overall station opera-tion and during his absenc shall delegate in writing the succession to this responsibility

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6.1. 2 i

The Shift 5; g ri nf:nden.-(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 Ex;;uti;;

=0irector-N annual basis 10:r Pret A tien shall be reissue to all station personnel 6.2 ORGANIZATION Ex e c.vT t V E. h tte res 5eF G J M~ N" I

6.2.1 0FFSITE AND ONSITE ORGANIZATIONS Onsite and offsite organizations shall be established for unit operation and corporate management, respectively. The onsite and offsite organizations shall include plant. the positions for activities affecting the safety of the nuclear power a.

Lines of authority, responsibility, and communication shall be established and defined for the highest management levels through intermediate levels to and including all operating organization 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 forms of documentation. These requirements shall be documented in the FSAR and update i ance with the requirements of 10 CFR 50.71.

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b. The Station ... 4,tkov- f , all be responsible for overall unit safe operation and shall have control over those onsite activities necessary for safe operation and maintenance of the plaat.

c.

The ex;;;ti;; Oir::t:r - "ucl::r Pre i:ti:r shall have corporate responsibility for overall plant nuclear safety and shall take any measures needed to ensure acceptable performance of the staff in operating, maintaining, and providing technical support to the plant to ensure nuclear safety.

d.

The individuals'who train the operating staff and those who carry out health physics and quality assurance functions may report to the appropriate onsite manager; however, they shall have sufficient organizational pressures. freedom to ensure their independence from operating SEABROOK - UNIT 1 6-1 .

9702190325 970212 PDR ADOCK 05000443 p PDR

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TABLE 6.2-1 MINIMUM SHIFT CREW COMPOSITION (1) l j i 5-POSITION NUMBER OF INDIVIOUALS REQUIRED TO FILL POSITION i

MODE 1, 2, 3, or 4 MODE 5 or 6 j

l S g2,4)- 1 1 i SR0(4) 1 None '

R0 2 1 l l PIM -te- 2 1 STA

3) None

+ Shift 4 ..t3 L.....".3 *S J... with a Senior Operator license on Unit 1 O5 SRO Individual with a Senior Operator license on Unit 1

_ RO Individual with an Ope ator W =ne_-sn-Un l u so - AO- -

-Atrxiliary Op;r t:r uc)w ks+ew O pwadow-

STA -

Shift Technical Advisor 4

TABLE NOTATIONS i

(1) The shift crew composition may be one less than the minimum requirements l of Table 6.2-1 for a period of time not to exceed 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months in order to

accommodate unexpected absence of on-duty shift crew members provided 2 immediate action is taken to restore the shift crew composition to within ,

i the minimum requirements of Table 6.2-1. This provision does not permit l l any shift crew position to be unmanned upon shi a ue to an oncoming l shif fr: nnae' late or absent. FMPA GER.

cr e w puse o (2) During of the Shift " ;;r' t;n_p t from t e control room while the unit is in MODE 1, 2, 3. or 4, an individual wit h a valid Senior )

Operatorlicenseshallbedesignatedtoassumethe@ntrolroomcommand I i function. During any absence of the Shift S;;r' t: d: t from the control room while the unit is in MODE 5 or 6, an individual with a valid Senior '

Operator license or Operator license shall be designated to assume the control room command function.

. 3) Tne STA position shall be manned in MODES 1, 2, 3, and 4 unless the Shift j

w a as.o ";7:rint: d::t or the individual with a Senior Operator license meets the j

qualifications for the STA as required by the NRC.

j (4) While the unit is in MODE 1, 2, 3 or 4, a licensed senior operator, either j i the r SRO, shall be on shift having had at least 6 months of hot operat-i ing experience.

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1 i g 6-4 SEABROOK - UNIT 1 i l(c87 cp l

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ADMINISTRATIVE CONTROLS j _ !

i 6.4 REVIEW AND AUDIT i 6,4.1 STATION OPERATION REVIEW COMITTEE (SORC) i FUNCTION

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! 6.4.1.1 T'he 50RC shall function to advise the Station "x:;;. on all matters

related to nucletr safety.

COMPOSITION 6.4.1.2 The 50RC shall, as a minimum, be composed of the Chairman"and n1ne

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l individuals who collectively have experience and expertise in the following areas:

i Nuclear Power Plant Administrative Controls Mechanical Maintenance l Electrical Maintenance -

Instrumentation & Control l Chemistry '

Health Physics

! Operations ;

} Technical Support / Engineering i

! ering '

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The Station i..;; r hall serve as Chairman of the S0RC and shall appoint the 4

SORC members in writing. Members shall have a minimum of eight years power plant experience of which a minimum of three years shall be nuclear power experience. At least one member shall have an SRO license for Seabrook Station.

j ALTERNATES -

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6.4.1.3 All alternate members shall be appointed in writing by the 50R0 i Chairman to serve on a temporary basis and shall have qualifications equivalent j to those of the members.

J MEETING FREOUENCY 4

i 6.4.1.4 The 50RC shall meet at least once per calendar month and as convened j by the 50RC Chairman or one of his designated alternate (s). l M .

l 6.4.1.5 The quorum of the.SORC necessary for the performance of the SORC

responsibility and authority provisions of these Technical Specifications shall

consist of the Chairman or one of his designated alternate (s) and sufficient SORC members including alternates to equal at least 50 percent of the SORC composition.

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{ SEABROOK - UNIT 1 6-6 Amendment No. 34

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1 ADMiNISTRATIVECONTROLS i

RESPONSIBILITIES 6.4.1.6 The SORC shall be responsible for:

l i 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 changes thereto, and (3) any other proposed procedures or changes thereto as determined by the Station l to affect nuclear safety. Procedures and programs required by hedo v-Specification 6.7 that are designated for review and approval b the Station Qualified Reviewer Program in accordance with

, Specif'ication 6.4.2 do not require SORC review.

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

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

d. Review of all proposed changes or modifications to station systems i or equipment that affect nuclear safety; p

l e. Investigation of all violations of the Technical Specifications, including the preparation and forwarding of reports covering evaluation and recommendations to prevent recurrence, to the r

E= = tin Oirnt:r "::10:r ?r:f::ti= and to the Nuclear Safety

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Audit Review Committee (NSARC);

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f. Review of all REPORTABLE EVENTS;

, g. Review of station operations to detec't potential hazards to nuclear safety; j

te.echor t h. Performance of special reviews, investigation , Jr'ana yses and reports thereon as requested by the Station ":=;;r or the NSARC; E. uch v e Oct l'

k. Review of any accidental, unplanned, or uncontrolled radioactive release including the preparation of reports covering evaluation, 5

recommendations, and disposition of the corrective action to i

prevent recurrence and the forwarding of these reports to the

- Re s tive Oirnter "ninr "rdntin-and to the NSARC; i 1- Review of changes to the PROCESS CONTROL PROGRAM, OFFSITE DOSE

] CALCULATION MANUAL, and the Radwaste Treatment System; and

! m. Review of the Fire Protection Program and implementing instructions and submittal of recommended Fire Protection Program changes to the NSARC.

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! SEABROOK - UNIT 1 6-7 Amendment No. 39 4

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l ADMINfSTRATIVE CONTROLS i

1 6.4.1.7 The 50RC shall:

, a. Recommend in writing to the Station M:::;i4:r approval or disapproval l '

4 j i t of items considered under Specification 6.4.1.6a. through d; l i

b. . Render determinations in writing with regard to whether or not each j

item considered under Specification 6.4.1.6a. through constitutes an unreviewed safety question; and b ec b r.

! c.

' Provide written notification within 2 ours to the -~ 'iu-

"ireet;.7 "d::7 "r:f::th: and NSARC of disagre t between t

he S0RC and the Station 57.:;:r ..:-ever, the Statioh shall have responsibility for resolution of such disagreements pursuant

! to S ect cat i

RECORDS M C h t O r-e h u S k

j 6.4.1.8 The 50RC shall maintain written minutes of each SORC meeting that, at i a minimum, document the results of all SORC activities perfomed under the i

i responsibility provided to the provisigd E :::t.;;ofSir::ter these Technical S

" &:r " pecifications. Copies shall be ,

F f :ti:: and the NSARC. l 6.4.2 STATION OUALIFIED REVIEWER PROGRAM

! FUNCTION i ^3We c.by-

!, i 6.4.2.1 The Station Managee-eay establish a Station Qualified Reviewer Program whereby required reviews of designated procedures or classer of procedures required by Specification 6.4.1.6.a are performed by Station Qualified Reviewers and approved b n n. These reviews are in lieu of l i reviews by the SORC. designated ver, procedure. hw:hich require a 10 CFR 50.59 j i evaluation must be re i d by the i

RESPONSIBILITIES *M

6.4.2.2 The Station Qualified Reviewer Program shall:

a. Provide for the review of designated procedures, programs, and 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 by cognizant M::: n Or Of =:t:= :s having specific expertise required to asses a particular procedure, program or change.

Cross-discip tion as a committee.

CNQah M & a.b5 SEABROOK - UNIT 1 6-8 Amendment No. 34

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1 j ADMINISTRATIVE CONTROLS l d. Provide for a screening of designated procedures, programs and I

j changes thereto to determine if an evaluation should be performed in accordance with the provisions of 10 CFR 50.59 to verify that an 4

unreviewed safety question does not exist. This screening will be i

performed by personnel trained and qualified in performing 10 CFR i . 50.59 evaluations,

e. _ Provide for written recommendation by the Qualified Reviewer (s) to ge9Aej ( ,[ and ,theprograms responsibMx:;;r for Specification considered under procedure or program was screened by a qualified approval 6.4.1.6a or disapproval and that the of procedu found not to require a 10 CFR 50.59 evaluatio( g5,Q )

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! 6.4.2.3 If the responsibli r : r determines that a new '

, . aedure, j or change thereto requires a 10 EFR 50.5g evaluation, tha . x ;. will ensure e

the required evaluation is performed te determine if the new pro;cedure, program, or change involves an unreviewed safety question. Tw new procedure, program, or change will then be forwarded with the 10 CFR 50.59 evaluation to -

50RC for review. r 2

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6.4.2.4 Personnel recommended to be Qualified Reviewers shall be

! designated in writing by the Station for each procedure, program, or

class of procedure or program within the scope of the Station Qualified -

2 Reviewer Program.

! 6.4.2.5 Temporary procedure changes shall be made in accordance with j 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.

6.4.2.6 The review of procedures and programs perfomed under the Station d

Qualified Reviewer Program shall be documented in accordance with -

administrative procedures.

TRAINING ABC OUALIFICATION

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 nuc' ear power plant experience; OR

b. Six years of nuclear power plant experience; OR i c. An equivalent combination of education and experience as approved

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SEABROOK - UNIT 1 Amendment No. 34

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ADMINISTRATIVE CONTROLS 4

6.4.3 NUCLEAR SAFETY AUDIT REVIEW C009tITTEE (NSARC) I j FUNCTION i

6.4.3.1 The NSARC shall function to provide independent review and audit of designate'd activities. The NSARC shall report to and advise the ::;ier "te: I 4

"r::id::t on those areas of responsibility specified in Specifications 6.4.3.7 i

and 6.4.3.8.

COMPOSITION l 6.4.3.2 The NSARC shall be composed of at least five (5) individuals. The i Chairman, Vice Chairman and members, including designated alternates, shall be i appointed in writing by the '- '- "'- - -"--' Collectively, the

individuals appointed to the NSARC should hav xperience and expertise in the following areas

a. Nuclear power plant operations, k

b. Nuclear engineering, C b 4 kLdew 09f ae c.

d.

Chemistry and radiochemistry, Metallurgy,

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e. Instrumentation and control,

f. Radiological safety,

g. Mechanical and electrical engineering, and '

h. Quality assurance practices.

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

ALTERNATES 6.4.3.3 All alternate members shall be appointed in writing by the :;icr "te: l l'r :id::t to serve on a temporary basis; however, no more than a minority shall participate as voting members in NSARC activities at any one time.

C.QNSMLTANIS 6.4.3.4 Consultants shall be utilized as determined by the NSARC to provide l expert advice to the NSARC.

i NEETING FREQUENCY 6.4.3.5 The NSARC shall meet at least once per 6 months

6 weeks. l 000RLM 6.4.3.6 The quorum of the NSARC necessary for the performance of the NSARC l review and audit functions of these Technical Specifications shall consist of the Chairman or Vice-Chairman and at least four NSARC members including alter-nates. No more than a minority of the quorum shall have line responsibility for operation of the unit. The Vice Chairman, or his designated alternate, can participate as an NSARC member when the Chairman is in attendance.

SEABROOK - UNIT 1 6-8B Amendment No. 34

!. ADMINISTRATIVE CONTROLS 1

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! AUDITS i

! 6.4.3.8 Audits of station activities shall be performed under the cognizance i 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 i provided the combined time interval for any three consecutive intervals shall j

not exceed 3.25 times the specified interval. These audits shall encompass:

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a. The conformance of station 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 station

staff at least once per 12 months;

! c. The results of actions taken to correct deficiencies occurring in station equipment, structures, systems, or method of operation that affect nuclear safety, at least once per 6 months; i

l d. The performance of activities required by the Operational Quality l Assurance Program to meet the criteria of Appendix B,10 CFR Part l 50, at least once per 24 months; i e. The fire protection programmatic controls including the l implementing procedures at least once per 24 months by qualified licensee QA personnel;

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

. consultant. An outside independent fire protection consultant

shall be used at least every third year; l g. The Radiological Environmental Monitoring Program and the results j thereof at least once per 12 months; i

h. The OFFSITE DOSE CALCULATION MANUAL and implementing procedures at j least once per 24 months;

i. The PROCESS CONTROL PROGRAM and implementing procedures for processing and packaging of radioective wastes at least once per 24 months; l

'j. The perfomance of activities required by the Quality Assurance

{ Program for effluent and environmental monitoring at least once per

. 12 months; I k. Not used; I i

1. Not used; and i m. Any other area of station operation considered appropriate by the NSARC or th g;ippf( _

oc k ev-SEABROOK - UNIT 1 6-10 Amendment No. 39

ADMINISTRATIVE CONTROLS RECORDS 6.4.3.9 Records of NSARC activities shall be prepared and distributed as indicated below: l

__ jt._ Minutes of each NSARC meeting shall be prepared and forwarded to we S: i:r Yi:: "r::!d::t within 30 working days following each l meeting; 6.4

b. Reports of reviews encompassed by Specificatio . 4.2.7 shall be included in the minutes where applicable or forwarded under sepa-rate cover to the Stier Yi:: "r::!d: t within 30 working days l following complefion of the review; and 1 l

c. Audit reportshncompassed by Specification 6.4.2.8 shall be forwarded to the S ter Yi:: "r::!d::t and to the management I positions responsible for the areas audited within 30 days after l Q completion of the yditina oraanizatio j Q' ,),y, d C Lief M uc W l

6.5 REPORTABLE EVENT ACTION 7 Udd d .

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] The following actions shall be taken for REPORTABLE EVENTS:

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

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

~ of this review shall be submitted to the NSARC and the S :;th:

d irecter Mu & r "r d etten.

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

a. The NRC Operations Center shall be notified by telephone as soon as possible and in all cases within I hour. The S:::th: Otr::t:r

gelear or 9: tb and the NSARC shall be notified within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months ;

b. A Safety Limit Violation Report shall be prepared. The report

, shall be reviewed by the 50RC. This report shall describe:

(1) applicable circumstances preceding the violation, (2) effects of the violation upon facility components, systems, or structures, and (3) corrective action taken to prevent recurrence; i c. The Safety Limit Violation Report shall be submitted to the

, Commission, the NSARC, and the S::eth: Directer-Me&ar e "r d :ti:n within 14 days of the violation; and

, d. Operation of the station shall not be resumed until authorized by the Commission.

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3 C e v-SEABROOK - UNIT 1 6-11 Amendment No. 34 i

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3 ADMINISTRATIVE CONTROLS !

6.7 PROCEDURES AND PROGRAMS 6.7.1 Written procedures shall be established, implemented, and maintained 1 covering the activities referenced below:

a. The applicable procedures recommended in Appendix A of Regulatory Guide 1.33, Revision 2, February 1978; b.

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

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c. Not used; i

d. Not used;

j e. PROCESS CONTROL PROGRAM implementation;

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f. OFFSITE DOSE CALCULATION MANUAL implementation; j- g. Quality Assurance Program for effluent and environmental j monitoring; j h. Fire Protection Program implementation; and 4

j i. Technica,L-Spec cation Improvement Program implementation. ,

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! 6.7.2 The Station ay designate specific procedures and programs or f

classes of procedures and programs to be reviewed in accordance with the

! Station Qualified Reviewer Program in lieu of review by the SORC. The review __

per the Qualified Reviewer Program shall be in accordance with Sp 1 6.4.2. ecsAme).kea.

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i 6.7.3 Prrecdures and programs listed in Specifi on 6.7.1, and change thereto, : hall be approved by the Station by cognizant or

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heckcr l Directors as specified who are designated in administrative as the Approval procedures. Authority The Approval by the for Authority Station eac t :F j procedure and program or class of procedure and program shall be specified in administrative procedures.

) 6.7.4 Each procedure of Specification 6.7.1.. and changes thereto shall be l

' reviewed reviewed by andthe SORC and approved shall be approved in accordance with thet,yStdion the Station Qualified $=; Reviewer;., or be i Program, prior to implementation. Each procedure of Specification 6.7.1 shall j be reviewed periodically as set forth in administrative procedures.

i 6.7.5 Changes to procedures of Specification 6.7.1 may be made prior to SORC l

review prov'ded: I 1 l j a. The intent of the original procedure is not citered, j j b. The change is approved by two members of the plant management !

,4 staff, at ler.st one of whom holds a Senior Operator license; and l n4 The change is documented, reviewed by the SORC and approved by the .

l StatiortJ4enagee, or reviewed and approved in accordance with the C,W*D w M c,< > Qual fled Reviewer Program, within 14 days of station implementation.

SEABROOK - UNIT 1 6-12 Amendment No. 39 I

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j ADMINISTRATIVE CONTROLS 1

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{ 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. A radiation monitoring device that continuously indicates the radiation dose rate in the area; or !

l i- b.

- A radiation monitoring device that continuously integrates the ;

j 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 ote levels in the area have been

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established and personnel have been made knowledgeable of them; or ;

c. An individual qualified in radiation protection procedures with'a i:

radiation dose rate monitoring device, who is responsible for providing positive control over the activities with*n the area and ;

3 shall perform periodic radiation surveillance at the frequency specified in the Radiation Work Permit.

! 6.11.2 In addition to the requirements of specification 6.11.1, areas i- 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 '

i penetrates shall be provided with locked doors to prevent unauthorized entry, and the keys shall be maintained under the administrative control of the Shift 3 t

gese ':;; t t::f::t on duty and/or health physics supervision. Doors shall remain t

locked except during periods of access by personnel under an approved RWP that -

shall 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, direct or remote (such as closed circuit TV cameras) i continuous surveillance may be made by personnel qualified in radiation protection procedures to provide positive exposure control over the activities being performed within the area.

For individual high radiation areas accessible to personnel with [

radiation levels of greater than 1000 mR/h that are located withic large areas, ;

such as PWR containment, where no enclosure exists for purposes H locking, and where no 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 PROCESS CONTROL PROGRAM (PCP) 6.12.1 The PCP shall be approved by the Commission prior to implementation.

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6.12.2 Licensee-initiated changes to the PCP:

a. Shall be submitted to the Commission in the Annual Radioactive Effluent Release Report for the period in which the change (s) was l made. This submittal shall contain:

SEABROOK - UNIT 1 6-21 Amendment No. 22

c, .

SECTION III .

RETYPE OF PROPOSED CIIANGES i

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6.0 ADMINISTRATIVE CONTROLS !

E l. RESPONSIBILITY 6.1.1 The Station Director shall be responsible for overall station operation l and shall delegate in writing the succession to this responsibility during his absence.

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

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

an annual basis. ,

6.2 ORGANIZATION 6.2.1 0FFSITE AND ONSITE ORGANIZATIONS Onsite and offsite organizations shall be established for unit operation and i corporate management, respectively. The onsite and offsite organizations shall l include the positions for' activities affecting the safety of the nuclear power l plant. j 1

a. Lines of authority, responsibility, and communication shall be ;

established and defined for the highest management levels through l intermediate levels to and including all operating organization 1 positions. These relationships shall be documented and updated, as '

I appropriate, in the form of organization charts, functional i descri)tions for departmental responsibilities and relationships, !

and jo) descriptions for key personnel positions, or in equivalent forms of documentation. These requirements shall be documented in the FSAR and updated in accordance with the requirements of 10 CFR ,

50.71. j

b. The Station Director shall be responsible for overall unit safe l l operation and shall have control over those onsite activities necessary for safe operation and maintenance of the plant.

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c. The Executive Vice President & Chief Nuclear Officer shall have l l corporate responsibility for overall plant nuclear safety and shall j take any measures needed to ensure acceptable performance of the ;

staff in operating, maintaining, and providing technical support to '

the plant to erisure nuclear safety. j

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. i i

i SEABROOK - UNIT 1 6-1 Amendment No.

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TABLE 6.2-l MINIMUM SHIFT CREW COMPOSITION

POSITION NUMBER OF INDIVIDUALS REQUIRED TO FILL POSITION l

MODE 1, 2. 3, or 4 MODE 5 or 6 1 l

SM*' 1 1 l SRO* 1 None R0 2 1 NSO STA 2*

1 1

None l

SM - Shift Manager with a Senior Operator license on Unit 1 l SRO - Individual with a Senior Operator license on Unit 1 R0 - Individual with an Operator license on Unit 1 NSO - Nuclear Systems Operator STA - Shift Technical Advisor !

TABLE 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 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months in order to accommodate unexpected absence of on-duty shift crew members provided immediate action is taken to restore the shift crew composition to within the minimum requirements of Table 6.2-1. 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 t

l (2) During any absence of the Shift Manager from the control room while the l l l unit is in MODE 1. 2, 3, or 4 an individual with a valid Senior Operator license shall be designated to assume the control room command function.

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

unit is in MODE 5 or 6 an individual with a valid Senior 0)erator '

license or Operator license shall be designated to assume tie control l room command 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.

(4) While the unit is in MODE 1. 2. 3 or 4 a licensed senior operator, either the SM or SRO. shall be on shift having had at least 6 months of I hot operating experience.

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SEABROOK - UNIT 1 6-4 Amendment No.

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! ' ADMINISTRATIVE CONTROLS i

i 6.4 REVIEW AND AUDIT-6.4.1 STATION OPERATION REVIEW COMMITTEE (SORC) j l FUNCTION I l

6.4.1.1 The SORC shall function to' advise the Station Director on all matters ;

related to nuclear safety. .;

i l COMPOSITION j 6.4;1.2 The SORC shall, as a minimum, be composed of the Chairman and nine !

individuals who collectively have experience and expertise in the'following i areas. ;

' i Nuclear Power Plant Administrative Controls !

Mechanical Maintenance Electrical Maintenance 1 Instrumentation & Centrol !

! Chemistry l

Health Physics ;

l Operations l l Technical Support / Engineering l Reactor Engineering j The Station Director shall serve as Chairman of the SORC and shall appoint the !

, SORC members in writing. Members shall have a minimum of eight years power !

i plant experience of which a minimum of three years shall be nuclear power i*

experience. At least one member shall have an SR0 license for Seabrook Station.

ALTERNATES ~

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6.4.1.3 All alternate members shall be appointed in writing by the SORC I Chairman to serve on a temporary basis and shall have qualifications equivalent i to those of the members.

MEETING FREQUENCY l

6.4.1.4 The SORC shall meet at least once per calendar month and as convened by the SORC Chairman or one of his designated alternate (s).

OUORUM 6.4.1.5 The quorum of the 50RC necessary for the performance of the SORC responsibility and authority provisions of these Technical Specifications shall consist of the Chairman or one of his designated alternate (s) and sufficient

SORC members including alternates to equal at least 50 percent of the SORC i

!. composition. !

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l SEABROOK - UNIT 1 6-6 Amendment No. 34 4

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ADMINISTRATIVE CONTROLS RESPONSIBILITIES 6.4.1.6 The SORC shall be responsible for:

a. Review of: (1) all proposed 6.7 and changes thereto. (2) procedures all proposedrequired programsbyrequiredSpecification by Specification 6.7 and changes thereto, and (3) any other proposed procedures or changes thereto as determined by the Station Di:'ector l to affect nuclear safety. Procedures and programs required by ,

Specification 6.7 that are designated for review and approval by the Station Qualified Reviewer Program in accordance with Specification 6.4.2 do not require SORC review.

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b. Review of all proposed tests and experiments that affect nuclear safety: <

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

d. Review of all 3roposed changes or modifications to station systems or equipment tlat affect nuclear safety:

l e. Investigation of all violations of the Technical Specifications. l l including the preparation and forwarding of reports covering evalua-l tion and recommendations to prevent recurrence, to the Executive l 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

i. Not used l j. Not used:

l k. Review of any accidental. unplanned, or uncontrolled radioactive i

release including the preparation of reports covering evaluation, recommendations, and disposition of the corrective action to prevent recurrence and the forwarding of these reports to the Executive Vice President & Chief Nuclear Officer and to the NSARC: ;

1. Review of changes to the PROCESS CONTROL PROGRAM OFFSITE DOSE I CALCULATION MANUAL. and the Radwaste Treatment System; and

m. Review of the Fire Protection Program and implementing instructions and submittal of recommended Fire Protection Program changes to the g NSARC.

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l SEABROOK - UNIT 1 6-7 Amendment No. 34. 39.

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ADMINISTRATIVE CONTROLS t

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~6.4.1.7 The SORC shall:

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a. Recommend in writing to the Station Director approval or disapproval i

[ of items considered under Specification 6.4.1.6a. through d: !

b. Render determinations in writing with regard to whether or not each !'

l item considered under Specification 6.4.1.6a. through e. constitutes l an unreviewed safety question; and l

c. Provide written notification within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months to the Executive Vice i President & Chief Nuclear Officer and the NSARC of disagreement 1 between the SORC and the' Station Director however, the Station i Director shall have responsibility for resolution of such I disagreements pursuant to Specification 6.1.1. ,

y RECORDS

! 6.4.1.8 The SORC shall maintain written minutes of each SORC meeting that, at a :

l minimum, document the results of all SORC activities performed under the (

l responsibility provisions of these Technical Specifications. Copies shall be i l

provided to the Executive Vice President & Chief Nuclear Officer and the NSARC. l l 6.4.2 STATION OUALIFIED REVIEWER PROGRAM l

FUNCTION !

I 6.4.2.1 The Station Director may establish a Station Qualified Reviewer Program l 1 whereby required reviews of designated procedures or classes of procedures

recuired by S)ecification 6.4.1.6.a are performed by Station Qualified Reviewers i anc approved 3y the designated department heads. These reviews are in lieu of l reviews by the SORC. However, procedures which require a 10 CFR 50.59 l evaluation must be reviewed by the SORC.

RESPONSIBILITIES i l 6.4.2.2 The Station Qualified Reviewer Program shall:

! R l a. Provide for the review of designated procedures, programs, and 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.

l c. Ensure cross-disciplinary reviews are performed by a Qualified

Reviewer (s) in affected disciplines, or by other persons designated

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

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i SEABROOK - UNIT 1 6-8 Amendment No. 34

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ADMINISTRATIVE CONTROLS l l

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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 performed by personnel trained and qualified in performing 10 CFR 50.59 evaluations. .

e. Provide for written recommendation by the Qualified Reviewer (s) to the responsible department head for approval or disapproval of l !

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.

i 6.4.2.3 If the responsible department head determines that a new arogram, procedure, or change thereto requires a 10 CFR 50.59 evaluation, tlat designated i department head will ensure the required evaluation is performed to determine if the new procedure, The new procedure, program, program, or change or change involves will then an unreviewed be forwarded with thesafety 10 CFRquestion.

l 50.59 evaluation to SORC for review.

6.4.2.4 Personnel recommended 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 l l Program.

1 6.4.2.5 Temporary procedure changes shall be made in accordance with l Specification 6.7.3 witn the exception that changes to procedures for which i reviews are assigned to Qualified Reviewers will be reviewed and approved as I described in Specification 6.4.2.2.

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RECORDS 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.

l TRAINING AND OUALIFICATION 6.4.2.7 The training and qualification requirements of personnel designated as l a Qualified Reviewer in accordance with the Station Qualified Reviewer Program l 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

c. An ecuivalent combination of education and experience as approved by 1

the cesignated department head.

i SEABROOK - UNIT 1 6-8A Amendment No. 34 1

l ADMINISTRATIVE CONTROLS l 6.4.3 NUCLEAR SAFETY AUDIT REVIEW COMMITTEE (NSARC)

FUNCTION i

6.4.3.1 The NSARC shall function to provide independent review and audit of

' designated activities. The NSARC shall report to and advise the Executive Vice President & Chief Nuclear Officer on those areas of responsibility specified in Specifications 6.4.3.7 and 6.4.3.8.

, COMPOSITION 6.4.3.2 The NSARC shall be com)osed of at least five (5) individuals. The Chairman, Vice Chairman and mem)ers, including designated alternates, shall be appointed in writing by the Executive Vice President & Chief Nuclear Officer.

i Collectively, the individuals appointed to the NSARC should have experience and expertise in the following areas:

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, a. Nuclear power plant operations. I

b. Nuclear engineering, ,

c. Chemistry and radiochemistry,

d. Metallurgy.

, e. Instrumentation and control.

l f. Radiological safety,

g. Mechanical and electrical engineering, and l

h. Quality assurance practices. i L

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

l ALTERNATES 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: however, 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 provide expert advice to the NSARC.

MEETING FREOUENCY 6.4.3.5 The NSARC shall meet at least once per 6 months 6 weeks.

OUORUM 6.4.3.6 The cuorum of the NSARC necessary for the performance of the NSARC review and aucit functions of these Technical Specifications shall consir of the Chairman or Vice-Chairman and at least four NSARC members including alter-nates. No more than a minority of the quorum shall have line respo,*sibility for operation of the unit. The Vice Chairman, or his designated alternate, can participate as an NSARC member when the Chairman is in attendance.

l SEABROOK - UNIT 1 6-8B Amend,nent No. 34, i

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ADMINISTRATIVE CONTROLS l

AUQlIS l

l 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 l provided the combined time interval for any three consecutive intervals shall l not exceed 3.25 times the specified interval. These audits shall encompass:

a. The conformance of station operation to 3rovisions contained within !

l the Technical Specifications and applica)le license conditions at !

least once per 12 months: I l

b. The performance, training, and qualifications of the entire station i

staff at least once per 12 months:

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c. The results of actions taken to correct deficiencies occurring in i station equipment, structures, systems, or method of operation that i affect nuclear safety, at least once per 6 months; '

l 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: l i

e. The fire protection programmatic controls including the implementing procedures at least once per 24 months by qualified licensee OA l personnel:

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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:

g. The Radiological Environmental Monitoring Program and the results thereof at least once per 12 months:

! h. The OFFSITE DOSE CALCULATION MANUAL and implementing procedures at l least once per 24 months:

l l i. The PROCESS CONTROL PROGRAM and implementing procedures for l processing and packaging of radioactive wastes at least once per 24 t

months:

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

l k. Not used:

1. Not used: and

m. Any other area of station operation considered appropriate by the NSARC or the Executive Vice President & Chief Nuclear Officer.

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

ADMINISTRATIVE CONTROLS RECORDS l

6.4.3.9 Records of NSARC activities shall be prepared and distributed as j indicated below:

, a. Minutes of each NSARC meeting shall be prepared and forwarded to l Executive Vice President & Chief Nuclear Officer within 30 working l .

days following each meeting- !

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b. Reports of reviews encompassed by Specification 6.4.3.7 shall be I j included in the minutes where applicable or forwarded under separate i cover to the Executive Vice President & Chief Nuclear Officer within !

So working days following completion of the review; and i i

c. Audit reports encompassed by Specification 6.4.2.8 shall be i forwarded to the Executive Vice President & Chief Nuclear Officer l and to the management positions responsible for the areas audited within 30 days after completion of the audit by the auditing organization.

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) 6.L REPORTABLE EVENT ACTION The following actions shall be taken for REPORTABLE EVENTS: i

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

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b. Each REPORTABLE EVENT shall be reviewed by the SORC and the results I i of this review shall be submitted to the NSARC and the Executive l-l Vice President & Chief Nuclear Officer.

i y 6.6 SAFETY LIMIT VIOLATION l

The following actions shall be taken in the event a Safety Limit is l violated:

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

! Jossible and in all cases within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months . The Executive Vice 3 resident & Chief Nuclear Officer and the NSARC shall be notified within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months ;

b. A Safety Limit Violation Re) ort shall be prepared. The report shall be reviewed by the SORC. T1is report shall describe: (1) applicable circumstances preceding the violation, (2) effects of the violation upon facility components systems, or structures, and (3) corrective action taken to prevent recurrence:

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

Commission the NSARC, and the Executive Vice President & Chief Nuclear Officer within 14 days of the violation: and i

i d. 0)eration of the station shall not be resumed until authorized by t1e Commission.

l l SEABROOK -' UNIT 1 6-11 Amendment No. 34

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ADMINISTRATIVE CONTROLS 6.7 PROCEDURES AND PROGRAMS 6.7.1 Written procedures shall be established, implemented, and maintained covering the activities referenced below:

a. The applicable procedures recommended in Appendix A of Regulatory Guide 1.33, Revision 2, February 1978:

b. The emergency operating procedures required to im)lement the requirements of NUREG-0737 and Supplement 1 to NUREG-0737 as stated in Generic Letter i40. 82-33:

c. Not used;

d. Not used:

e. PROCESS CONTROL PROGRAM implementation: I l

f. OFFSITE DOSE CALCULATION MANUAL implementation: ;

g. Quality Assurance Program for effluent and environmental monitoring;

h. Fire Protection Program implementation; and I

i. Technical Specification Improvement Program implementation.

6.7.2 The Station Director may designate specific procedures and programs or l

classes of procedures and programs to be reviewed in accordance with the Station Qualified Reviewer Program in lieu of review by the SORC. The review per the l Qualified Reviewer Program shall be in accordance with Specification 6.4.2. I 6.7.3 Procedures and programs listed in S)ecification 6.7.1, and changes l thereto, shall be a) proved by the Station Jirector or by cognizant department '

i head or Directors w1o are designated as the Approval Authority by the Station '

Director. s 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)ecification 6.7.1. and changes thereto, shall be reviewed by the SORC 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.

6.7.5 Changes 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 approved in accordance with the l Station Qualified Reviewer Program, within 14 days of implementation.

SEABROOK - UNIT 1 6-12 Amendment No. 34, 39.

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ADMINISTRATIVE CONTROLS 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. A radiation monitoring device that continuously indicates the >

radiation dose rate in the area; or

b. A radiation monitoring device that continuously integrates the i radiation dose rate in the area and alarms when a preset integrated i dose is received. Entry into such areas with this monitoring device i may be made after the dose rate levels in the area have been established and personnel have been made knowledgeable of them; or

c. An individual qualified in radiation protection procedures with a radiation dose rate monitoring device, who is responsible for providing positive control over the activities within the area and shall perform aeriodic radiation surveillance at the frequency specified in t1e Radiation Work Permit.

6.11.2 In addition to the requirements of Specification 6.11.1, areas dCCessible 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 i%rager on duty and/or health ph sics supervision. Doors shall remain locked cxcept during periods of access personnel under an approved RWP that shall l specify the dose rate levels in t e immediate work areas and the maximum allowable stay time for individuals in that area. In lieu of the stay time specification of the RWP, direct or remote (such as closed circuit TV cameras) continuous surveillance may be made by personnel qualified in radiation 3rotection procedures to provide positive exposure control over the activities 3eing performed within the area.

For individual high radiation areas accessible to personnel with radiation levels of greater than 1000 mR/h that are located within large areas, such as PWR containment, where no enclosure exists for purposes of locking, and where no 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 PROCESS CONTROL PROGRAM (PCP) 6.12.1 The PCP shall be approved by the Commissicn prior to implementation.

6.12.2 Licenseednitiated changes to the PCP:

a Shall be submitted to the Commission in the Annual Radioactive Effluent Release Report for the period in which the change (s) was made. This submittal shall contain:

4 SEABROOK - UNIT 1 6-21 Amendment No. 23.

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SECTION IV J I

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l DETERMINATION OF SIGNIFICANT IIAZARDS FOR PROPOSED CIIANGES I i

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IV. DETERMINATION OF SIGNIFICANT HAZARDS FOR PROPOSED CHANGES License Amendment Request (LAR) 96-19 proposes multiple organizational title changes contained in Technical Specification (TS) 6.0, " Administrative Control". An additional proposed change to Technical Specification 6.4.2," Station Qualified Reviewer Program" is also included in LAR 96-19.

In accordance with 10CFR 50.92, North Atlantic has reviewed the proposed changes and has concluded that they do not involve a significant hazards consideration. The proposed changes do not involve a significant hazards consideration because the changes would not:

1. Involve a significant increase in the probability or consequences of an accident previously 3

evaluated. !

l No design basis accidents are affected by the proposed administrative and editorial changes. The l proposed organizational changes are administrative and editorial in nature and are being proposed to '

reflect the NU nuclear organizational changes from October 1996 and January 1997 and other title i changes implemented by North Atlantic. The Technical Specification changes associated with the October 1,1996 organizational changes involve the responsibilities currently assigned to the Senior

., Vice President and the Executive Director-Nuclear Production. The proposed changes assign these .

! responsibilities to the Executive Vice President and Chief Nuclear Officer. Additional changes !

I include the title changes of the Station Manager to Station Director, Shift Superintendent to Shift l Manager, Auxiliary Operator to Nuclear Systems Operator and the revision of the term crewman to l crewperson to make the term gender neutral.

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1 The proposed change to the Station Qualified Reviewer Program is also an administrative change and no design basis accidents are affected by the proposed change. The change replaces the term

" Manager, (shown in both upper and lower case throughout TS Sections 6.4.2 and 6.7.3) with the terms " department head" or " designated department head." Many department managers are actually Supervisors and this change will assign responsibility to the correct departmental position.

2. Create the possibility of a new or different kind of accident from any previously evaluated.

There are no changes in the way Seabrook Station is operated due to this administrative change, thus the potential for an unanalyzed accident is not created. There is no impact on plant response and no new failure modes are introduced. These proposed administrative and editorial changes have no impact on the safety limits or design basis accidents and they have no potential to create a new or l, unanalyzed event.

3 Involve a significant reduction in a margin of safety.

The changes do not directly affect any protective boundaries nor do they impact the safety limits for the protective boundaries. These proposed changes are administrative and editorial in nature and will not create a reduction in the margin of safety.

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ML20134L868

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