ML20134E166
ML20134E166 | |
Person / Time | |
---|---|
Site: | Millstone |
Issue date: | 02/03/1997 |
From: | NORTHEAST NUCLEAR ENERGY CO. |
To: | |
Shared Package | |
ML20134E162 | List: |
References | |
NUDOCS 9702060064 | |
Download: ML20134E166 (82) | |
Text
-- ._. _ _ _ _ . . _ _ . _ - . _ _ - _ _ . . . . _ _ _ . . . _ . - _ _ . . _ _ _ _ _ _ _ _ _ . _ . . . _ _ _ . _ . _ .
l Docket No. 50-245 50-336 -
50-423 i l
B16224 4
i 1
i l
l l
i i
Attachment 1 4
i Millstone Nuclear Power Station, Unit Nos.1,2, and 3
+
Proposed Revision to Technical Specifications a Administrative Controls Marked-Up Pages i
l i
j i
d February 1997 9702060064 970203 PDR ADOCK 05000245' P PDR l
4/26/94
]*-
ADMIN!$TRATIVE CONTROLS . .
6.1 RESPONSIBftTTY
!,* 6.1.1 Chief 10udse officer (c$ e)- m.*0M 0:rd overall operation 9+hig>shall of the Millstone Station site while the tud be responsible for coeration af +he
- A;T President t.
17ston*J3*ttto The Senior Vice j ' QM in writing, he succession e M Q1srar WhW Director hall each delegate, i
a e respons1D111tiestdurino their ahtaare.
s.f ORGANf7ATf0N
] "b N#
6.2.1 DFFSITF A dd% ks CANffATION
& ) @ %.jiS % u.at 9Rea Onsite and offsite organizations shall be establi r
' g h'] # M 1
corporate management ._ .s unit operation and
! respectively. The onsite and offsite organizations 1
1 shall plant.
power include the pos,itions for activities affecting the safety of the nuclea 1
a.
Lines of authority, responsibility, and comunication shall be -
i established and efined for the higher management levels through intermediate levela to and including all operating organization positions.
4 These relationships shall be docume~nted and 6pdated, as i
1 tions of departmental responsibilities and relationsh I
descriptions documentation.for key personnel positions, or 1r. equivalent forms of Quality Assurance Topical Report.These requirements shall be rio:
~ ,g 4gg cq,tep b.
The CEh/o'r Vi#'PrAsWent(w4dhtonwSHtiminha11 be respon for overall unit safe operation and sia11 have control over those onsite activities necessary for safe operation and maintenance of the plant.
g g,,,, y:ce G b T u d W - /.* y d c.
The(Ifg[utiv'e Yice Pr.tueet-Mut@ shill nave corporate respon-sibility for overall plant nuclear safety and shall take any measures operation needed to ensure acceptable performance of the staff in to ensure, nuclear safety. maintaining, and providing technical support d.
The individuals who train the operating staff and those who carry out health physics and quality assurance functions may report to the appropriate ensite manager; however, they shall have sufficient organizational freedom to ensure their independence from operating pressures.
- l ,
5.2.2 FAtilfTY STAFF .
s.
Each os duty shift shall be composed of at least the minimum shift crew composition shown in Table 6.21.
b.
At fuelleast is inone thelicensed reactor, Operator shall be in the control room when a.
c.
4 At least two licensed Operators shall be present in the control room during recovery reactor start-up, from reactor scheduled reactor shutdown and during trips.
)
[1,1,1stoneUnitI s-1 Amendment No. 77. 77, 74
1 i
3 i
July 16,1996 ADNINISTRATIVE CONTROLS 4
6.4 TRAINING f
Q -(.p6-#1%% h 6.4.1 A retraining and replacement training program for the facility staff j shall be atintat3ed under the direction of the Senior Vice President i' requiremen&fUlysknedustioln and shall meet or exceed the ts anc recomendauens of Section 5.5 of ANSI NI8.1-1971 and 10 CFR Part 55.59. The Director-Nuclear Training has the overall Program.
responsibility for the implementation of the Training 6.5 REVIEW AND AUDIT 6'.5.1 Plant Deerations Review Committee (PORC) i Function O
{
6.5.1.1 ThePORCshallfunctiontoadvisethkegegpf#Pi're'otMonall matters related to nuclear safety.
Cemeesition 6.5.1.2 The PDRC shall be composed of nine to eleven members. Members shall collectively have experience and expertise in the following areas:
Plant Operations Engineering Reactor Engineering Maintenance Instrumentation and Controls Health Physics Chemistry Work Pla /Cs(nt Quality
.u*u e)
The minimum qualifications of PORC membert shall be that all members have an academic degree in an engineering or physical science field.
b;mtv, or hold a management position. and have a minimum of five years
- t. technical experience in their respective field of expejr ise. The y a mbers of PORC shall be appointed in writing by the @(ch_aar/UMt.
8P' mrAe . The Chairperson and alternate Chairperson of the PORC sha' Lye drawn from the PORC members and be appointed in writing by the Qc5ttr&Usit/ D#rtetTr).
Alternates '
6.5.1.3 Alternate members shall be appointed in writing by the PORC Chairperson to serve on a temporary basis; however, no more than two alternates shall participate in PORC activities at any one time.
Millstone Unit 1 6-5 essa Amendment No. 77. JJ. 7J.
95
ADMINISTRATIVE CONTROLS Meetino Fresuenev 6.5.1.4 The PORC shall meet at least once per calendar month and as convened by the PORC Chairperson.
AluttiR 6.5.1.5 A quorum of tha_ PORC zhall consist of the Chairperson or Vice membersincludingalternates. Chairperson Frestfiist V(ceI:4sid@t - mvst Reseensibilition j 6.5.1.6 The PORC shall be responsible for:
- a. Review of 1) all procedures, except comon site procedures, required by Specification 6.8 and changes thereto, 2) all programs, except comon site programs, required by Specification 6.8 and changes thereto, 3) any other proposed procedures.
D:# programs, or changes thereto, as determined by the @crent #nK.
u.;t MrgotprJto affect nuclear safety. Procedures and programs p Wd 5 required by Specification 6.8 that are designated for review and approval by the Station Qualified Reviewer Program do not require PORC review.
- b. Review of all proposed tests and experiments that affect nuclear safety.
- c. Review of all proposed changes to Sections 1.0 - 5.0 of these Technical Specifications.
- d. Review of all proposed changes or modifications to plant systems or equipment that affect nuclear safety.
- e. Investigation of all violations of the Technical specifications and preparation and forwarding of a report coverina evaluation and sea:or recomendations to prevent recurrence to theqindutivs Fir.t vic e resident 4Weamland to the Chairperson of-the Nuclear Safety fed ' e Assessment Board.
cP9"pg
- f. Review of all REPORTABLE EVENTS.
- g. Review of facility operations to detect potential safety hazards.
- h. Performance of special reviews and investigations and reports ,
thereon as requested by the Chairperson of the Nuclear Safety Assessment Board.
- 1. Render determinations in writing if any ites considered under 6.5.1.6(a) through (d) above, as appropriate and as provided by '
10CFR50.59 or 10CFR50.92, constitutes an unreviewed safety -
l question or re l
determination. quires a significant hazards consideration Millstone em Unit 1 6-6 Amendment No. J. N, N, 71,91
j ADMINISTRATIVE CONTROLS July 16,1996 i8 1
4 i j. Review of the unit-specific Fire Protection Program and I' implementing procedures.
i .
Authoritv 5.5.1.7 The PORC shall:
0;ede,%:tO(>eO**b
); -7
- a. - Recommend to the M rbr4V0frWeMlwritten approval or i disapproval of t i@ ems consiceres under 6.5.1.6(a) throu j * "*
,,4cpo.in:M*nd Q:lb7N h:t1 bWC4 8
- b. Provide 1 triate written notification in ne senior vice i Pramident w sy Stofg SMtf6M Gatedutive' VAe' PrtMdh W-i~ p;eutoG ji' Mar)ancFthe Qairperson'of the Nuclear Jafe Asses'ement u t
- J*d Board'of disagreement between the PORC and the Altrit_
- 4 epe DiferA,o6; however, theQk!credr Arnit DJfocteDsha11 have oN b ve.
n = res 4
5.5.1.8.
The PORC shall siaintain written minutes of eacgmeeting and o..:waa shall be provided to the Senior Vice PresidentQ'IH1ktene4tA74m and Chairperson of the Nuclear Safety Assessment Board.
6.5.2 Site coerations Review comittee fs0Rt1 i Funetion d 'M 6.5.2.1 The enne W 11 function to advise the Senior Vice President /
7Wistord stb 6sDon all matters related to nuclear safety o e entire M111stche Station Site.
6.5.2.2 The 50RC shall be composed of the:
y c.p7m:ltsfue)
Chairperson: 5enine Vice PresidentG AHWatefseWsiD )
Member: GMtd BWester pt,auwe,u. u e ,,,,,ti.. O l Member: Lnit Z< U U t OW ct*& -
Unit 3C{ ,,,3 ,,g % k ,s:c e{
Member: Aernces W ret 4p ht*0*e> Gsd k'*5)
Member: Designated Mem>er of Unit 1 PORC Member: Designated Member of Unit 2 PORC Member:
Den Unated Member of Unit 3 PORC O '* #
Member: Des. nated Member of @f1fty/Stryists ow4's!S O I The Chairperson.
Seniorh Unit Director in attendance _shall be the Vice f ,%+, r , A , + o pt,45 ..]
Alternates 6.5.2.3 Alternate members shall be appointed in writing by the SORC Chairperson to serve on a temporary basis; however, no more than two alternates shall participate in 50RC activities at one time.
Millstone Unit 1 6-7 Amendment No. pp. 7J. 7p, JJ,95 eies
i April 24,1996 i i ADMIN!sTRATIVE CONTROLS j Neetino Frecuency
- 6.5.2.4 The 50RC shall meet at least once per six months and as convened by
- the SORC Chairperson.
m ..
6.5.2.5 A quorum of the 50RC shall consist of the Chairperson or Vice j Chairperson and five members including alternates.
pesconsibilities *
, 6.5.2.6 The 50RC shall be responsible for:
- a. Review of 1) all common site procedures required by Specifi-cation 6.8 and changes thereto, 2 all coanon site pro .J required by Specification 6.8 and)ch&nges thereto,any 3) grams, other cN#-
proposed procedures, programs. er chanose th e to.as determined 2 wtone by the Senior Vice PresidentCtmi4Wtdnf $4at'idXo affect site nuclear safety. Common site programs and procedures required by Specification 6.8 that are designated for review and approval by the Station Qualified Review Program do not require SORC review.
i b. Review of all proposed changes to Section 6.0, ' Administrative Controls", of these Technical Specifications.
- c. perfomance of special reviews and investigations and reports as requested by the Chairperson of the Nuclear Safety Assessment Board.
- d. Not used. l
- e. Not used. l
- f. Review of all common site proposed tests and experiments that affect nuclear safety.
- g. Review of all common site proposed changes or modifications to systems or equipment that affect nuclear safety.
- h. Render deteminations in writin , or meeting minutes if any item considered under 6.5.2.6 appropriate and as provided by(a through 0CFR50.5g or (g) above .as 10CFR50.92, constitutes an unreviewed safety question or requires a significant hazards consideration detemination. ,
- 1. Review of the common site Fire Protection Program and taplementing procedures.
miltstone unit 1 s-a Amendment no. pp 77, 77, U, 94 em
1 1
January 17,1996 l ADMINISTRATIVE CONTROLS Authoritv 6.5.2.7 The 50RC shall: nd CNo-I6!U d "
I
- a. Recomend to the Senior Vice President (s/Wili/tsW SfstMwritten approval or disa under 6.5.2.6(a)pproval, in meeting minutes, of items considered through(g)above.
provido imediate written mo"ification, or meeting minutes, to the 4
Pmbf dtuer
-*hedukit' vim /Wetfdtat/WW4:19and the Chairperson of the Nuclear Safety Assessment Board _of disaareement between the 50RC f>cc S X and the Senior Vice President 631:indsWSith however, the 1
onw) Senior Vice President 67hf1lignMs Jon3sha119 ave (ca o responsibility for resolution or suchptsagreemenTs) pursuant to 6.1.1 above.
4%
mae 6.5.2.8 The 50RC shall maintain written minutes of each etini and cocies shall be provided to the Senior Vice President hfinewStstran and Chairperson of the Nuclear Safety Assessment BoarC 5.5.3 NUtLEAR SAFETY ASSESSMENT BOARD (NSAB)
FUNCTION 6.5.3.1 The minimum qualifications of NSAB members are as follows:
- a. The Chairperson and NSAB members shall have:
- 1. An academic degree in an engineering or physical science field, or hold a senior management position, and
- 2. A minimum of five years technical experience in their respective field of expertise.
- b. The NSAB shall have experience in and shall function to provide independent oversight review and audit of designated activities in the areas of:
- 1. Nuclear power plant operations;
- 2. Nuclear engineering;
- 3. Chemistry and radiochemistry;
- 4. Metallurgy;
- 5. Instrumentation and control;
- 6. Radiological safety;
[i,1,1stoneUnit1 49 Amendment No. JJ JJ. JJ. 7J. 77, 91
Jrnuary 17,1996 ADMIN!$TRATIVE CONTROL 5
- 7. Nechanical and electrical engineering; and
- 8. Quality assurance practices. Y a ~a d #
The NSAB serves to advise theMW VjfrpedWartt#-Andter)on mattern related to nuclear safety and notify me d:'nudw. wwn Yeatfde6t - NucWwithin 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> of a safety significant disagreement'between the NSAB and the organization or function being reviewed.
COMPOSITION ;d"Y *nd c Nh 6.5.3.2 The h ttne yi/a Prdst'ddrd - Wudini9 shall appoint, in writing, a 7
l minimum m seven members to the NSAB and shall designate from this !
membership, in writing, a Chairperson and a Vice Chairperson. The l membership shall function to provide independent review and audit in I the areas listed in Specification 6.5.3.1.
ALTERNATES 7 .dcE 9) 6.5.3.3 All alternata ==here shall be appointed, in writing, by the Vice _Pris##pt --/N4cis'eS; however, no more than two alternates sha participate as members in NSAB activities at any one time.
MEETING FRE00ENCY 6.5.3.4 The NSAB shall meet at least once per calendar quarter.
EEllE 4.5.3.5 The quorum of the NSAB shall consist of a majority of NSAB members including the Chairperson or Vice Chairperson. No more than a minority of the quorum shall have line responsibility for operation of the same Northeast Utilities' nuclear unit. No more than two alternates shall be appointed as members at any meeting in fulfillment of the quorum requirements.
REVIEW RESPONSIBftfTIES 6.5.3.6 The NSAB shall be responsible for the review of:
I
- a. The safety evaluations for changes to procedures, equipment, or systems, and tests or experiments completed under the provisions of 10 CFR 50.59, to verify that such actions did not constitute an unreviewed safety question as defined in 10 CFR 50,59;
- b. Proposed changes to procedures, equipment, er systems that involve an unreviewed safety question as defined in 10 CFR 50.59;
- c. Proposed tests or experiments that involve an unreviewed safety question as defined in 10 CFR 50.59;
~
t Millstone Unit 1 em 6-10 Amendment No. JJ, JJ. 7J. 91
1 \
l ADMIN!$7RATIVE CONTROLS l! d. Proposed changes to Technical Specifications and the Operating License; e
- e. Violations af applicable codes regulations, orders, license j
requirements, or interral proce,dures having nuclear safety
{ significance; i
- f. All Licensee Event Reports required by 10 CFR 50.73; J
- g. Indications of significant unanticipated deficiencies in any
} aspect of design or operation of structures, systems, or i
components that could affect nuclear safety; j h. Significant accidental, unplanned, or uncontrolled radioactive
] releases, including corrective actions to prevent recurrence;
) 1. Significant operating abnormalities or deviations from normal and 4
expected performance of equipment that could affect nuclear i safety; 7 ca;dat'a~d l
- J. The perforzance of the corrective action program; and CGo
- k. Audits and audit plans.
. , f, ;/.h,,g,Q Reeerts er reeerde af these reviews shall be forwarded to thalthc4tivD
! Vite &re' stb 6t /d4(cMr)within 30 days following completion of the '
i review. !
) AUDIT PROGoM RESPONSIBILITits h.15audEw 6.5.3.7 i
~Ks'se stmgnt dietvieti) De r partment.The NSAB audits shal NSAB audit erocram -
lean, ente per 24 montis in accordance with Nuclear Group Procedures l and shall encompass:
- a. The conformance of unit operation to provisions contained within i the Technical specifications and applicable license conditions; 4
i
- b. The training and qualifications of the unit staff;
! c. The implementation of all programs required by Specification 6.8;
- d. The Fire Protection Program and implementing procedures.
- e. The' fire protection equipment and program implementation utilizing either a qualified offsite license fire protection engineer or an outside independent fire protection consultant.
- f. Actions taken to correct deficiencies occurring in equipment, structures systems, components, or method of operation that affect nuclear safety; and
{ijlstoneUnit1 6-11 Amendment No. J, 77, 71 91
ADMINISTRATIVE CONTROLS January 17,1996 ;
g.
jther activities Jrdridet and do:uments as requested by the Q McQt he M p tryc}ep6 .
RECORDS f s;de ,+and CE o 6.5.3.8 Written records of reviews and audits shall be maintained. As a minimum these records shall include:
- a. Results of the activities conducted under the provisions of Section 6.5.3;
- b. Recommended approval or disapproval of items considered under !
Specifications 6.5.1.6.a through 6.5.1.6.d. and 6.8; and 1
- c. Determination as to whether each item considered under Specification 6.5.1.6.a. 6.5.1.6.b, 6.5.1.6.d. and 6.8 constitute an unreviewed safety question as defined in 10 CFR 50.5g.
6.5.4 Station Dualified Reviewer Pr '
Function ~
6.5.4.1 k'
.L D D UMN*N eovus [ .
The dildJetr Mit' DirtMor Senior Vice President (7hillst404 Statipn) may establisa a stat < on Qualified Reviewer Program whereby requireo /
reviews of designated procedures or classes of procedures required by Specifications 6.5.1.6.a and 6.5.2.6.a are performed by Station >
Qualified Reviewers and approved by designated managers. These reviews are in lieu of reviews by the PORC or SORC. However, procedures which require a 10CFR50.59 evaluation must be reviewed by the PORC or 30RC.
Reseensibilities 6.5.4.2 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 perfomed by a Qualified Reviewer (s)inaffecteddisciplines or by other persons designated by cognizant managers or, directors as having specific expertise required to assess a particular procedure, program, or change. Cross disciplinary reviewers may function as a committee.
- 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 10CFR50.59 to verify that Millstone me Unit 1 6-12 Amendment No. #, 77. 91
i ADMIN!57 PIT!YE CONTROLS '
\ ,
an unreviewed safety question does not exist. This screening will i be performed by personnel trained and qualified in performing 10CFR50.5g evaluations.
~
- e. Provide for written recommendation by the Qualified Reviewer (s to the responsible Manager for approval or disapproval of procedur)es 4
and programs considered under Specification 5.5.1.5.s and 6.5.t.6.a and that the procedure or program was screened by a qualified individual and found not to require a 10CFR50.5g
{ evaluation.
1 i 5.5.4.3 If the responsible manager detemines that a new program, procedure i
i change thereto requires a 10CFR50.5g evaluation, that manager will , or ensure the required evaluation is performed to determine if the new j
procedure, program, or change involves an unreviewed safety question.
The new procedure, program er e e will then be forwarded with the
- 10CFR50.5g evaluation to r review-i n.c .r s e a O I 6.5.4.4 Personnel recomended to the Station tualified Reviewers shall be i
designated in wri N 4 * @
i PresidentC#Itipit6/StAto or aP4WM DiMrder)or Senior Vice each procegure, regram, or class of procedure or regram within the scope of the Station Qualified Reviewer Program.
l ,,gcya,g,;;9p.9 y }'f,}
6.5.4.5 Temporary procedure changes shall be made in accorcance with i 5pecification 6.8.3 with the exception that changes to procedures for witch reviews are assigned to Qualified Reviewers will be reviewed and approved as described in Specification 6.5.4.2.
Renrds 5.5.4.6 The review of procedures and programs performed under the Station Qualified Reviewer Program shall be documented in accordance with administrative procedures.
Trainine and Dualificatien 6.5.4.7 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 engineerins, 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 equivalent combination of education and experience as approved by a department sanager.
Millstone Unit 1 em 6-13 Amendment No. 91
6 l
April 24,1996 ADMINISTRATIVE CONTROLS l l l 6.6 REPORTABLE EVENT ACTION j 6.6.1 The following actions shall be taken for REPORTABLE EVENTS:
- a. The Commission shall be notified and a report submitted
- pursuant to the requirement of 10 CFR 50.73.
- b. Each REPORTABLE EVENT shall be reviewed by the PORC and the results of this review < hall be suh=1tted to the Chairperson of the NSAB and the(gr6sctivy VW1reMdsstr#pdtaO ---
6.7 SAFETY LINIT VIOLATION "
[*k i 6.7.1 The following actions shall be taken in the event a Safety Limit is
{ violated:
i
- a. The unit shall be placed in at least HOT STANDBY within two hours.
}
i b. The NRC Operations Center shall be no'tified by telephone at j
soon as possible and in all cases within one hour. The6dedHW%
V&rPeeMontAtGelerr)and the Chairperson of the NSAB shall be notsfied within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. )
4,, y,.g py;gggg .3:,g,f,,g
! c. A Safety Limit Violation Report shall be prepared. The report j shall be reviewed by the PORC. This report shall describe (1) applicable circumstances preceding the violation, (2) effects 3
i of the violation upon facility components, systems or structures, and (3) corrective action taken to prevent recurrence.
I d. The Safety Limit Violation Report shall be submitted to the Commission. the Chairperson of the NSAB and theGarsd4veditr#
Jte5Mefd Mwithin 14 days of the violation.
- e. Operation shall not be resumed until authorized by the Cosnission.
6.8 PROCEDURES 6.8.1 Written procedures shall be established, implemented and maintained covering the activities referenced below
- a. The applicable procedures reconnended in Appendix 'A" of i Regulatory Guide 1.33, February,1978.
- b. Refueling operations.
- c. Surveillance activities of safety related equipment.
- d. Not used.
I
- e. Not used. I
- f. Fire Protection Program Implementation.
N111 stone Unit 1 6-14 Amendment No. J. M. M. U. 94 ossa
l ADNIN!$7AATIVE CONTROL 5 l
t
\
j 3 Quality Control for effluent monitoring using the guidance in
- Regulatory Guide 1.21 Rev. 2. June 1974.
i i h. Radiological Effluent Monitoring and Offsite Dese Calculation Manual j (REMODCM Radiological l
Environme)ntal Monitoring, implementation,g;;~ except cvofor+:ll5N section 1.E d
! 6.8.2 a. "hadEiktr4frdt pfght@or Senior Vice President 6At11stMo i
'G u v ' MM491*ay casignate specific procedures and programs, or classes of j ope procedures and programs to be reviewed in accordance with the station i
lij+.,p#W e nM Qualified Reviewer Program in lieu of review by theQL%C/ The I F8 "*$ oop" review per the Qualified Reviewer Program shall ha in mera-dane specification 6.5.4. be, h:t onmfiea f 8
[*3,je j j b. Procedures and 1rograms listed in Semelfication 6.8.1. and chang i thereto, shall a sonroved by the cketr Enn4bert or Senior j Vice PresidentQ- htiJt9dedGtitik@er by cognizar,t Mann er o Directors who are cesignated as the rava Autha the otr)r Uptt11rettm9er Senior Vice President ' 1&Md4A specified in administrative procedures. The Approval as each procedure and program or class of recedure and(fauthority program shall be for specified in admiaistrative crocedures. a.,4 c4 o - pmt stue) o F.C. o r $0g@
- c. Each procedure enseification 6.8.1, and changes thereto ishall be 3:J r. reviewed by th 5@and shall be sooroved by 1 i g RitetteF or Senior VLee President or reviewed O P'j ,o s and approved in accordance with th tation quailfled Reviewer Program, prior to implementation. Each procedure of Specification 6.8.1 shall be reviewed periodically as set forth in administrative procedures.
6.8.3 Temporary changes to procedures of 6.8.1 above any be made provided:
- a. The intent of original procedure is not altered.
- b. The change is approved by two members of the plant annagement staff, ,
at least one of whom holds a Senior Reactor Operator's License on the unit affected. o g ,,.i.p.
- c. The change is documented, reviewed by the or the Station t'. rec.tk i lified Reviewer Pronram, as annlicable an ' approved by the gat atfonAwityVd RefWar Prosnpaa NarrrM or the@cH5efArdt'__
'o - Bea 3 IriDtrettoT)or 91HofXhft Pr5MHat 7MijaMprW141Mywithin 14 daysr
'of implementation. -
(Jeo.,r V;ee fec:dar 4.lcMo Mt 40 2 *N~'" 0"st*<d te g,w.e Pn$e=4 b t*P I 6.8.4 wrnten procesures shall De established, implemented and maintaine .
covering section 1.E Radiological Environmental Monitoring, of the i REMODCN.
gijlstoneUnit1 6 15 Amendment No. M, 71, 91
i j' ADMINISTRATIVE CONTROLS V26/H j s
!l j 6.15 RADIOLOGICAL EFFLUENT MONITORING AND OFF3!TE 00$E CALCULATION MANUAL i (REMODCM) i
! Section I, Radiolo ical Effluents Monitoring Manual (REMM), shall outline the l sampling and anal is programs to detersine the concentration of radioactive 1
saterials release offsite as well as dose comitments to individuals in those
, exposure pathways and for those radionuclides released as a result of station
- operation. It shall also specify operating guidelines for radioactive waste j treatment systems and report content.
i
! Section II, the Offsite Dose Calculation Manual (0DCM), shall describe the
! methodology and parameter.s to be used in the, calculation of offsite doses due i to radioactive gaseous and liquid affluents and in the calculations of gaseous
! and liquid effluent monitoring instrumentation alarr/ trip setpoints consistent l with the applicable LC0's contained in these technical specifications.
Changes to the REMODCM:
l a. Shall be documented and records of reviews perfomed shall be retained
- as required by Specification 6.10.2.m. This documentation shall l contain
I
- 1) Sufficient information to support the change together with the
! appropriate analyses or evaluations justifying the change (s),
l4 and i
! 2) A determination that the change will maintain the level of l radioactive effluent control required by 10 CFR 20.106, 40 CFR i Fart 190, 10 CFR 50.36a, and Appendix ! to 10 CFR Part 50 and 1 not adversely impact the accuracy or reliability of affluent, i dose, or setpoint calculations.
- b. Shall become effective after review and accentance by 50RC and the j approval of the Senior Vice PresidentG7 tit 1st4rg Stattdr0 t-caq wo - rn:iis MO l
, c. Shall be submitted to the Comission in sne vers of a complete, legible copy of the entire REMM or ODCM, as appropriate, as a part of or concurrent with the Annual Radioactive Effluent Report for the ;
period of the report in which any change was made. Each change shall be identified by markingt in the margin of the affected pages, t
clearly indicateindicating the date (e.he area /ofyear)thechangewasimplemented, the page that was changed, and shall g., month l 4
1 i
gi,1,1stoneUnit1 6-23 Amendment No. 77,77,77,74
ADMIN!$TRATIVE CONTROLS 4/26/94 p.3 g y- 6.1 RESPONSIBfLITY hd UM"'/r" W'b Mb /"
l' 6.1.1 The Senior Vice President [ Milleter.e Ot: ten shall be responsible l
for overall operation of the Millstone Station Site while the LeiniekUnit
- Director shall be responsible for operation of the unit. The Senior Vice i President r Mill:t::: St:ti;r. er.d Ecleer- nit Director shall each delegate in
( writing the succession to these resnensibi it es during their absence.
5,2 "0RGAN17AT10 t '" d /# M # d # A b "'# " Y
- l w.a a .+ .1 sha// be Ws/tnso64 fs o. rent /
I 6.'t .1 0FFSITE AND ONSITE ORGANI7AT10NS *W+9', N ' "/' " *#^ * * " # %
! Onsite and offsite organizations shall be established for unit operation and j corporate management, respectively. The onsite and offsite organizations shall include the positions for activities affecting the sa'ety of the nuclear power plant.
l a. Lines of authority, responsibility, and comunit.ation shall be l
established and defined for the higher management levels through intermediate levels to and including all operating organization
- positions. These relationships shall be documented and updated, as 4 appropriate, in the form of organization charts, functional descrip-i tions of departmental responsibilities and relationships, and job
! descriptions for key personnel positions, or in equivalent forms of documentation. These requirements shall be documented in the Quality Assurance Topical Report.gf g3g gg
- b. Th e .. .. . . . . . .. . . . . . . . .. . . . . . . . . .... . . . . . ...*s h a11 be re s p o n s i bl e for overall unit safe operation and shall have control over those onsite activities necessary for safe operation and maintenance of the plant. ,g p,,g a m.,,,jj,g
- c. The S:cutive Viceh eiUenticieerfsha11 have corporate respon-sibility for overall plant nuclear safety and shall take any measures needed to ensure acceptable perfomance of the staff in operation, saintaining, 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 ennager; however, they shall have sufficient organizational freedom to ensure their independence from operating pressures.
6.2.2 FACILITY STAFF
- a. Each on duty shift shall be composed of at least the minimum shift crew composition shown in Table 6.2-1.
- b. At least one licensed Operator shall be in the control room when fuel is in the reactor.
- c. At least two licensed Operators shall be present in the control room during reactor start-up, scheduled reactor shutdown and during recovery from reactor trips.
Millstone - Unit 2 6-1 Amendment No. JJ. 77 77, J7.
me 92. 208. 125. !#2. 752.
r 1
@ 9 ')
ADMINISTRATIVE CONTROLS July 16,1996 l
6.4 TRAINING h C'#o- A//5h 4
! A retraining and replacement training program for the facilit staff shall be .
- ilit;;;
! maintained under the direction of the Senior Vice President l
Ot:the and shall meet or exceed the requirements and recomendations of
- Section 5.5 of ANSI N18.1-1971 and 10 CFR Part 55.59. The Director-Nuclear Traintrig has the overall responsibility for the implementation of the Training i Program.
I l 6.5 REVIEW AND AUDIT
, 6.5.1 Plant Doerations Review Committee (PORC)
Function 6 44 6.5.1.1 The PORC shall function to advise the Nuclet Unit Director on all matters related to nuclear safety.
Comoosition 6.5.1.2 The PORC shall be composed of nine to eleven members. Members shall l collectively have experience and expertise in the following areas: l Plant Operations Engineering Reactor Engineering i Maintenance Instrumentation and Controls Health Physics Chemistry Work Planning : d C:;tr:1 Quality S:rvi::: /?ssur.mcc The minimum qualifications of PORC members shall be that all members have an academic degree in an engineering or physical science field, or hold a management position, and have a minimum of five years technical experience in their respective field of expertise. The members Director. The of PORC shall be Chairperson andbe appointed alternate in writingof Chairperson bythe the >0RC M :)1:D Unit shall be drawn from the PORC members and be appointed in/Friting by the %.;1e:r Director. j Alternates 6.5.1.3 Alternate members shall be appointed in writing by the PORC Chairperson to serve on a temporary basis; however, no more than two alternates shall participate in PORC activities at any one time.
Millstone Unit t 6-5 Amendment No. JJ7, 17J. 17J I
- 200
J_______ _ ._.______ ___ ___
- 9-3-99 .,
j ADMINISTRAT!YE CONTROLS i, n , ,, , 3 f 3aag j j . _
i Meetino Freauenev i
- 6.5.1.4 The PORC shall meet at least once per calendar month and.as convened j by the PORC Chairperson.
i j DMB
! 6.5.1.5 A quorum of the PORC shall consist of the Chairperson, or Vice 1
Chairperson,-cr Sr.ies ";;; "r;:ti;,t - %;1ht:a; Stetten and four f members including alternates.
! Reseensibilities i
8.5.1.6 The PORC shall be responsible for:
i a. Review of 1) all procedures, except common site procedures, j required by Specification 6.8 and chan j programs, except comon site programs,ges re thereto, 2) all {
l i Specification 6.8 and changes thereto, 3) quired any other byproposed l 1 procedures, programs, or changes thereto as determined by the j tl,,, t 9 -tuchar* Unit Director to affect nuclear safety. Procedures and !
i programs required by Specification 6.8 that are designated for review and approval by the Station Qualified Reviewer prograa j do not require PORC review.
I b. Review of all proposed tests and experiments that affect
- nuclear safety. i i
I c. Review of all proposed changes to Sections 1.0 - 5.0 of these l Technical Specifications.
i I d. Review of all proposed changes or modifications to plant j systems or equipment that affect nuclear safety.
l e. Investigation of all violations of the Technical Specifications and preparation and forwarding of a report covering ovaluation i and recommendations to prevent recurrence to the free:th; " ;e-i "rt:th-t "nh;r and to the Chairnerman af the Nucir Safety
- Assessment Board. / h ,,, v,u v b /,,.s 1
! f. Review of all REPORTABLE EVENTS.QaosA coo ~/",:isk.n
- g. Review of facility operations to detect potential safety i
hazards.
i h. Performance of special reviews and investigations and reports
- thereon as requested by the Chairperson of the Nuclear Safety Assessment Board. .
- i. Render determinations in writing if any ites considered under 6.5.1.6(a)through(d)above,asappropriateandasprovidedby l 10CFR50.59 or 10CFR50.92, constitutes an unreviewed safety i question or re .)
determination. quires a significant hazards consideration i
J. Review of the fire protection program and implementing procedure.
J Millstone Unit 2 88 AmendmentNo.JJ,77,77, enes 19,111,I.ll,III. .186. 111.193
_ m._ _. _
2 l p-3-99 -
July 16,1996 ADMINISTRATIVE CONTROLS AMO9 2 .
clesfa 6.5.1.7 The PORC shall:
- ~ a. Recommend to the ll;;hir ' Unit Director written a disapproval of items considered under 6.5.1.6(a)pproval through (d) or above, a,,,, cm . ,,,, y, g, p,,,w is,, a gg.,,,, gag
- b. Provide mediate written notification to the Senior Vice President r liilleten; St:ti:n, Executh: Y!:: Pr::id;nte;1eer and the Chairperson of the Nuclear Safety Asser,sment Board of disagreement between the PORC and the ::a;1eerj.dnit Director; however, the l';;1;;r Unit Director shall have responsibility for resolution of suc disagreements pursuan'. to 6.1.1 above.
Records dad
- 6.5.1.8 The PORC shall maintain written minutes of each meeting and copies
. shall be provided to the Senior Vice Presidentc "il ht;n; Stetien,-
and Chairperson of the Nuclear Safety Assessment Board.
6.5.2 Site Ooerations Review Committee (SORC) and CNo-/71,//shn]
Function 6.5.2.1 The 50RC shall function to advise the Senior Vice President #
,.illete..e
" Ot;ti:n- en all matters related to nuclear safety of the entire Millstone Station Site.
(*"**' *"
6.) cno-s!!<//shQ 6.5.2.2 The 50RC shall be composed of the:
Chairperson: Senior Vice President ".ilut::: St:ti;;r i Member: Unit 1 Dir::t:r 0,m e. u,. e oj,<,., f,i n i Member: Unit 2+ Director ,
Member: Unit 3* Director Member: Unit Ser,-i;;; Oire;ter Du<ch-#s</~' 5Yv"'S Member: tite Servh;; Directe <prueg u,6 <oca/5<e </^ <r Member: Designated Member of Unit 1 PORC Member. Designated Member of Unit 2 PORC Member. Designated Member of Unit 3 PORC Member: Designated Member of 0;:lity 0;rvices44ec4w j o s v.), p +
The senior l;;h:r Unit Director in attendance shall be the Vice- l Chairperson.
/Dyreh.,thi+0puahu}s 6.5.2.3 Alternate members shall be appointed in writing by the SORC Chairperson to serve on a temporary basis; however, no more than two alternates shall participate in 50RC activities at one time.
Millstone Unit 2 6-7 Amendment No. # 1. J U . J U.
0100 200
l d-3-79 ADMINISTRATIVE CONTROLS Neatino F2 qggngy l l 6.5.2.4 The 50RC shall meet at least once per six months and as convened by the 50RC Chairperson. !
l W j 6.5.2.5 A quorum of the 50RC shall consist of the Chairperson or Vice Chairperson and five members including alternates.
Resconsib111 ties 6.5.2.6 The 50RC shall be responsible for: I
- a. Review of 1) all common site procedures required by Specifi-cation 6.8 and changes thereto, 21 all common site programs, any other required by Specification proposed procedures, programs, 6.8orand changes changes thereto, thereto as 3) determined by the Senior Vice President "i11epr.e Statin to affect site nuclear safety. Commor. sit programs and procedures required by Specification 6.8 that are designated for review and approval by the Station Qualified Reviewer Program do no require 50RC review. 9 ,,.,4 cao. ,n,g, A.,g
- b. Review of all proposed changes to Section 6.0 ' Administrative I Controls' of these Technical Specifications. ,
- c. Perforisance of special reviews and investigations and reports as requested by the Chairperson of the Nuclear Safety Assessment Board.
- d. Not used. !
- e. Not used. I
- f. Review of all common site proposed tests and experiments that affect nuclear safety.
- g. Review of all common site proposed changes or modifications to systems or equipment that affect nuclear safety.
- h. Render determinations in writing or meeting minutes if any item considered under 6.5.2.6fa) through (g) above, as appropriate and as provided by 10CFRSO.5g or 10CFR50.g2, constitutes an unreviewed safety question or requires a significant hazards consideration determination.
~
l 1. Review of the common site fire protection program and implementing procedures.
L .
)
i r ut11 stone unit a 6-s Amendment No. 17, pp 177, 177, un 177, 171, 171, 196
9 9 t>
ADMINISTRATIVE CONTROLS , _ _ _ _ _ _ _ ,
Authority
( 6.5.2.7 The 50RC shall: a-./ No-M//sWeg
- a. Recommend to the Senior Vice Presidentr "'11;t;;.; . St.th .
written asproval or disapproval in meeting minutes of items considerec.under6.5.2.6(a)through(g)above.
- b. Pr, v,ide i.n. media,te written mnotification
._..u__. '--- or meeting minutes to
_ _ _ . . ...u ..
and the Chairperson of the 8Ma4"4 od Nuclear Safety Assessment Board of disagreement between the l
CA,c/ Emuhst 50RC and the Senior Vice Presiden " ' " ^ - - ~^^^'---
l cyh- (cfo) however, the Senior Vice President ?.illete..e it:t'= shall have responsibility for resolut 'of such disagreements j l pursuant to 6.1.1 above. i Records ' ** ' "'O 5.5.2.8 The 50RC shall maintain written minutes of each meeting " ' " ^ - -
and copies I
shall be provided to the Senior Vice President ' ' " ' - -
and Chairperson of the Nuclear Safety Assessment Board.
6.5.3 NUCLEAR SAFETY ASSESSMENT BOARD (NSAB) !
4 l
FUNCTION 6.5.3.1 The minimum qualifications of NSAB members are as follows:
l- a. The Chairperson and NSAB members shall have:
1
- 1. An academic degree in an engineering or physical science i field, or hold a senior management position, and j i
- 2. A minimum of five years technical experience in their i respective field of expertise.
- b. The NSAB shall have experience in and shall function to provide independent oversight review and audit of designated activities in the areas of: l
- 1. Nuclear power plant operations;
- 2. Nuclear engineering; l 3. Chemistry and radiochemistry; i
l 4. Metallurgy; 1
- 5. Instrumentation and control;
- 6. Radiological safety;
- 7. Mechanical and electrical engineering; and lf-
- 8. Quality assurance practices.
Millstone Unit 2 6-9 Amendment Nos. 17. JJ 77, un 91,119,Ill, 77K. 78K. 193
ADMINISTRATIVE CONTROLS Janusry 17,1996 1
l The NSAB serves to advise the Oe;etive V;;; Tr.;it;t ':::h:r on .
)
matters related to nuclear afety and notify the '--""- "'-- i Pr::!tet - "=h:r withi i 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> of a safety significant I disagreement between the NSABIand the organization or unction being reviewed. I 1
COMPOSITION
@rrode.d and Cfo '
6.5.3.2 The 0.;etive V;;e 7.old...t - L;h;r shall appoint, in writing, a minimum of seven members to the NSAB and shall designate from this ,
membershi , in writing, a Chairperson and a Vice Chairperson. The l' l
membershi shall function to provide independent review and audit in the areas listed in Specification 6.5.3.1.
ALTERNATES 6.5.3.3 All alternate members shall ""-h be a ppointed, in writing, by the R:rtive Yh: gre;" " -
however, no more than two alternates shall participate as members in NSAB activities at any one time. i er,J r.s4 a J C :
l MEETING FRE00ENCY 6.5.3.4 The NSAB shall meet at least once per calendar quarter.
EDEM ,
6.5.3.5 The quorum of the NSAB shall consist of a majority of NSAB members including the Chairperson or Vice Chairperson. No more than a minority of the quorum shall have line responsibility for operation of the same Northeast Utilities' nuclear unit. No more than two alternates shall be appointed as members at any meeting in fulfillment of the quorum requirements.
REVIEW RESPONSIBILITIES 6.5.3.6 The NSAB shall be responsible for the review of:
- a. The safety evaluations for changes to procedures, equipment, or systems, and tests or experiments completed under the provisions of 10 CFR 50.59, to verify that such actions did not constitute an unreviewed safety question as defined in 10 CFR 50.59;
- b. Proposed changes to procedures, equipment, or systems that involve an unreviewed safety question as defined in 10 CFR 50.59; -
- c. Proposed tests or experiments that involve an unreviewed safety question as defined in 10 CFR 50.59; ,
l d. Proposed changes to Technical Specifications and the Operating T License; i l
!. Millstone Unit t 6-10 Amendment No.17, 97, jf,193 h esoe 11$,191,19$,
i l
j-3-9) i
_i February 14,1995 ADMINISTRATIVE CONTROLS i ,
(~
- e. Violations of applicable codes, regulations, orders, license requirements, or internal procedures having nuclear safety significancei;
- f. All Licensee Event Reports required by 10 CFR 50.73;
- g. Indications of significant unanticipated deficiencies in any aspect of design or operation of structures, systems, or components that could affect nuclear safety;
- h. Significant accidental, unplanned, or uncontrolled radioactive releases, including corrective actions to prevent recurrence;
- i. Significant operating abnormalities or hviations from normal and expected performance of equipment that could affect nuclear safety;
- j. The performance of the corrective action program; and j k. Audits and audit plans.
Reports or records of these reviews shall be forwarded to the iE::::th: Y!: Pre !6r.t M :l=pithin 30 days following completion of the review.
I AUDIT PROGRAM RESPONSIBILITIES {fa sw/r~1 d4 CE '
[y" f
6.5.3.7 The NSAB audit program shall be the responsibility of theftveH+y-I M ?.;;;;;;;.;r.t Srvice* Department. NSAB audits shall be performed at least once per 24 months in accordance with Nuclear Group Procedures and shall encompass:
- a. The conformance of unit operation to provisions contained within the Technical Specifications and applicable license conditions;
- b. The training and qualifications of the unit staff; !
l c. The implementation of all programs required by Specification 6.8;
- d. The Fire Protection Program and implementing procedures.
- e. The fire protection equipment and program implementation utilizing either a qualified offsite license fire protection engineer or an outside independent fire protection consultant. I
- f. Actions taken to correct deficiencies occurring in equipment,
, structures, systems, components, or method of operation that
!f affect nuclear safety; and
! g. Other activities and documents as requested by thep:=the 1
-Vice rreswent - L.cl =. g Millstone Unit 2 6-11 ndment No.79,45,64, j nei 73,726,777,73#,763,184 i
D- 3 -9 t? _
ADMIN!5TRATIVE CONTROLS January 17.1996 RICORDS
}
6.5.3.8 Written records of reviews and audits shall be maintained. As a i
minimum these records shall include:
, a. Results of the activities conducted under the provisions of Section 6.5.3; i
- b. Recomended approval or disapproval of items considered under Specifications 6.5.1.6.a through 6.5.1.6.d, and 6.8; and
- c. Determination as to whether each Specification 6.5.1.6.a. 6.5.1.6.b, iter considered under
- 6. J' .1. 6. d, and 6.8 constitute an unreviewed safety question as defined in 10 CFR 50.5g. ,
i I
6.5.4 Station Dua11fied Reviewer Procram Function Q {j/j ,
& Mow 6.5.4.1 ThebMh:- Unit Directorder Senior Vice President ".." u m .e St:tur. may establish a Station Qualified Reviewer Program whereby required reviews of designated procedures or classes of procedures required by Specifications 6.5.1.6.a and 6.5.2.6.a are performed by Station Qualified Reviewers and approved by designated managers.
These reviews are in lieu of reviews by the PORC or SORC. However, procedures which require a 10CFR50.5g evaluation must be reviewed by I the PORC or 50RC.
Restonsibilities 6.5.4.2 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, prograas, and changes thereto when organizations other than the presaricg organization are affected by the procedure, program, or caange.
- c. Ensure cross-disciplinary reviews are perfomed by a Qualified Reviewer (s designated) by in affected disciplines, or by other persons cognizant Managers or Directors as having specific expertise required to assess a particular procedure, program, or change. Cross-disciplinary reviewers may function as a committee.
- d. Provide for a screening of designated procedures, programs and i changes thereto to determine if an evaluation should be l
- performed in accordance with the provisions of 10CFR50.59 to verify that an unreviewed safety question does not exist. This ,j screening will be perfomed by personnel trained and qualified in performing 10CFR50.5g evaluations.
Millstone Unit 2 6-12 Amendment Nos. JJ, JJ, JJ. JJJ,193 0307
o C- 3 -9 9 l ADMINISTRAT!YE CONTROLS J2nuary 17,1996 i i
I k e. Provide for written recomendation by the Qualified Reviewer s) to the responsible Manager for approval or disapproval (of procedures and programs considered under Specification 6.5.1.6.a and 6.5.2.6.a and that the procedure or program was
~ screened by a qualified individual and found not to require a
.. 10 CFR 50.59 evaluation.
6.5.4.3 If the responsible manager deterstnes that a new program, procedure, or change thereto requires a 10 CFR 50.59 evaluation, that Manager will ensure the required evaluation is performed to determine if the new procedure, program, or change involves an unreviewed safety question. The new procedure, program, or charge will then be forwarded with the 10 CFR g g eva tio 3r for review.
6.5.4.4 Personnel recomended to be designated in writing by the(Station5&r UnitQualified Reviewers Directo shall or Senior Vicebe President c t ilet: c :tet h; for each procedure, rogram, or class of procedure or program within the scope pf the Stati_on Dualified RevLewsr Program. a,,J cpo ,,wm.,7' a Arts A ,,e etn t h eeue ,y cuwv.,j 6.5.4.5 Temporary procedure changes shall be made in accorcance with Specification 6.8.3 with the exception that changes to procedures for which reviews are assigned to Qualified Reviewers will be reviewed and approved as described in Specification 6.5.4.2.
Reecrds 6.5.4.6 The review of procedures and programs performed under the Station Qualified Reviewer Program shall be documented in accordance with administrative procedures.
Trainine and Dualification 6.5.4.7 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; DR
- c. An equivalent combination of education and experience as approved by a Department Manager.
Millstone Unit R 6-13 Amendment Nos. 193 anos
p-3-e April 24,1996 ADNINISTRATIVE CONTROL 5 6.6 REPORTABLE EVENT ACTION 6.6.1 '
The following actions shall be taken for REPORTABLE EVENTS:
- a. The Commission shall be notified and a report submitted
~
. pursuant to the requirements of Section 50.73 to 10 CFR Part 50, and
- b. Each REPORTABLE EVENT shall be reviewed by the PORC and the results of this review shall be submitted to the Chairperson of l the NSAB and the C;e;;tiv: Y!c: 5 :td:nt ";;]eer.
Se w t/,ce f>As./ M 6.7 SAFETY LIMIT VIOLATION q ego f,,,dd,t r 6.7.1 The following actions shall be taken in the event a safety Omit is violated:
- a. The unit shall be placed in at least HOT STANDBY within one hour. ,
- b. The NRC Operations Center shall be notified by telephone as soon as possible and in all cases within I hour. The, W
- "ice Pr;;id;;t ";&r and the Chairperson of the NSABI1 hall be notified within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />; (5~m,u We Gn,dra
\4(n.2 C,vD - /Pro lHrirne
- c. A Safety Limit Violation Report shall be prepared. The report shall be reviewed by the PORC. This report shall describe:
(1) applicable circumstances preceding the violation, i (2) effects of the violation upon facility components, systems, i or structures, and (3) corrective action taken to prevent recurrence; '
- d. The Safety Limit Violation Report shall be submitted to the Cosmiission, the Chair >erson of the NSAB, and the ";tiv: Y!ce Tre;ident " &r witiin 14 days of the violation
- e. Operation shall not be resumed until authorized by the I
'**"'"'*** Sea,io , U,<c $ m b d 6.8 PROCEDURES #ad M A N 5* re 6.8.1 Written procedures shall be established, implemented and maintained covering the activities referenced below:
- a. The applicable procedures recomunended in Appendix "A" of Regulatory Guide 1.33, February,1978.
- b. Refueling operations. ~
- c. Surveillance activitiws of safety related equipment.
- d. Not used.
3 9
- e. Not used.
~
Nillstone Unit t 6-14 Amendment Nos. M . JJ. 77. 111.
ame # 1, i n . I M . 1 H .196
2 ~3 -9 ')
ADMINISTRATIVE C0hTROLS January 17.1996
- f. Fire Protection Program implementation.
- g. Quality Control for effluent monitoring using the guidance in Regulatory Guide 1.21 Rev.1 June 1974. ,
- h. Radiological Effluent Monitoring and Dffsite Dose Calculation implementation, except for Section I.E.,
J. Manual Radiological(REMODCM)ironmental Env Monitoring.fr Asse ud"d u,,nl A m..e<1o n aJ ('w~ ^ds ha 6.8.2 a. The-+htehec Unit Director,'or Senior Vice President > r.illnens 4t: tier may designate specific procedures and programs, or classes of procedures and programs to be reviewed in accordance with the
f g Station Qualified Reviewer Program in lieu of review by the POR SORC. The review per the Qualified Reviewer Program shall be in accordance with Specification 6.5.4. o,.
/
b.
Procedures and programs listed in}e .Specificacion 6.8.1, and changes thereto, shall be approved by th .;;i::r Unit Director or Senior om/ N O- Vice PresidentMi.litene U rectors Stitien who are designated or by as the co$nizant Approva Mana Authority er or ed y the Alls hu 4hrc%agUnit Director or Senior Vice President 6 ".iil;te .:- Ignache,
-Stttten, as specified in administrative procedures. The Approval 4,, r 9 Authority for each procedure and program or class of procedure and program shall be specified in administrative procedures.
- c. Each procedurz of Specift atto 6.8.1, and changes thereto, shall be reviewed by the POR ORC and shall be approved by the t'u;ia;r
- St;tica, or be hi- 9dp, Director reviewedor and Senior Vice approved President in accordance withrHiiisndStation th Qualified Reviewer Program, prior to implementation. (Each procedure of Specification 6.8.1 shall be reviewed periodically)as set forth in administrative procedures. g ega_f,g, 6.8.3 Temporary changes to procedures of 6.8.1 above may be made provided:
- a. The intent of 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 Reactor Operator's License on the unit affected. Q de.f 3
- c. The change is documented, reviewed by the P MRC, or the /
Station Qualified Reviewer Program as applicable, and approvedlby th ~"-- Ogilified EcView:r Pre;ri- Manager ;r M;;i.d'Jnit
" " ' ^ -
recto for Vice Presidentt ^^ ^' y lthin 14 days of implementation. g.a cao hng 6.8.4 Written procedures shall be established, implemented and maintained covering Section I.E, Radiological Environmental Monitoring, of the REMODCH.
l, ,- % M Qal, AJ ,
1 g%e~<. 6%y.1m (Drp,w a mamy.-
l Millstone Unit 2 6-15 Amendment Hos.111,17F,1 77, 77, 7J,9sJJJ, em
4/26/94 ADMINISTRATIVE CONTROLS 1
i
' 6.15 RADIOLOGICAL EFFLUENT MONITORING AND OFFSITE DOSE CALCULATION MANUAL fREMODCM)
Section I, Radiological Effluents Monitoring Manual (RDM), shall outline the t
sampling and analysis programs to determine the concentration of radioactive materials released offsite as well as dose comitments to individuals in those exposure pathways and for those radionuclides released as a result of station operation. It shall alco specify operating guidelines for radioactive waste treatment systems and report content.
Section II, the Offsite Dose Calculation Manual (00CN), shall describe the !
methodology and parameters to be used in the calculatfor, of offsite doses due I to radioactive gaseous and liquid effluents and in the f.alculations of gaseous !
and liquid effluent monitoring instrurentation Alang/ Trip Setpoints consistent with the applicable LC0's contained in these Technical Specifications.
Changes to the REMODCM:
- a. Shall be documented and records of reviews performed shall be retained as required by Specification 6.10.2m. This documentation shall contain:
- 1) Sufficient inforsation to support the change together with the appropriate analyses or evaluations justifying the change (s),
and
- 2) A detemination that the change will maintain the level of l radioactive affluent control required by 10 CFR 20.106, 40 CFR l Part 190,10 CFR 50.36a, and Appendix 1 to 10 CFR Part 50 and not adversely impact the accuracy or reliability of effluent, dose, or setpoint calculations.
- b. Shall become effective after review and acceptance by SORC and the approval of the Senior Vice President r 7d115 tea St:ti=._
y__ S t c~,n sm as m e_)
a l
- c. Shall be submitted to the Connitsion in the form of a complete, legible copy of the entire REMM or ODCM, as appropriate, as a part of or concurrent with the Annual Radioactive Effluent Report for the period of the report in which any change was made. Each change shall be identified by markings in the margin of the affected pages, clearly indicating the area of the page that was changed, and shall-indicate the date (e.g., month / year) the change was implemented.
i )
l l gijlstoneUnit2 6-24 Amendment No. JJJ, JJJ, JJJ,174 l
\ - -- _-. .-
4/26/94 ADMINISTRATIVE CONTROLS i
6.1 RESPONSIBILITY 4,vp C w M m s44 O rr,sc4 (cQ 6.1.1 The Senior Vice President - Millstone @tetEDshall be responsible l
for overall operation of the Millstone Station site while theQn?nr "1 Oirnt@shall be responsible for on' nit of the unit. The shallsenior vice '
O Presteent.- Millstone Ot:t! " nd p:_. 1g;..
_ Director each dele
- writingthesuccessiontothferesponsiblitiesduringtheirabsence.gatein 6.2 ORGANIZATI0k'fy*** 5"'d h # b#* # ~
i Id"### '#
Mue r s sunsr a t n d s F**'s,0*/
6.2.1 0FFSITE AND DN5ITE ORGANIZATIONS Fo4 O W C A As,s W e sP E A F 4 0 8 Y 44 r M*'
4*m rue 6,,r
- uu,e Necr= ,
i Onsite and offsite organizations shall be established for unit operation and corporate management, respectively. The onsite and offsite organizations shall include the positions for activities affecting the safety of the nuclear power plant.
- a. Lines of authority, responsibility, and comunication 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 descrip-tions of departmental responsibilities and relationships, and job l descriptions for key personnel positions, or in equivalent forms of documentation. These requirements shall be documented in the Quality Assurance Topical Report.
Pone a ene s so n~r - mwe an U*ord
- b. The(*m Mr Yi n Fr:rfd =t "'ll:ta; :;tet;Qshall be responsible for overall unit safe operation and shall have control over those l onsite activities necessary for safe operation and maintenance of the pla
, ,,,,,c , g,, , , ,,, , 4, , cy , , g , ,,, ,3
- c. TheC==the YMe rnid=t M 1 2 shall have corporate responsi-a bility for overall plant nuclear saTety 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.
I 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.
i 6.2.2 FACILITY STAFF
- a. Each on-duty shift shall be composed of at least the minimum shift
.: crew composition shown in Table 6.2-1; 1
MILLSTONE - UNIT 3 6-1 Amendment No. JJ, JA 90 0192
ADMINISTRATIVE CONTR0tS August 28,1992 l 6.2.3 INDEPENDENT SAFETY ENGINEERfNC CROUP fitEC)
FUNCTf0N
) 6.2.3.1 The ISEG shall include, as part of its function, examination of unit 1
operating characteristics, NRC issuances, industry advisories, Licensee Event
) Reports, and other sources of unit design and operating experience 4
information, including units of similar design, which may indicate areas for improving unit safety. The ISEG shall make detailed recommendations for
, revised procedures, equipment modifications, maintenance activities, 2 operations activities, er other means of improving unit safety to appropriate station /corporationmanagement.
1 COMPOSITION l
} 6.2.3.2 The ISEG shall be composed of at least four full-time personnel i located on site to perform the functions described in 6.2.3.1 for Millstone i Unit 3. Each person shall have either:
) (1) A bachelor's degree in engineering or related science and at least 2 years of professional level experience in his field, at least 1 year of which experience shall be in the nuclear field, or.
l (2) At least lo years of professional level experience in his field, at least 4 5 years of which experience shall be in the nuclear field.
A minimum of 50% of these personnel shall have the qualifications specified in i
(1)above.
j RESPONSIBfL1 TIES 6.2.3.3 The ISEG shall be responsible for maintaining surveillance of unit 2
activities to provide independent verification
- that these activities are performed correctly and that human errors are reduced as much as practical.
RECORDS 6.2.3.4 Records of activities performed by the !$EG shall be prepared and maintained, and quarterly reports of completed safety evaluations will be made to the Vice President-Nuclear . . . . . . . . . . . . . . . . ,
l 6.f.4 SHIFT TECHNICAL ADVISOR u E< s t t u r) 6.2.4.1 The Shift Technical Advisor shall provide advisory technical support to the Shift Supervisor in the areas of thermal hydraulics, reactor engineering, and plant analysis with regard to the safe operation of the unit.
The Shift Technical Advisor shall have a bachelor's degree or equivalent in a scientific or engineering discipline and shall have received specific training in the response and analysis of the unit for transients and accidents, and in unit design and layout, including the capabilities of instrumentation and
- controls in.the control room.
l T
- Not responsible for sign.off function.
MILLSTONE - ifNIT 3 64 Amendment No. 21,69 eess
ADNINISTRATIVE CONTROLS l .
6.3 FACILITY STAFF 00ALIFICATIONS 6.3.1 Each member of the facility staff shall meet or exceed the minimum a
qualifications of ANSI N18.1-1971 for comparable positions, except for:
- a. If the Operations Manager does not hold a senior reactor operator license for Millstone Unit No. 3, then the Operations Manager shall have
, held a senicr reactor operator license at a pressurized water reactor, and the Asaistant Operations Manager shall hold a senior reactor operator license for Millstone Unit No. 3.
- b. The Health Physics Manager shall meet or exceed the qualifications of Regulatory Guide 1.8, Revision 1, May 1977.
6.4 TRAINING l
6.4.1 A retraining and replacement training program for the facility staff shall be maintained under the direction of the Senior Vice President oCNh MillstoneGt;t@and shall meet or exceed the requirements and recommendations of Section 5.5 of ANSI N18.1-1971 and 10 CFR Part 55.59. The Director-Nuclear Training has the overall responsibility for the implementation of the Training Program.
6.4.2 Deleted.
6.5 REVIEW AND AUDIT 6.5.1 PLANT OPERATIONS REVIEW COMMITTEE (PORC) l FUNCTION M 6.5.1.1 related matters The PORC shallsafety.
to nuclear function to advise theh nit Director on all COMPOSITION 6.5.1.2 The PORC shall be composed of nine to eleven members. Members i shall collectively have experience and expertise in the following areas:
Plant Operations Engineering Reactor Engineering Maintenance Instrumentation and Controls Health Physics Chemistry -
Work Planning C CK.t;-M Quality The minimum qualifications of PORC members shall be that all members have an academic degree in an engineering or physical science field, or hold a management position, and have a minimum of five years technical experience in their respective fi expertise. The members of PORC shall be appointed in writing by the O M - nit Director. The Chairperson and alternate Chairperson of the PORC all be drawn from the PORC members and be appointed in writing by the * "" Unit Director.
MILLSTONE - UNIT 3 6-5 Amendment No. 77,77,77,77,77,
- J77,132
1 ADMIN!5TRAT!YE CONTROLS January 17,1996 ALTERNATES 6.5.1.3 All alternate members shall be appointed in writing by the PORC Chairperson to serve on a temporar;r basist however no more than two alternates shall participate as voSing members in f0RC activities at any one time.
MEETING FRE0UENCY 6.5.1.4 The PORC shall meet at least once per calendar month and as convened by the PORC Chairperson.
AEElli 6.5.1.5 The nuorum of the PORC thall :ennist of the chairperson or Vice Chairperson ^Ihrna1es.ir.cluding aI r ;;a ;r;;;;;:::: :Tresident
- ti;;; and four
- = members RESPONSIBftfTIES 6.5.1.6 The PORC shall be responsible for: U uir3
- a. Review of: 1 all procedures except common s te procedures, requiredby(Sp)ecification6.8,andchangesthe to 2 all programs, exceptthereto, changes common and L3site prog) any other rams required prseanad by Spect ocedures programs or icalion) 6 changes thereto as deSermined by thaCM ;;;; nit Direc, tor to affect nuclear safety. Procedures and programs required by Specification 6.8 that are designated for review and approval by the Station Qualified Reviewer Program do not require PORC review.
- b. Review of all proposed tests and experiments that affect nuclear safety;
- c. Review of all proposed changes to Sections 1.0-5.0 of these Technical Specifications; l
- d. Review of all proposed changes or modifications to plant systems or equipment that affect nuclear safety;
- e. Investigation of all violations of the Technical Specifications including the preparation and forwarding of reports covarha ava,lu -
tion and recommandLtions to prevent recurrence to theC ::Uth.
qm pre:nu ieeG and to the Chairperson o,f the Nuc; lear saraty _
assessment Boarc ;
(sgsc., vu,,, P4,n,,,r 4,, cuo d U "' " # #""~"
- f. Review of all REPORTABLE EVENTS; [ ),"$,"," y,$" 3
- g. Review of facility operations to detect potential safety hazards;
- h. Perfomance of special reviews investications reports thereon as requested the Chairperson,oforthe analyses Nuclearand SaFaty Assessment Board or th Senior Vice President - 111 stone A or O'8-
"Q'; snd y fant o res-
- 1. Render determinations in writing if any ites considere under Spet:ification 6.5.1.6a. through d. above, as appropriate and as provided by 10CFR50.59 or 10CFR50.92 constitutes an unreviewed fTj) 3 safety question determination.,orrequiresasignificanthazardsconsideration '
. NILLSTONE - UNIT 3 was 66 Amendment No. 7f, Jf, Jf 77, 171,125
July 16.1996 ADMINISTRATIVE CONTROLS j.
Review of Unit Turbine Overspeed Protection Maintenance and Testing Program and revision thereto,
- k. Review of the Fire Protection Program and implementing procedures.
AUTHORITY 6.5.1.7 The PORC shall: fj,,r 3
- a. Recommend to the Unit Director written approval or disapproval of item onsidered under Specification 6.5.1.6a.
through d. above; an
.aP4 assam-/r),,o.nuuerb @up c/up
- b. Provide written notification to the Senior Vice President f-Millstone Cteti:a* TE==tiv: '!::: "rr e m = m J and the i Chairperson of the Nuclear safet between the PORC and theO=l::? ynit Assessment loard or cisagreenant Director; however, thed":' r.
Unit Director shall have res onsibility for resolution of such disagreements pursuant to Sp ificat n 6.1.1. I 6.5.1.8 The PORC shall maintain written minutes of each meetinc and copies shall be provided to the Senior Vice President Millstone @q and the Chairperson of the Nuclear Safety Assessment Board.
A~ o CN3 6.5.2 SITE OPERATIONS REVIEW COMMITTEE (50RC)
FUNCTION ppCN) 6.5.2.1 The SORC shall function to advise the Senior Vice President -
Millstone CtetiO on all matters related to nuclear safety of the entire Millstone Station Site.
COMPOSITION 6.5.2.2 The SORC shall be composed of the: pp CA/o Chairperson: Senior Vice President - Millstone h ,
Member: "Jr/ t SDirectoi(T/-er Dru4 r, g !
Member:
Member: Unit Unit 32Hirector director r" "'#
CEit ;;rs;;;; ;r.:tMP,4ser.<, Nw.c44. Scs ..u)
Member:
Member: G"^ -
Q4agen, Gres4a 54a'"h Member: Designated Member of Unit 1 PORC Member: Designated Member of Unit 2 PORC Member: Designated Member of Unit 3 PORC ym u Member: Designated Member ofQ::lity **r/M-O oggo, gf, e !
The
- Senior h Unit Director in attendance shall be the Vice l
/ Donec. ret, U~urorsn Ar&
MILLSTONE - UNIT 3 6-7 Amendment No. pp, pp, Jpf, 117,
- l M -- -
April 24,1996 ADNINISTRATIVE CONTROLS ALTERNATES 6.5.2.3 Alternate members shall be appointed in writing by the 50RC Chairperson to serve on a temporary basis; however, no more than two alternates shall participate in SORC activities at one time.
MEETING FRE00ENCY 6.5.2.4 The SORC shall aset at least once per 6 months and as convened by the 50RC Chairperson.
EQElM 6.5.2.5 A quorum of the 50RC shall consist of the Chairperson .or Vica Chairperson and five members including alternates.
RESPONSIBILITJES 6.5.2.6 The 50RC shall be responsible for:
- a. Review of (1) all common site tion 6.8 and changes thereto, (2) procedures required by Specifica-all co 3 any other proposed A90Ch nrocedurer Vice Pres'de'nt nrYrams,1 stone ""*to affect site nu N11 or chanans thereto as Comon site proirans and prMs required by Specification 6.8 that are designated for review and approval b Reviewer Program do not require 50RC review.y the station Qualified
- b. Review of all proposed cha s to Section 6.0 " Administrative Controls" of these Technical S ecifications;
- c. Performance of special reviews and investigations and reports as requested by the Chairperson of the Nuclear Safety Assessment Board;
- d. Not used. l
- e. Not used.
l
- f. Review of all cosmon site proposed tests and experiments that affect nuclear safety;
- g. Review of all common site croposed changes or modifications to systems or equipment that affecu nuclear safety; and
- h. Render determinations in writing or meeting minutes if any ites considered under Specification 6.5.2.6(a) through (g) above, as appropriate and as provided by 10CFR50.59 or 10CFR50.9Z constitutes an unreviewed safety question or requires a significant hazards consideration determination.
~
- 1. Review of the common site Fire Protection Program and implementing procedures.
i MILLSTONE - L8l!T 3 6-8 Amendment No. S. pp pp. JM. JJP, 128
ADMINISTRATIVE CONTROLS January 17,1996 e
- AUTHORITY Cgo 6.5.2.7 The 50RC shall
- # -
a.
Recommend to the Senior Vice President - Millstone C> written
- approval or disapproval in meeting minutes of items considered unter Soecification E.E_f.6fa) throuch fa) above. and 3
- b. Pus ee r~r d o c mra Cr m rwe o m s< (c8-))
Pr m an s e estate written notification or meeting minutes to the R::Utive Y' e Her e nt- M eedand the Chairperson of the Nuclear safety Assessment Board of d: sagreement between the 50RC and the Senior Vice Presiden - 11 stone F4e44es; however, the Senior Vice Presidenta- Millstone _ tit.:...shal' have responsibility for resolutio i of such disagreements pursuant to 6.1.1 above.
RECORDS spCrpy
, 6.5.2.8 The 50RC shall maintain written minut s of each meetino and copies j
shall be provided to the Senior Vice President
- Millstone @and Chairperson of the Nuclear Safety Assessment Board.
- 6.5.3 NUCLEAR SAFETY ASSESSMENT BOARD (NSAB)
, FUNCTION 6.5.3.1 The minimum qualifications of NSAB members are as follows:
- a. The Chairperson and NSAB members shall have:
- 1) An academic degree in an engineering or physical science fleid, or hold a senior management position and i
- 2) A minimum of five years technical experience in their respective field of expertise. ;
- b. The NSAB shall have experience in and shall function to provide independent oversight review and audit of designated activities in the areas of:
- 1) Nuclear power plant operations;
- 2) Nuclear engineering;
- 3) Chemistry and radiochemistry;
- 4) Metallurgy;
- 5) Instrumentation and control;
- 6) Radiological safety; NILLSTONE - UNIT 3 6-9 Amendment No. JJ. JJ. 77. 177 125 un
I i
i i ADMINISTRATIVE CONTROL 5 January 17.1996 I
j
- 7) Mechanical and electrical engineering; and 8). Quality assurance practices. [ dtsptvTdd8 The NSAB serves to advise the6;;.ti.. t";se 7.;;;td;;A - Ldear%n natuers i related to nuclear safety and notify theGA;; li ".'ie; 7.e; Mesa - LiLet within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> of a safety significant disagreemens e ww.n sne naAs ana ';he organization or function being reviewed.
- COMPOSITION s,ocar op Ch 6.5.3.2 Th e @ - - "* * "- " ' -- * -- - "- ' Lid shall appoint, in writing, a minimum of seveTi members to the NSAs and shaL1 designate from this membership, in writing, a Chairperson and a Vice Chairperson. The membership shall !
j function to provide independent review and audit in the areas listed in Specification 6.5.3.1. l 4
0
- ALTERNATES ,Oggsso p r A+'D I
G.5 1 3 All alternate members shall be appointed, in writing, by the 6E e tie = v4-* ***ti E - r::3 however, no more than two alternates shall
'periisipaw as members in nas ac';ivities at any one time.
MEETING FRE0UENCY 6.5.3.4 The NSAB shall meet at least once per calendar quarter.
El!Mi 6.5.3.5 The quorum of the NSAB shall consist of a majority of NSAB members i
including the Chairperson or Vice Chairperson. No more than a minority of the
' quor:m tha11 have line responsibility for operation of the same Northeast Utilities' 3uclear unit. No more than two alternates shall be appointed as merhers at any meeting in fulfillment of the quorum requirements.
REVIEW RESPONSIBILITIES 6.5.3.6 The NSAB shall be responsible for the review of:
- a. The safety evaluations for changes to procedures, equipment, or systems, and tests or experiments completed under.the provisions of 10 CFR 50.59, to verify that such actions did not constitute an unreviewed safety question as defined in 10 CFR 50.59;
- b. Proposed changes to procedures, equipment, or systems that involve an unreviewed safety question as defined in 10 CFR 50.59; .
- c. Proposed tests or experiments that involve an unreviewed safety question as defined in 10 CFR 50.59; MILLSTONE - UNIT 3 6-10 Amendment No. 77, #, J#,125 eens Corr. Ltr. 4/6/94
j ADMINISTRATIVE CONTROLS
.in ni,m ru 1 7 s o o g
}
- d. Proposed changes to Technical Specifications and the Operating License;
- s. Violations of applicable codes, regulations, orders, license i
i requirements, or internal procedures having nuclear safety significance; '
' f.
All Licensee Event Reports required by 10 CFR 50.73; i g. Indications of significant unanticipated deficiencies in any aspect j !
of design or operation of structures, systems, or components that could affect nuclear safety; t
} h. Significant accidental, unplanned, or uncontrolled radioactive releases, including corrective actions to prevent recurrence; 4 1. Significant operating abnorsalities or deviations from normal and l expected performance of equipment that could affect nuclear safety;
! j.
The performance of the corrective action program; and
- k. Audits and audit plans. j'[
j j
itenerts er records of these reviews shall be forwarded to th 5;.a;n sk2 Q.e;id;ra - L;ig)within 30 days following completion of the review.
j AUDIT PROGRAM RESPONSIBILITIES osts A ,p b A w m a
^
Of !A A TMW"Y 6.5.3.7 The NSAB audit eranram Ahall be the responsibility of theGul;Q
~
Gnu Assessment $1rvices Decartmen). NSAS audits shall be performed at least once per z4 months in accordance with Nuclear Group Procedures and shall encompass:
- a. The conformance of unit operation to provisions contained within the Technical Specifications and applicable license conditions;
- b. The training and qualifications of the unit staff; I
- c. The implementation of all programs required by Specification 6.8;
- d. The Fire Protection Program and implementing procedures.
- e. The fire protection equipment and program impleme6tation utilizing l
either a qualified offsite license fire protection engineer or an outside independent fire protection consultant,
- f. Actions taken to correct deficiencies occurring in equipment, structures, systems, components, or method of operation that affect nuclear safety; and
- g. Other activitten and documents as requested by th S rth: Y: @
Gg;iderd - Sy.
(Pus opser V' (C fE0 MILLSTONE - UNIT 3 6-11 AmendmentNo.71.FJ,77,77,125 mas m
. - - -- - _ -.. . - - . - . . - _ ~ - - - . -_
l
{ ADMIN!$TRATIVE CONTROLS January 17,1996 e -
4 RECORDS I
i 6.5.3.8 Written records of reviews and audits shall be maintained. As a j minimum these records shall include:
i
- a. Results of the activities conducted under the provisions of l Section 6.5.3;
- i l b. Recomended approval or disapproval of items considered under j Specifications 6.5.1.6.a through 6.5.1.6.d. and 6.8; and
- c. Determination as to whether each item considered under l Specification 6.5.1.6.a. 6.5.1.6.b 6.5.1.6.d. and 6.8 constitute an i
unreviewed safety question as defined in 10 CFR 50.59.
l 6.5.4 stationcualdiedReviewerPrearam g Function Quer3 8' 4,o C $
I 6.5.4.1 The C M nit Director or Senior Vice President'- Millstone
! it".M may estaonsn a Station Qualifi6d Taviewer Program whereby required reviews of designated procedures or classes sif procedures required by Specifications 6.5.1.6.a and 6.5.2.6.a are performed by Station Qualified l Reviewers and approved by designated managers. These reviews are in lieu of
! reviews by the PORC or SORC. However, procedures which require a 10 CFR 50.59 i evaluation must be reviewed by the PORC or 50RC.
- Reseensibilities i
j 6.5.4.2 The Station Qualified Reviewer Program shall:
! a. Provide for the review of designated procedures, p ograms, and 4
j whopreparedtheprocedure, program,or(change. changes thereto b l l 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.
4
- c. Ensure cross-disciplinary reviews are performed by a Qualified Reviewer (s) in affected disciplines, or by other persons designated 4
i by cognizant Managers or Directors as having specific expertise required to assess a particular procedure, program, or change.
i Cross-disciplinary reviewers may function as a comittee.
1,
! d. Provide for a screening of designated procedures, programs and i
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 j performed by personnel trained and qualified in performing l 10 CFR 50.59 evaluations.
1 i .
I i
MILLSTONE - UNIT 3 uns 6-12 Amendment No. JJ. JJ. 77. JJ,17J' 125
ADM8N!sTRAT!YE CONTROL 5 jannney 37 goog
- e. Provide for written recomendation by the Qualified Reviewer (s) to the responsible Manager for approval or disapproval of procedures and programs considered under Specification 5.5.1.6.a and -5.5.2.5.a and that the procedure or program was screened by a qualified individual and found not to require a 10 CFR 50.59 evaluation.
5.5.4.3 If the responsible manager determines that a new program, procedure or change thereto requires a 10 CFR 50.59 evaluation, that Manager will ensure, the required evaluation is performed to determine if the new procedure, program, or change involves an unreviewed safety question. The new procedure, nronram. or change will then be forwarded with the 10 CFR 50.59 evaluation to E?^ im ~vtaw. (%,,r 33 og va russom- App
(*!l Q ac.eSggc. 3 ow " 4~ *r3 ua 5.5.4.4 rerwun.. ,. omended to the statio lifted Reviewers shall be designated in writing by the N P or Senior Vice President -
Millstone h".3 for each prM, Unit Directoprogram, or class of procedure or program within tae scope of the Station Qualified Reviewer Program.
5.5.4.5 Ter.porary precedure changes shall be made 15 accordance with Specification 5.8.3 with the exception that changes to procedures for which reviews are assigned to Qualified Reviewers will be reviewed and approved as described in Specification 5.5.4.2.
Records 5.5.4.5 The review of procedures and programs performed under the Station Qualified Reviewer Program shall be documented in accordance with I administrative procedures.
Trainino and Qualificatien 6.5.4.7 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
- c. An equivalent combination of education and experience as approved by a Department Manager.
i MILLSTONE - UNIT 3 6-13 Amendment No.125 4423 l
l
) April 24,1996
)
j ADMINISTRATIVE CONTROLS l
6.6 REPORTABLE EVENT ACTION
- 6.6.1 The following actions shall be taken for REPORTA8LE EVENTS
- a. The Commission shall be notified and a report ' submitted pursuant i
to the requirements of Section 50.73 to 10 CFR Part !io, and
- b. Each REPORTA8tE EVENT shall be reviewed by the PORC and the i results of this review shall be submitted to the Chaf rperson of the NSA8 and the g ;tte
j 6.7 SAFETY LIMIT VIOLATION n,se u p CNo i
k[(Siran.4. mUeu.i - sc.sr-Pu r 6.7.1 The following actions shall be taken in the event a safety Limit is l violated:
i i a. The Unit shall be placed in at least HDT STAND 8Y within one hour.
l 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 />. TheG....re; YTp
,.;;id;;.t4.J.3 and the Chairperson of the NSAB snali ou
! not171ea un;ntn 74 hours8.564815e-4 days <br />0.0206 hours <br />1.223545e-4 weeks <br />2.8157e-5 months <br />; i
- c. A Safety Limit Violation Report shall be prepared. The report i Sgm , W4 shall be reviewed by the PORC. This report shall describe
i
' Df"'d# g (1) applicable circumstances preceding the violation, (2) effects l 1 of the violation upon facility components, systems, or structures, c oo FI " ") and (3) corrective action taken to prevent recurrence;
- d. The Safety Limit Vio1Ltion Report shall be submitted in the j
r-ission. the Chairperson of the NSAB, and the(;;;;tiv: Yi:0 l Q;;id;;t "rh@within 14 days of the violation; and t
j e. Operation shall not be resumed until authorized by the Cosmission.
! 6.8 PROCEDURES AND PROGRAMS I
i 6.8.1 Written procedures shall be established, implemented, and maintained j covering the activities referenced below:
- a. The applicable procedures recommended in Appendix A of Regulatary Guide 1.33, Revision 2, February 1978;
- b. The applicable procedures required to implement the requirements j of NUREG-0737 and supplements thereto; f c. Refueling operations; 1
- j d. Surveillance activities of safety related equipment; J e. Not used.
i J
i NILLSTONE - LalIT 3
- 6-14 Amenhent No. M, M. JM, ygg,128 l
l l 3, 4 l April 24,1996 i
l ADMINISTRATIVE CONTROLS
- f. Not used. .
l j g. Fire Protection Program implementation;
, h. Quality controls for effluent monitoring, using the guidance in j Regulatory Guide 1.21, Rev. 1, June 1974; and t
j i. Padiological Effluent Monitoring and Offsite Dose Calculation
- Mai.Ja1 (REMODCM) implementation except for Section I.E, i Radiological Environmental Monitoring. go
! 6.8.2 a.
b j,[fd,,,II. T N h j
I hit Directo or' Senior Vice President - Millstone was may designate specific procedures and programs, or classes og i of procedures and programs to be reviewed in accordance with the i
Station Qualified Reviewer Program in lieu of review by the POR SORC. The review per the Qualified Revitwer Program shall be in accordance with Specification 6.5.4. ymr3
- b. Procedures and programs listed in Specifi tion 6.8.1, and changes MD t
- Cuo thereto, shal1 be approved by theCib nit Director or Senior Vice PresideniF- M111 stone E6eMe) or oy cognizant Manager or
- Mmf3 Diructors L( who
- c.;*Jnit are designated Director as tse or Senior Vice Approval President Authority by the [pC Nh erMillstone i GeMeik as specified in administrative procedures. The Approval i
Authority for each procedure and program or class of procedure and
- program shall be specified dainistrative orpcede c es.
, OM A Ar O C. 14 0)
- c. Each procedure of Speci at on 6.8 , ana enanges thereto. shall Wir3 be reviewed by the POR / RC and s all be approved by the6hM4eefb j 3 , ,, Director or Senior Vic President - M111stonech"O, or be 4 reviewed and approved in accordance with the Station Qualified i Reviewer Program, prior to implementation. Each procedure of !
Specification 6.8.1 shall be reviewed periodically as set forth in
- administrative procedures.
- - 6.8.3 Temporary changes to procedures of Specification 6.8.1 may be made provided
I 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 enior_ Operator license on the
- unit affected; and 4,,g p y g g c g, g ,7 3
- c. The change is documented, reviewed by th M / % r tation j Qualified Reviewer Program, as ap priate, una appro by the Station Qualified Reviewer Progr Manager orc';.;';= it Director or Senior Vice Presiden - Millstone g within 14 days of implementation.
nuoCN)
MILLSTONE - lit!T 3 eens 6-15 Amenhent No. M, M, y),128
, 6. J.,
i i
l 4/26/94 I
{ ADMINISTRATIVE CONTROLS i
i 6.13 RADIOLOGICAL (REMODCMI EFFLUENT MONITORING AND OFF5fTE DOSE CALCULATION
! Section I, Radiol i
sampling and ana ical Effluent Monitoring Manual (rem), shall outline the materials release is programs to determine the concentration of radioactive i
offsite as well as dose commitments to individuals in those exposure pathways and for those radionuclides released as a result of station i operation.
treatment systemsIt shalland alsoreport specify operating guidelines for radioactive waste content.
Section II the Offsite Dose Calculation Manual (0DCM , shall describe the l
! methodology, and parameters to be used in the calculation o)f offsite dose!
l radioactive gaseous and liquid affluents and in the calculations of gaseous and liquid effluent monitoring instrumentation alarin/ trip setpoints consistent with !
the applicable LCOs contained in these technical specifications. I Changes to the REMODCM:
a.
j Shall be documented and records of reviews performed shall be retained as 4
required by Specification 6.10.30. This documentation shall contain:
4 -
1)
Sufficient information to support the change together with the i appropriate analyses or evaluations justifying the change (s), and i 2)
! A determination that the change will maintain the level of radioactive effluent control required by 10 CFR 20.106, 40 CFR j part 190,
- 10 CFR 50.36a, and Appendix I to 10 CFR part 50 and not adversely j impact the accuracy or reliability of effluent, dose, or setpoint calculations.
!' b.
Shall become effective after review and acce taaea by S0RC and the 1 approval of the Senior Vice President - Millstone
~o C N l i c.
! Shall be submitted to the Commission in the form of a complete, legible copy j of the entire REMM or ODCM, as appropriate, as a part of or concurrent with the Annualwas any change Radioactive made. Effluent Report for the period of the report in which i Each change shall be identified by markings in the
! margin of the affected pages, clearly indicating the area of the page that l was changed, and shall tadicste the date (e.g., month / year) the change was implemented.
5.14 RADIDACTIVE WASTE TREATMENT Unit shall be prepared, approved, maintained and adhered involving the use of offsite a releases of radioactive effluents. These procedures shall specify the REM 0DCM.ppropriate waste treatment systems utilizing the guidance provided.in The Solid Radioactive Waste Treatment system shall be operated in accordance with the Process Control Program to process wet radioactive wastes to meet shippin and burial ground requirements.
gIglSTONE-UNIT 3 6-24 Amendment No. /J, JJ ##,90
Docket No. 50-245 50-336 50-423-B16224 i
l Attachment 2 Millstone Nuclear Power Station, Unit Nos.1,2, and 3 Proposed Revision to Technical Specifications Administrative Controls i Retyped Pages l i
February 1997
ADMINISTRATIVE CE'TROLS 6.1 RESPONSIBILITY l
6.1.1 The Senior Vice President and Chief Nuclear Officer (CNO) - Millstone ,
shall be responsible for overall operation of the Millstone Station Site while I the Millstone Unit 1 Recovery Officer shall be responsible for overall unit '
safe operation and the Director, Unit Operations shall be responsible for j operation of the unit. The Senior Vice President and CN0 - Millstone, Millstone Unit 1 Recovery Officer, and Director, Unit Operations shall each delegate, in writing, the succession to these responsibilities during their absence.
6.2 ORGANIZATION 6.2.1 0FFSITE AND ONSITE ORGANIZATIONS Onsite and offsite organizations shall be established for unit operation and corporate management, respectively. The onsite and offsite organizations shall include the positions for activities affecting the safety of the nuclear power plant.
- a. Lines of authority, responsibility, and communication shall be established and defined for the higher 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 descrip-tions of departmental responsibilities and relationships, and job descriptions for key personnel positions, or in equivalent forms of '
documentation. These requirements shall be documented in the Quality Assurance Topical Report.
- b. The Millstone Unit 1 Recovery Officer shall be responsible for overall unit safe operation and shall have control over those onsite l activities necessary for safe operation and maintenance of the plant.
- c. The Senior ' lice President and CN0 - Millstone shall have corporate responsibility for overall plant nuclear safety and shall take any l measures needed to ensure acceptable performance of the staff in operation, maintaining, and providing technical support to the plant to ensure nuclear safety,
- d. The individuals who train the operating staff and those who carry out health physics and quality assurance functions may report to the appropriate onsite manager; however, they shall have sufficient organizational freedom to ensure their independence from operating pressures.
6.2.2 FACILITY STAFF
- a. Each on duty shift shall be composed of at least the minimum shift crew composition shown in Table 6.2-1.
- b. At least one licensed Operator shall be in the control room when fuel is in the reactor,
- c. At least two licensed Operators shall be present in the control room during reactor start-up, scheduled reactor shutdown and during recovery from reactor trips.
Millstone Unit 1 6-1 Amendment No. 77 JJ, 7J.
0281
ADMINISTRATIVE CONTROLS 6.4 TRAINING 6.4.1 A retraining and replacement training program for the facility staff shall be maintained under the direction of the Senior Vice President and CN0 - Millstone and shall meet or exceed the requirements and l recommendations of Section 5.5 of ANSI N18.1-1971 and 10 CFR Part 55.59. The Director-Nuclear Training has the overall responsibility for the implementation of the Training Program. ,
6.5 REVIEW AND AUDIT 6.5.1 Plant Ooerations Review Committee (PORC)
Function 6.5.1.1 The PORC shall function to advise the Director, Unit Operations on l all matters related to nuclear safety. ,
Comoosition 6.5.1.2 The PORC shall be composed of nine to eleven members. Members shall collectively have experience and expertise in the following areas:
Plant Operations Engineering Reactor Engineering Maintenance Instrumentation and Controls Health Physics l Chemistry Work Planning Quality Assurance The minimum qualifications of PORC members shall be that all members have an academic degree in an engineering or physical science field, or hold a management position, and have a minimum of five years technical experience in their respective field of expertise. The members of PORC shall be appointed in writing by the Director, Unit Operations. The Chairperson and alternate Chairperson of the PORC shall be drawn from the PORC members and be appointed in writing by the Director, Unit Operations. l Alternates 6.5.1.3 Alternate members shall be appointed in writing by the PORC Chairperson to serve on a temporary basis; however, no more than two alternates shall participate in PORC activities at any one time.
Millstone Unit 1 6-5 Amendment No. JJ, JJ, 77, JJ, 0282
I ADMINISTRATIVE CONTROLS Meetina Freauency 6.5.1.4 The PORC shall meet at least once per calendar month and as convened by l
the PORC Chairperson.
Quorum l 6.5.1.5 A quorum of the PORC shall consist of the Chairperson, or Vice Chairperson, and four members including alternates. l Resnonsibilities 6.5.1.6 The PORC shall be responsible for:
- a. Review of 1) all procedures, except common site procedures, required by Specification 6.8 and changes thereto, 2) all programs, except common site programs, required by Specification 6.8 and changes thereto, 3) any other proposed procedures, programs, or changes thereto, as determined by the Director, Unit Operations to affect nuclear safety. Procedures and programs required by Specification 6.8 that are designated for review and approval by the Station Qualified Reviewer Program do not require PORC review.
- b. Review of all proposed tests and experiments that affect nuclear safety.
- c. Review of all proposed changes to Sections 1.0 - 5.0 of these Technical Specifications.
- d. Review of all proposed changes or modifications to plant systems or equipment that affect nuclear safety.
- e. Investigation of all violations of the Technical Specifications and preparation and forwarding of a report covering evaluation and recommendations to prevent recurrence to the Senior Vice President and CNO - Millstone and to the Chairperson of the Nuclear Safety Assessment Board,
- f. Review of all REPORTABLE EVENTS.
- g. Review of facility operations to detect potential safety hazards,
- h. Performance of special reviews and investigations and reports thereon as requested by the Chairperson of the Nuclear Safety Assessment Board.
- i. Render determinations in writing if any item considered under 6.5.1.6(a) through (d) above, as appropriate and as provided by 10CFR50.59 or 10CFR50.92, constitutes an unreviewed safety question or requires a significant hazards consideration determination.
Millstone Unit 1 6-6 Amendment No. 1, 77, 77 77, 71, un
1, ADMINISTRATIVE CONTR0LS 1 j. Review of the unit-specific Fire Protection Program and
! implementing procedures.
Authority 6.5.1.7 The PORC shall:
, a. Recommend to the Director, Unit Operations written approval or l disapproval of items considered under 6.5.1.6(a) through (d) above.
- b. Provide immediate written notification to the Senior Vice President and CN0 - Millstone, Millstone Unit 1 Recovery Officer, 1 and the Chairperson of the Nuclear Safety Assessment Board of disagreement between the PORC and the Director, Unit Operations; however, the Directcr, Unit Operations shall have responsibility for resolution of such disagreements pursuant to 6.1.1 above.
Records l 6.5.1.8 The PORC shall maintain written minutes of each meeting and copies j shall be provided to the Senior Vice President and CNO - Millstone and l
- Chairperson of the Nuclear Safety Assessment Board, j 6.5.2 Site Operations Review Committee (SORC)
Function l
j 6.5.2.1 The SORC shall function to advise the Senior Vice President and CN0 -
i Millstone on all matters related to nuclear safety of the entire Millstone Station Site.
6.5.2.2 The 50RC shall be composed of the:
! Chairprson: Senior'Vice President and CN0 - Millstone Member: Director, Unit Operations Member: unit 2 Unit Director 4 Member: Unit 3 Unit Director Member: Director, Nuclear Services
- Member
- Manager, General Services Member: Designated Member of Unit 1 PORC
, Member: Designated Member of Unit 2 PORC Member: Designated Member of Unit 3 PORC Member: Designated Member of Nuclear Oversight l The Senior Unit Director / Director, Unit Operations in attendance shall l be the Vice Chairperson.
~
l Alternates l
6.5.2.3 Alternate members shall be appointed in writing by the SORC Chairperson i
to serve on a temporary basis; however, no more than two alternates i shall participate in 50RC activities at one time. (
I Nillstone Unit 1 6-7 Amendment No. 77,77,77,71,77, 0283 i l
ADNINISTRATIVE CONTROLS l
Meetina Freauency 6.5.2.4 The 50RC shall meet at least once per six months and as convened by the SORC Chairperson.
AIL 9i$5 6.5.2.5 A quorum of the 50RC shall consist of the Chairperson or Vice Chairperson and five members including alternates.
Responsibilities 6.5.2.6 The 50RC shall be responsible fcr:
- a. Review of 1) all common site procedures required by Specification 6.8 and changes thereto, 2) all common site programs, required by.
Specification 6.8 and changes thereto, 3) any other proposed procedures, programs, or changes thereto as determined by the Senior Vice President and CNO - Nillstone to affect site nuclear l safety. Common site programs and procedures required by Specification 6.8 that are designated for review and approval by the Station Qualified Review Program do not require SORC review.
I b. Review of all proposed changes to Section 6.0, " Administrative Controls", of these Technical Specifications.
! c. Performance of special reviews and investigations and reports as j requested by the Chairperson of the Nuclear Safety Assessment j Board.
- d. Not used.
. e. Not used. l t :
, f. Review of all common site proposed tests and experiments that l affect nuclear safety. l a
Review of all common site proposed changes or modifications to j g.
systems or equipment that affect nuclear safety.
- h. Render determinations in writing, or meeting minutes if any item considered under 6.5.2.6(a) through (g) above, as appropriate and 4
as provided by 10CFR50.5g or 100FR50.92, constitutes an unreviewed safety question or requires a significant hazards consideration determination.
- i. Review of the common site Fire Protection Program and implementing procedures.
i Nillstone Unit 1 6-8 Amendment No. JJ, 7f, 77, 71, JJ.
0282
l ADMINISTRATIVE CONTROLS Authority 6.5.2.7 The SORC shall:
- a. Recommend to the Senior Vice President and CN0 - Millstone written l l
.. approval or disapproval, in meeting minutes, of items considered ;
under 6.5.2.6(a) through (g) above.
- b. Provide immediate written notification, or meeting minutes, to the President and Chief Executive Officer (CE0) and the Chairperson of the Nuclear Safety Assessment Board of disagreement between the SORC and the Senior Vice President and CNO - Millstone; however, the Senior Vice President and CNO - Millstone shall have responsibility for resolution of such disagreements pursuant to 6.1.1 above.
Records 6.5.2.8 The SORC shall maintain written minutes of each meeting and copies shall be provided to the Senior Vice President and CN0 - Millstone and l Chairperson of the Nuclear Safety Assessment Board.
6.5.3 NUCLEAR SAFETY ASSESSMENT BOARD (NSAB)
FUNCTION 6.5 3.1 The minimum qualifications of NSAB members are as follows:
- a. The Chairperson and NSAB members shall have:
l 1. An academic degree in an engineering or physical science field, or hold a senior management position, and
- 2. A minimum of five years technical experience in their respective field of expertise.
, b. The NSAB shall have experience in and shall function to provide
! independent oversight review and audit of designated activities in the areas of:
- 1. Nuclear power plant operations;
- 2. Nuclear engineering; !
- 3. Chemistry and radiochemistry; !
- 4. Metallurgy;
- 5. Instrumentation and control;
- l. 6. Radiological safety; i
l I Millstone Unit 1 6-9 Amendment No. 77, pp, 77, 77, 77, 71,
- M i
l
i ADNINISTRATIVE CONTROLS 3 _._, ,
ns 1 7. Mechanical and electrical engineering; and i
- 8. Quality assurance practices, a
The NSAB serves to advise the President and CEO on matters related to nuclear safety and notify the President and CEO within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> of a safety significant disagreement between the NSAB and the organization
! or function being reviewed.
1 COMPOSITION 6.5.3.2 The President and CEO shall appoint, in writing, a minimum of seven l
- members to the NSAB and shall designate from this membership, in j writing, a Chairperson and a Vice Chairperson. The membershio shall i function to provide inlependent review and audit in the areas listed in Specification 6.5.3.1.
l ALTERNATES 6.5.3.3 All alternate members shall be appointed, in writing, by the President i and CE0; however, no more than two alternates shall participate as
- members in NSAB activities at any one time. ,
MEETING FREQUENCY j 6.5.3.4 The NSAB shall meet at least once per calendar quarter.
. DUORUM i
! 6.5.3.5 The quorum of the NSAB shall consist of a majority of NSAB members
! including the Chairperson or Vice Chairperson. No more than a minority of the quorum shall have line responsibility for operation of the same j Northeast Utilities' nuclear unit. No more than two alternates shall l
be appointed as members at any meeting in fulfillment of the quorum
- requirements.
REVIEW RESPONSIBILITIES
- 6.5.3.6 The NSAB shall be responsible for the review of
- a. The safety evaluations for changes to procedures, equipment, or
, systems, and tests or experiments completed under the provisions
- of 10 CFR 50.59, to verify that such actions did not constitute an unreviewed safety question as defined in 10 CFR 50.59;
- b. Proposed changes to procedures, equipment, or systems that involve 4 an unreviewed safety question as defined in 10 CFR 50.59;
! c. Proposed tests or experiments that involve an unreviewed safety
- question as defined in 10 CFR 50.59; 1
N111 stone Unit 1 6-10 Amendment No. 77, 77, 77 71 0282
ADMINISTRATIVE CONTROLS
- d. Proposed changes to Technical Specifications and the Operating License;
- e. Violations of applicable codes, regulations, orders, license requirements, or internal procedures having nuclear safety significance;
- f. All Licensee Event Reports required by 10 CFR 50.73;
- g. Indications of significant unanticipated deficiencies in any aspect of design or operation of structures, systems, or components that could affect nuclear safety; h Significant accidental, unplanned, or uncontrolled radioactive releases, including corrective actions to prevent recurrence;
- i. Significant operating abnormalities or deviations from normal and expected performance of equipment that could affect nuclear safety;
- j. The performance of the corrective action program; and
- k. Audits and audit plans.
Reports or records of these reviews shall be forwarded to the President and CEO within 30 days following completion of the review.
AUDIT PROGRAM RESPONSIBILITIES 6.5.3.7 The NSAB audit program shall be the responsibility of the Audit and Evaluation Department. NSAB audits shall be performed at least once per 24 months in accordance with Nuclear Group Procedures and shall encompass:
- a. The conformance of unit operation to provisions contained within the Technical Specifications and applicable license conditions;
- b. The training and qualifications of the unit staff;
- c. The implementation of all programs required by Specification 6.8;
- d. The Fire Protection Program and implementing procedures.
- e. The fire protection equipment and program implementation utilizing either a qualified offsite license fire protection engineer or an outside independent fire protection consultant.
- f. Actions taken to correct deficiencies occurring in equipment, !
structures, systems, components, or method of operation that affect nuclear safety; and Millstone Unit 1 6-11 Amendment No. J. 77 77, 71, 0282
i ADMINISTRATIVE CONTROLS
- g. Other activities and documents as requested by the President and CEO.
RECORDS 6.5.3.8 Written records of reviews and audits shall be maintained. As a
.- minimum these records shall include:
- a. Results of the activities conducted under the provisions of Section 6.5.3; i
l b. Recommended approval or disapproval of items considered under l Specifications 6.5.1.6.a through 6.5.1.6.d, and 6.8; and l
l c. Determination as to whether each item considered under
! Specification 6.5.1.6.a, 6.5.1.6.b, 6.5.1.6.d, and 6.8 constitute an unreviewed safety question as defined in 10 CFR 50.59.
6.5.4 Station Qualified Reviewer Proaram Function
! 6.5.4.1 The Director, Unit Operations or Millstone Unit 1 Recovery Officer, or Senior Vice President and CN0 - Millstone may establish a Station Qualified Reviewer Program whereby required reviews of designated procedures or classes of procedures required by Specifications 6.5.1.6.a and 6.5.2.6.a are performed by Station Qualified Reviewers and approved by designated managers. These reviews are in lieu of reviews by the PORC or SORC. However, procedures which require a 10CFR50.59 evaluation must be reviewed by the PORC or SORC.
Resoonsibilities 6.5.4.2 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 I 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 managers or directors as having specific expertise required to assess a particular procedure, program, or change. Cross-disciplinary reviewers may function as a committee.
- 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 100FR50.59 to verify that l
Millstone Unit 1 6-12 Amendment No. JJ, 77, 71.
0282
1 l
ADMINISTRATIVE CONTROLS l an unreviewed safety question does not exist. This screening will be performed by personnel trained and qualified in performing 10CFR50.59 evaluations.
- e. Provide for written recommendation by the Qualified Reviewer (s) to the responsible Manager for approval or disapproval of procedures
, and programs considered under Specification 6.5.1.6.a and 6.5.2.6.a and that the procedure or program was screened by a qualified individual and found not to require a 10CFR50.59 evaluation.
6.5.4.3 If the responsible manager determines that a new program, procedure, or change thereto requires a 10CFR50.59 evaluation, that manager will ensure the required evaluation is performed to determine if the new procedure, program, or change involves an unreviewed safety question.
The new procedure, program, or change will then be forwarded with the 10CFR50.59 evaluation to PORC or 50RC for review. l I
6.5.4.4 Personnel recommended to the Station Qualified Reviewers shall be designated in writing by the Director, Unit Operations, Millstone Unit 1 Recovery Officer, or Senior Vice President and CNO - Millstone for each procedure, program, or class of procedure or program within the scope of the _ Station Qualified Reviewer Program.
6.5.4.5 Temporary procedure changes shall be made in accordance with Specification 6.8.3 with the exception that changes to procedures for which reviews are assigned to Qualified Reviewers will be reviewed and approved as described in Specification 6.5.4.2.
Records 6.5.4.6 The review of procedures and programs performed under the Station Qualified Reviewer Program shall be documented in accordance with administrative procedures.
Trainina and Qualification 6.5.4.7 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:
I
- 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 experienct; OR
- c. An equivalent combination of education and experience as approved by a department manager.
Millstone Unit 1 6-13 Amendment No. JJ, 0292
i l ADMINISTRATIVE CONTROLS j 6.6 REPORTABLE EVENT ACTION ;
l 6.6.1 The following actions shall be taken for REPORTABLE EVENTS:
i
, a. The Commission shall be notified and a report submitted l l pursuant to the requirement of 10 CFR 50.73.
j .- b. Each REPORTABLE EVENT shall be reviewed by the PORC and the i results of this review shall be submitted to the Chairperson of I the NSAB and the Senior Vice President and CNO - Millstone. l l 6.7 SAFETY LIMIT VIOLATION
- 6.7.1 The following actions shall be taken in the event a Safety Limit is
! violated:
i j a. The unit shall be placed in at least HOT STANDBY within two hours.
i I
- b. The NRC Operations Center shall be notified by telephone as soon as possible and in all cases within one hour. The Senior Vice President and CNO - Millstone and the Chairperson of the NSAB shall be notified within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
l
- c. A Safety Limit Violation Report shall be prepared. The report .
shall be reviewed by the PORC. This report shall describe '
(1) applicable circumstances preceding the violation, (2) effects l of the violation upon facility components, systems or structures, 1 and (3) corrective action taken to prevent recurrence. I
- d. The Safety Limit Violation Report shall be submitted to the Commission, the Chairperson of the NSAB and the Senior Vice President and CNO - Millstone within 14 days of the violation.
- e. Operation shall not be resumed until authorized by the Commission.
6.8 PROCEDURES 6.8.1 Written procedures shall be established, implemented and maintained covering the activities referenced below.
- a. The applicable procedures recommended in Appendix "A" of Regulatory Guide 1.32, February,1978.
- b. Refueling operations.
- c. Surveillance activities of safety related equipment.
- d. Not used.
l
- e. Not used.
- f. Fire Protection Program Implementation.
Millstone Unit 1 6-14 Amendment No. J pp. 77, JJ. 77, 0292
i ADMINISTRATIVE CONTROLS
]
i l g. Quality Control for effluent monitoring usirg the guidance in
, Regulatory Guide 1.21 Rev.1, June 1974.
- h. Radiological Effluent Monitoring and Offsite Dose Calculation Manual
. (REMODCM) implementation, except for Section I.E., Radiological Environmental Monitoring.
6.8.2 a. The Director, Unit Operations or Millstone Unit 1 Recovery Officer, or Senior Vice President and CN0 - Millstone may designate specific procedures and programs, or classes of procedures and programs to be reviewed in accordance with the Station Qualified Reviewer Program in lieu of review by the PORC or SORC. The review per the Qualified l l Reviewer Program shall be in accordance with Specification 6.5.4.
l b. Procedures and programs listed in Specification 6.8.1, and changes j thereto, shall be approved by the Director, Unit Operations or Senior i
Vice President and CNO - Millstone or by cognizant Manager or i Directors who are designated as the Approval Authority by the PORC or
] SORC or Senior Vice President and CNO - Millstone as specified in administrative procedures. The Approval Authority for each procedure i and program or class of procedure and program shall be specified in administrative procedures.
'l l c. Each procedure of Specification 6.8.1, and changes thereto, shall be i reviewed by the PORC or SORC and shall be approved by the Director, Unit Operations or Senior Vice President and CNO - Millstone, or be reviewed and approved in accordance with the Station Qualified i
Reviewer Program, prior to implementation. Each procedure of
- Specification 6.8.1 shall be reviewed periodically as set forth in administrative procedures.
6.8.3 Temporary changes to procedures cf 6.8.1 above may be made provided:
- a. The intent of original procedure is not altered.
l b. The change is approved by two members of the plant management staff, i at least one of whom holds a Senior Reactor Operator's License on the l
unit affected.
i c. The change is documented, reviewed by the PORC or 50RC, or the l Station Qualified Reviewer Program, as applicable, and approved by
- the Director, Unit Operations, or the Senior Vice President and CN0 -
i Millstone or Station Qualified Reviewer Program Department Manager within 14 days of implementation.
- 6.8.4 Written procedures shall be established, implemented and maintained i covering Section I.E, Radiological Environmental Monitoring, of the
- REMODCM.
l i
Millstone Unit 1 6-15 Amendment No. 5 , 77, # ,
0382
i l ADMINISTRATIVE CONTROLS 6.15 RADIOLOGICAL EFFLUENT MONITORING AND OFFSITE DOSE CALCULATION MANUAL (REMODCM)
' Section I, Radiological Effluents Monitoring Manual (REM), shall outline the sampling and analysis programs to determine the concentration of radioactive
< materials released offsite as well as dose commitments to individuals in those
{ exposure pathways and for those radionuclides released as a result of station
- operation. It shall also specify operating guidelines for radioactive waste treatment systems and report content.
i Section II, the Offsite Dose Calculation Manual (00CM), shall describe the
! methodology and parameters to be used in the calculation of offsite doses due
? to radioactive gaseous and liquid effluents and in the calculations of gaseous and liquid effluent monitoring instrumentation alarsVtrip setpoints consistent with the applicable LC0's contained in these technical specifications.
Changes to the REMODCM:
- a. Shall be documented and records of reviews performed shall be retained as required by Specification 6.10.2.m. This documentation shall contain:
- 1) Sufficient information to support the change together with the appropriate analyses or evaluations justifying the change (s),
and
- 2) A determination that the change will maintain the level of radioactive effluent control required by 10 CFR 20.106, 40 CFR Part 190, 10 CFR 50.36a, and Appendix I to 10 CFR Part 50 and not adversely impact the accuracy or reliability of eff!uent, dose, or setpoint calculations.
- b. Shall become effective after review and acceptance by SORC and the approval of the Senior Vice President and CNO - Millstone. l
- c. Shall be submitted to the Commission in the form of a complete, legible copy of the entire REM or ODCM, as appropriate, as a part of or concurrent with the Annual Radioactive Effluent Report for the period of the report in which any change was made. Each change shall be identified by markings in the margin of the affected pages, clearly indicating the area of the page that was changed, and shall indicate the date (e.g., month / year) the change was implemented.
Millstone Unit 1 6-23 Amendment No. 77,77,77,77, 0283
! ADMINISTRATIVE CONTROLS l
4 j 6.1 RESPONSIBILITY a
j 6.1.1 The Senior Vice President and Chief Nuclear Officer (CNO) -
1 Millstone shall be responsible for overall operation of the Millstone Station i Site while the Millstone Unit 2 Recovery Officer shall be responsible for i overall unit safe operation and the Unit 2 Unit Director shall be responsible i for operation of the-unit. The Senior Vice President and CN0 - Millstone, i Millstone Unit 2 Recovery Officer and Unit 2 Unit Director shall each delegate in writing the succession to these responsibilities during their absence.
! 6.2 ORGANIZATION
! 6.2.1 0FFSITE AND ONSITE ORGANIZATIONS
) Onsite and offsite organizations shall be established for unit operation and
! corporate management, respectively. The onsite and offsite organizations j shall include the positions for activities affecting the safety of the nuclear
} power plant. l 4
} a. Lines of authority, responsibility, and communication shall be i established and defined for the higher management levels through intermediate levels to and including all operating organization i
positions. These relationships shall be documented and updated, as appropriate, in the form of organization charts, functional descrip-
! tions of departmental responsibilities and relationships, and job i descriptions for key personnel positions, or in equivalent forms of i documentation. These requirements shall be documented in the Quality Assurance Topical Report.
- b. The Millstone Unit 2 Recovery Officer shall be responsible for
- overall unit safe operation and shall have control over those onsite l l activities necessary for safe operation and maintenance of the
- pl ant.
I l'
- c. The Senior Vice President and CN0 - Millstone shall have corporate responsibility for overall plant nuclear safety and shall take any l
, measures needed to ensure acceptable performanis of the staff in
- operation, maintaining, and providing technied ispport to the plant j to ensure nuclear safety.
I d. The individuals who train the operating staff and those who carry out health physics and quality assurance functior.s may report to the l appropriate onsite manager; however, they shall have sufficient
! organizational freedom to ensure their independence from operating
- pressures.
) 6.2.2 FACILITY STAFF i
- a. Each on duty shift shall be composed of at least the minimum shift crew composition shown in Table 6.2-1.
- b. At least one licensed Operator shall be in the control room when 2 fuel is in the reactor.
i c. At least two licensed Operators shall be present in the control room
! during reactor start-up, scheduled reactor shutdown and during j recovery from reactor trips.
l Millstone - Unit 2 6-1 Amendment No. M , M M , # ,
' om #,1#, IM, Hi, Hi, 1H,
1 ADMINISTRATIVE CONTROLS l
- 6.4 TRAINING i
. A retraining and replacement training program for the facility staff shall be maintained under the direction of the Senior Vice President and CN0 -
Millstone and shall meet or exceed the requirements and recommendations of Section 5.5 of ANSI N18.1-1971 and 10 CFR Part 55.59. The Director-Nuclear i Training has the overall responsibility for the implementation of the Training Program.
l 6.5 REVIEW AND AUDIT 6.5.1 Plant Doerations Review Committee (PORC) l Function
! 6.5.1.1 The PORC shall function to advise the Unit 2 Unit Director on all
- matters related to nuclear safety.
i
- Comoosition l 6.5.1.2 The PORC shall be composed of nine to eleven members. Members shall 3
collectively have experience and expertise in the following areas:
! Plant Operations j Engineering i Reactor Engineering
- Maintenance Instrumentation and Controls
,. Health Physics Chemistry Work Planning l Quality Assurance The minimum qualifications of PORC members shall be that all members have an academic degree in an engineering or physical science field, or hold a management position, and have a minimum of five years technical experience in their respective field of expertise. The membirs of PORC shall be be appointed in writing by the Unit 2 Unit l Director. The Chairperson and alternate Chairperson of the PORC shall be drawn from the PORC members and be appointed in writing by the Unit 2 Unit Director. l Alternates 6.5.1.3 Alternate members shall be appointed in writing by the PORC Chairperson to serve on a temporary basis; however, no more than two alternates shall participate in PORC activities at any one time.
Millstone Unit 2 6-5 Amendment No. Jp), 17J JJJ.
ores JPP
ADNINISTRATIVE CONTROLS Meetino Freauency 4
6.5.1.4 The PORC shall meet at least once per calendar month and as convened by the PORC Chairperson.
Ouorum 6.5.1.5 A quorum of the PORC shall consist of the Chairperson, or Vice Chairperson, and four members including alternates. l Resoonsibilities 6.5.1.6 The PORC shall be responsible for:
- a. Review of 1) all procedures, except common site procedures, required by Specification 6.8 and changes thereto, 2) all programs, except common site programs, required by Specification 6.8 and changes thereto, 3) any other proposed procedures, programs, or changes thereto as determined by the Unit 2 Unit Director to affect nuclear safety. Procedures and l programs required by Specification 6.8 that are designated for review and approval by the Station Qualified Reviewer Program do not require PORC review.
- b. Review of all proposed tests and experiments that affect nuclear safety.
- c. Review of all proposed changes to Sections 1.0 - 5.0 of these Technical Specifications.
- d. Review of all proposed changes or modifications to plant systems or equipment that affect nuclear safety.
- e. Investigation of all violations of the Technical Specifications and preparation and forwarding of a report covering evaluation and recommendations to prevent recurrence to the Senior Vice President and CN0 - Millstone and to the Chairperson of the Nuclear Safety Assessment Board.
- f. Review of all REPORTABLE EVENTS.
- g. Review of facility operations to detect potential safety hazards.
- h. Performance of special reviews and investigations and reports thereon as requested by the Chairperson of the Nuclear Safety Assessment Board.
- 1. Render determinations in writing if any item considered under 6.5.1.6(a) through (d) above, as appropriate and as provided by 10CFR50.59 or 10CFR50.92, constitutes an unreviewed safety question or requires a significant hazards consideration determination.
J. Review of the fire protection program and implementing procedure.
Nillstone Unit 2 6-6 Amendment No. J7, 77, 77, 19, 111, 191 179, 199, 191, 193
ADMINISTRATIVE CONTLOLS ;
htierjty 6.5.1.7 The PORC shall: 1
- a. Recommend to the Unit 2 Unit Director written approval or disapproval of items considered under 6.5.1.6(a) through (d) above. !
- b. Provide immediate written notification to the Senior Vice ;
President and CN0 - Millstone, Millstone Unit 2 Recovery 1 Officer and the Chairperson of the Nuclear Safety Assessment Board of disagreement between the PORC and the Unit 2 Unit Director; however, the Unit 2 Unit Director shall have '
responsibility for resolution of such disagreements pursuant to )
6.1.1 above. '
Records 6.5.1.8 The PORC shall maintain written minutes of each meeting and copies shall be provided to the Senior Vice President and CN0 - Millstone I and Chairperson of the Nuclear Safety Assessment Board.
6 . 5. 7. Site Operations Review Committee (SORC)
Function 6.5.2.1 The SORC shall function to advise the Senior Vice President and CNO - Millstone on all matters related to nuclear safety of the entire Millstone Station Site.
Composition 6.5.2.2 The SORC shall be composed of the:
Chairperson: Senior Vice President and CN0 - Millstone Member: Director, Unit Operations Member: Unit 2 Unit Director !
Member: Unit 3 Unit Director !
Member: Director, Nuclear Services Member: Manager, General Services Member: Designated Member of Unit 1 PORC Member: Designated Member of Unit 2 PORC Member: Designated Member of Unit 3 PORC Member: Designated Member of Nuclear Oversight !
The senior Unit Director / Director, Unit Operations in attendance !
shall be the Vice-Chairperson.
Alternates:
6.5.2.3 Alternate members shall be appointed in writing by the SORC Chairperson to serve on a temporary basis; however, no more than two alternates shall participate in SORC activities at one time.
Millstone Unit 2 6-7 Amendment No. JJJ, 17J, Jpp.
om Jpp,
ADMINISTRATIVE CONTROLS Meetina Freauency 6.5.2.4 The SORC shall meet at least once per six months and as convened by the SORC Chairperson.
Quorum i
6.5.2.5 A quorum of the SORC shall consist of the Chairperson or Vice Chairperson and five members including alternates.
- Resnonsibilities
- 6.5.2.6 The SORC shall be responsible for:
1 4
- a. Review of 1) all common site procedures required by Specifi-4 cation 6.8 and changes thereto, 2) all common site programs,
- required by Specification 6.8 and changes thereto, 3) any other
- proposed procedures, programs, or changes thereto as determined by the Senior Vice President and CN0 - Millstone to affect site l nuclear safety. Common site programs and proceoures required by Specification 6.8 that are designated for review and approval by the Station Qualified Reviewer Program do no
- require SORC review.
- b. Review of all proposed changes to Section 6.0 " Administrative
- Controls" of these Technical Specifications.
j c. Performance of special reviews and investigations and reports as requested by the Chairperson of the Nuclear Safety Assessment Board.
4 d. Not used.
I
- e. Not used.
I f. Review of all common site proposed tests and experiments that j affect nuclear safety.
- g. Review of all common site proposed changes or modifications to j systems or equipment that affect nuclear safety.
i h. Render determinations in writing or meeting minutes if any item 4
considered under 6.5.2.6(a) through (g) above, as appropriate and as provided by 10CFR50.59 or 10CFR50.92, constitutes an i unreviewed safety question or requires a significant hazards
- consideration determination.
- 1. Review of the common site fire protection program and implementing procedures, i
i i
Millstone Unit 2 6-8 Amendment No. # , # , 1 9 , 17#,
- om 1%, Hi,19, IM, 1
a
} ADMINISTRATIVE CONTROLS l Authority i 6.5.2.7 The SORC shall:
- a. Recommend to the Senior Vice President and CN0 - Millstone l written approval or disapproval in meeting minutes of items j considered under 6.5.2.6(a) through (g) above. l
) b. Provide immediate written notification or meeting minutes to l the President and Chief Executive Officer (CEO) and the !
l Chairperson of the Nuclear Safety Assessment Board of
- disagreement between the SORC and the Senior Vice President and i CN0 - Millstone; however, the Senior Vice President and CN0 -
Millstone shall have responsibility for resolution of such !
! disagreements pursuant to 6.1.1 above. '
- I l Records
- 6.5.2.8 The 50RC shall maintain written minutes of each meeting and copies j shall be provided to the Senior Vice President and CN0 - Millstone l
- and Chairperson of the Nuclear Safety Assessment Board.
i 6.5.3 NUCLEAR SAFETY ASSESSMENT BOARD (NSAB)
]
l FUNCTION i
i 6.5.3.1 The minimum qualifications of NSAB members are as follows:
- a. The Chairperson and NSAB members shall have
I
- 1. An academic degree in an engineering or physical science field, or hold a senior management position, and j 2. A minimum of five years technical experience in their i respective field of expertise.
(
) b. The NSA8 shall have experience in and shall function to provide
! independent oversight review and audit of designated activities
) in the areas of:
- 1. Nuclear power plant operations;
- 2. Nuclear eagineering;
- 3. Chemistry and radiochemistry; j i 4. Metallurgy;
- 5. Instrumentation and control;
- 6. Radiological safety; '
i
- 7. Mechanical and electrical engineering; and i
i 8. Quality assurance practices.
Nillstone Unit 2 6-9 Amendment Nos. Jp, (), 77.
l ones Flo ille ille 119,199,191, l .
1 1
j ADMINISTRATIVE CONTROLS
! )
i i The NSAB serves to advise the President and CEO on matters related 1 to nuclear safety and notify the President and CEO within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />
- of a safety significant disagreement between the NSAB and the i i organization or function being reviewed.
COMPOSITION i 6.5.3.2 The President and CEO shall appoint, in writing, a minimum of seven l ;
members to the NSAB and shall designate from this membership, in i i
writing, a Chairperson and a Vice Chairperson. The membership shall l function to provide independent review and audit in the areas listed )
4 in Specification 6.5.3.1. '
\
l ALTERNATES i
6.5.3.3 All alternate members shall be appointed, in writing, by the President and CE0; however, no more than two alternates shall j participate as members in NSAB activities at any one time.
MEETING FREQUENCY l 6.5.3.4 The NSAB shall meet at least once per calendar quarter.
$ 000 RUM i
i 6.5.3.5 The quorum of the NSAB shall consist of a majority of NSAB members
! including the Chairperson or Vice Chairperson. No more than a l minority of the quorum shall have line responsibility for operation 1
of the same Northeast Utilities' nuclear unit. No more than two alternates shall be appointed as members at any meeting in fulfillment of the quorum requirements.
j REVIEW RESPONSIBILITIES l 6.5.3.6 The NSAB shall be responsible for the review of:
4 i a. The safety evaluations for changes to procedures, equipment, or
- systems, and tests or experiments completed under the i
provisions of 10 CFR 50.59, to verify that such actions did not '
constitute an unreviewed safety question as defined in 10 CFR 50.59;
- b. Proposed changes to procedures, equipment, or systems that involve an unreviewed safety question as defined in 10 CFR 50.59;
- c. Proposed tests or experiments that involve an unreviewed safety question as defined in 10 CFR 50.59;
- d. Proposed changes to Technical Specifications and the Operating License; N111 stone Unit 2 6-10 Amendment No. J7, (), JJ.
ones 15$,191,199,191
ADMINISTRATIVE CONTROLS i
! e. Violations of applicable codes, regulations, orders, license !
- requirements, or internal procedures having nuclear safety i
significance; I i
j f. All Licensee Event Reports required by 10 CFR 50.73; 1 i
- g. Indications of significant unanticipated deficiencies in any
, aspect of design or operation of structures, systems, or
. components that could affect nuclear safety;
- h. Significant accidental, unplanned, or uncontrolled radioactive !
J releases, including corrective actions to prevent recurrence;
! 1. Significant operating abnormalities or deviations from normal l and expected performance of equipment that could affect nuclear
- safety;
- j. The performance of the corrective action program; and I
- k. Audits and audit plans.
! Reports or records of these reviews shall be forwarded to the 1 President and CEO within 30 days following completion of the review. l
]
AUDIT PROGRAN RESPONSIBILITIES l
! 6.5.3.7 The NSAB audit program shall be the responsibility of the Audits and i j Evaluation Department. NSAB audits shall be performed at least once j per 24 months in accordance with Nuclear Group Procedures and shall l
- encompass:
i 1
- a. The conformance of unit operation to provisions contained within the Technical Specifications and applicable license conditions;
- b. The training and qualifications of the unit staff;
- c. The implementation of all programs required by Specification 6.8;
- d. The Fire Protection Program and implementing procedures.
- e. The fire protection equipment and program implementation utilizing either a qualified offsite license fire protection engineer or an outside independent fire protection consultant.
- f. Actions taken to correct deficiencies occurring in equipment, structures, systems, components, or method of operation that affect nuclear safety; and
- g. Other activities and documents as requested by the President and CEO.
Millstone Unit 2 6-11 Amendment No. 17, JJ, JJ. ;
osee 95, life 111,lif,191,19f
ADMINISTRATIVE CONTROLS RECORDS 6.5.3.8 Written records of reviews and audits shall be maintained. As a minimum these records shall include:
- a. Results of the activities conducted under the provisions of Section 6.5.3;
- b. Recommended approval or disapproval of items considered under Specifications 6.5.1.6.a through 6.5.1.6.d, and 6.8; and
- c. Determination as to whether each item considered under Specification 6.5.1.6.a, 6.5.1.6.b, 6.5.1.6.d, and 6.8 constitute an unreviewed safety question as defined in 10 CFR 50.59.
6.5.4 Station Qualified Reviewer Proaram Function j 6.5.4.1 The Unit 2 Unit Director or Millstone Unit 2 Recovery Officer or ,
Senior Vice President and CN0 - Millstone may establish a Station l Qualified Reviewer Program whereby required reviews of designated procedures or classes of procedures required by Specifications 6.5.1.6.a and 6.5.2.6.a are performed by Station Qualified Reviewers i and approved by designated managers. These reviews are in lieu of '
reviews by the PORC or SORC. However, procedures which require a 10CFR50.59 evaluation must be reviewed by the PORC or SORC.
Responsibilities 6.5.4.2 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 Managers or Directors as having specific expertise required to assess a particular procedure, program, or change. Cross-disciplinary reviewers may function as a committee.
- 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 10CFR50.59 to verify that an unreviewed safety question does not exist. This screening will be performed by personnel trained and qualified in performing 10CFR50.59 evaluations.
Millstone Unit 2 6-12 Amendment Nos. JJ, JJ, JJ, JJJ, JJJ 0206
j j ADNINISTRATIVE CONTROLS a
I
]
4 e. Provide for written recommendation by the Qualified Reviewer (s) to the responsible Manager for approval or di:: approval of 4 procedures and programs considered under Specification !
6.5.1.6.a and 6.5.2.6.a and that the procedure or program was screened by a qualified individual and found not to require a j 10 CFR 50.59 evaluation.
i 6.5.4.3 If the responsible manager determines that a new program, procedure, i or change thereto requires a 10 CFR 50.59 evaluation, that Manager
- will ensure the required evaluation is performed to determine if the
] new procedure, program, or change involves an unreviewed safety
! question. The new procedure, program, or change will then be '
forwarded with the 10 CFR 50.59 evaluation to PORC or SORC for
! review.
! 6.5.4.4 Personnel recommended to be Station Qualified Reviewers shall be j designated in writing by the Unit 2 Unit Director or Millstone Unit ,
2 Recovery Officer or Senior Vice President and CN0 - Millstone for '
i each procedure, program, or class of procedure or program within the l scope of the Station Qualified Reviewer Program.
i l' 6.5.4.5 Temporary procedure changes shall be made in accordance with l Specification 6.8.3 with the exception that changes to procedures l i for which reviews are assigned to Qualified Reviewers will be !
reviewed and approved as described in Specification 6.5.4.2.
j Records
! 6.5.4.6 The review of procedures and programs performed under the Station
! Qualified Reviewer Program shall be documented in accordance with
! administrative procedures.
1 i
Trainina and Qualification l 6.5.4.7 The training and qualification requirements of personnel designated j 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 i technical discipline, and two years of nuclear power plant i experience; i'
- b. Six years of nuclear power plant experience; l OR 1
) c. An equivalent combination of education and experience as approved by a Department Manager.
l
+
l l Millstone Unit 2 6-13 Amendment Nos. Jp7,
! 0258
_ . _ _ _ . _ _ . _ _ _ _ _ _ _ _ . _ _ _ _ _ ~ _ _ . . _ _ _ _ _ _ _ . _ . _ _ _ _ _
- ADNINISTRATIVE CONTROLS i
j 6.6 REPORTABLE EVENT ACTION 6.6.1 The following actions shall be taken for REPORTABLE EVENTS:
- a. The Commission shall be notified and a report submitted
! pursuant to the requirements of Section 50.73 to 10 CFR Part 50, and
, b. Each REPORTABLE EVENT shall be reviewed by the PORC and the
! results of this review shall be submitted to the Chairperson of the NSAB and the Senior Vice President and CN0 - Millstone. l l 6.7 SAFETY LIMIT VIOLATION l 6.7.1 The following actions shall be taken in the event a Safety Limit is
! violated:
i a. The unit shall be placed in at least HOT STANDBY within one
- hour.
- 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 Senior Vice President and CNO - Millstone and the Chairperson of the i NSA8 shall be notified within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />; i c. A Safety Limit Violation Report shall be prepared. The report shall be reviewed by the PORC. This report shall describe:
(1) applicable circumstances preceding the violation, j (2) effects of the violation upon facility components, systems, )
- or structures, and (3) corrective action taken to prevent recurrence;
- d. The Safety Limit Violation Report shall be submitted to the j Commission, the Chairperson of the NSAB, and the Senior Vice '
President'and CN0 - Millstone within 14 days of the violations. ;
a i e. Operation shall not be resumed until authorized by the
- Commission.
6.8 PROCEDURES i
6.8.1 Written procedures shall be established, implemented and maintained
,' covering the activities referenced below:
- a. The applicable procedures recommended in Appendix "A" of q Regulatory Guide 1.33, February,1978.
- b. Refueling operations.
j
- c. Surveillance activities of safety related equipment.
j d. Not used.
- e. Not used.
Millstone Unit 2 6-14 Amendment Nos. 7), JJ, 77, 111,
- ones 1f1, 191* 19fe 191s 19fe
i
! ADMINISTRATIVE CONTROLS i
i f. Fire Protection Program implementation.
i i g. Quality Control for effluent monitoring using the guidance in
! Regulatory Guide 1.21 Rev. 1, June 1974.
l h. Radiological Effluent Monitoring and Offsite Dose Calculation
! Manual (REM 00CM) implementation, except for Section I.E.,
j Radiological Environmental Monitoring.
t 6.8.2 a. The Unit 2 Unit Director or Millstone Unit 2 Recovery Officer or
- Senior Vice President and CN0 - Millstone may designate specific j procedures and programs, or classes of procedures and programs to be reviewed in accordance with the Station Qualified Reviewer i
Program in lieu of review by the PORC or SORC. Thereviewperthel j Qualified Reviewer Program shall be in accordance with j Specification 6.5.4.
i
, b. Procedures and programs listed in Specification 6.8.1, and changes i thereto, shall be approved by the Unit 2 Unit Director or Senior l' Vice President and CN0 - Millstone or by cognizant Manager or Directors who are designated as the Approval Authority by the Unit
- 2 Unit Director or Senior Vice President and CN0 - Millstone, as i
specified in administrative procedures. The Approval Authority
- for each procedure and program or class of procedure and program j shall be specified in administrative procedures.
1 c. Each procedure of Specification 6.8.1, and changes thereto, shall
! be reviewed by the PORC or SORC and shall be approved by the j Unit 2 Unit Director or Senior Vice President and CNO - Millstone,
{ or be reviewed and approved in accordance with the Station
- Qualified Reviewer Program, prior to implementation. Each
! procedure of Specification 6.8.1 shall be reviewed periodically as i set forth in administrative procedures.
I 4
6.8.3 Temporary changes to procedures of 6.8.1 above may be made provided:
- a. The intent of original procedure is not altered.
I b. The change is approved by two members of the plant management j staff, at least one of whom holds a Senior Reactor Operator's j License on the unit affected.
) c. The change is documented, reviewed by the PORC or SORC, or the t
Station Qualified Reviewer Program as applicable, and approved by the Unit 2 Unit Director or Senior Vice President and CNO -
- Millstone or Station Qualified Reviewer Program Department Manager j within 14 days of implementation.
6.8.4 Written procedures shall be established, implemented and maintained
- - covering Section I.E, Radiological Environmental Monitoring, of the REM 00CM.
t i
Millstone Unit 2 6-15 Amendment Nos. J7, Jp, 77, JJJ, j 171,17),193
ADMINISTRATIVE CONTROLS 6.15 RADIOLOGICAL EFFLUENT MONITORING AND OFFSITE DOSE CALCULATION MANUAL (REMODCM)
Section I, Radiological Effluents Monitoring Manual (REM), shall outline the sampling and analysis programs to determine the concentration of radioactive materials released offsite as well as dose commitments to individuals in those exposure pathways and for those radionuclides released as a result of station operation. It shall also specify operating guidelines for radioactive waste treatment systems and report content.
Section II, the Offsite Dose Calculation Manual (ODCM), shall describe the methodology and parameters to be used in the calculation of offsite doses due to radioactive gaseous and liquid effluents and in the calculations of gaseous and liquid effluent monitoring instrumentation Alare/ Trip Setpoints consistent with the applicable LCO's contained in these Technical Specifications.
Changes to the REM 00CM:
- a. Shall be documented and records of reviews performed shall be retained as required by Specification 6.10.2m. This documentation shall contain:
- 1) Sufficient information to support the change together with the appropriate analyses or evaluations justifying the change (s),
and
- 2) A determination that the change will maintain the level of radioactive effluent control required by 10 CFR 20.106, 40 CFR Part 190,10 CFR 50.36a, and Appendix I to 10 CFR Part 50 and not adversely impact the accuracy or reliability of effluent, dose, or setpoint calculations.
- b. Shall become effective after review and acceptance by SORC and the approval of the Senior Vice President and CN0 - Millstone. l
- c. Shall be submitted to the Commission in the form of a complete, legible copy of the entire REM or ODCM, as appropriate, as a part of or concurrent with the Annual Radioactive Effluent Report for the period of the report in which any change was made. Each change shall be identified by markings in the margin of the affected pages, clearly indicating the area of the page that was changed, and shall indicate the date (e.g., month / year) the change was implemented.
Millstone Unit 2 6-24 Amendment No. JJJ, JJJ, JJJ, J7J.
0286
! ~
l 4
j ADMINISTRATIVE CONTROLS 6.1 RESPONSIBILITY
- 6.1.1 The Senior Vice President and Chief Nuclear Officer (CNO) - Millstone
{ shall be responsible for overall operation of the Millstone Station site while
! the.Vice President - Millstone Unit 3 shall be res>onsible for overall unit i safe operation and the Unit 3 Unit Director shall >e responsible for operation i of the unit. The Senior Vice President and CN0 - Millstone, Vice President -
l Millstone Unit 3 and Unit 3 Unit Director shall each delegate in writing the
- succession to these responsibilities during their absence.
! 6.2 ORGANIZATION 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 i shall include the positions for activities affecting the safety of the nuclear power plant.
. a. Lines of authority, responsibility, and communication shall be established and defined for the highest management levels through i intermediate levels to and including all operating organization j positions. These relationships shall be documented and updated, as appropriate, in the form of organization charts, functional descrip-j tions of departmental responsibilities and relationships, and job descriptions for key personnel positions, or in equivalent forms of
- documentation. These requirements shall be documented in the !
Quality Assurance Topical Report.
- b. The Vice President - Millstone Unit 3 shall be responsible for l overall unit safe operation and shall have control over those onsite j activities necessary for safe operation and maintenance of the
- plant.
. c. The Senior Vice President and CNO - Millstone shall have corporate l l 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.
i d. The individuals who train the operating staff and those who carry out health physics and quality assurance functions may report to the j- appropriate onsite manager; however, they shall have sufficient
! organizational freedom to ensure their independence from operating
- pressures.
6.2.2 FACILITY STAFF
{ a. Each on-duty shift shall be composed of at least the minimum shift 4
crew composition shown in Table 6.2-1; MILLSTONE - UNIT 3 6-1 Amendment No. # , 77, 77, 0471
~
- l i !
1 anastaltRTaAYtvr enarrant t 1
l 6.2.3 INDEPENDENT SAFETY ENGINEERING GROUP fISEG)
FUNCTION i 6.2.3.1 The ISEG shall include, as part of its function, examination of unit l operating characteristics, NRC issuances, industry advisories, Licensee Event Repotts, and other sources of unit design and operating experience information, including units of similar design, which may indicate areas for improving unit safety. The ISEG shall make detailed recommendations for ,
revised procedures, equipment modifications, maintenance activities, operations I activities, or other means of improving unit safety to appropriate station / corporation management.
COMPOSITION 6.2.3.2 The ISEG shall be composed of at least four full-time personnel located on site to perform the functions described in 6.2.3.1 for Millstone Unit 3. Each person shall have either:
(1) A bachelor's degree in engineering or related science and at least 2 years of professional level experience in his field, at least 1 year of which experience shall be in the nuclear field, or, (2) At least 10 years of professional level experience in his field, at least 5 years of which experience shall be in the nuclear field.
A minimum of 50% of these personnel shall have the qualifications specified in (1) above.
RESPONSIBILITIES 6.2.3.3 The ISEG shall be responsible for maintaining surveillance of unit activities to provide independent verification
- that these activities are 4 performed correctly and that human errors are reduced as much as practical.
RECORDS I
6.2.3.4 Records of activities performed by the ISEG shall be prepared and maintained, and quarterly reports of completed safety evaluations will be made to the Vice President-Nuclear Oversight. l 6.2.4 SHIFT TECHNICAL ADVISOR 6.2.4.1 The Shift Technical Advisor shall provide advisory technical support to the Shift Supervisor in the areas of thermal hydraulics, reactor engineering, and plant analysis with regard to the safe operation of the unit. The Shift Technical Advisor shall have a bachelor's degree or equivalent in a scientific or engineering discipline and shall have received specific training in the response and analysis of the unit for transients and accidents, and in unit design and layout, including the capabilities of instrumentation and controls in the control room.
- Not responsible for sign-off function.
NILLSTONE - UNIT 3 6-4 Amendment No. JJ 77, 0472
< ADNINISTRATIVE CONTROLS i
gj FACILITY STAFF QUALIFICATIONS i
6.3.1 Each member of the facility staff shall meet or exceed the minimum
, qualifications of ANSI N18.1-1971 for comparable positions, except for:
?
- a. If the Operations Manager does not hold a senior reactor operator
, license for Millstone Unit No. 3, then the Operations Manager shall have
- held a senior reactor operator license at a pressurized water reactor,
- . and the Assistant Operations Manager shall hold a senior reactor
- operator license for Millstone Unit No. 3.
- b. The Health Physics Manager shall meet or exceed the qualifications of
! Regulatory Guide 1.8, Revision 1, May 1977.
6.4 TRAINING
! 6.4.1 A retraining and replacement training program for the facility staff i shall be maintained under the direction of the Senior Vice President and CNO -
l Millstone and shall meet or exceed the requirements and recommendations of l Section 5.5 of ANSI N18.1-1971 and 10 CFR Part 55.59. The Director-Nuclear
- Training has the overall responsibility for the implementation of the Training Program.
l 6.4.2 Deleted.
! 6.5 REVIEW AND AUDIT I
l 6.5.1 PLANT OPERATIONS REVIEW COMITTEE (PORC)
FUNCTION 6.5.1.1 The P0RC shall function to advise the Unit 3 Unit Director on all l l matters related to nuclear safety.
i i' q COMPOSITION i
j 6.5.1.2 The PORC shall be composed of nine to eleven members. Members j shall collectively have experience and expertise in the following areas:
! Plant Operations ;
i Engineering '
4 Reactor Engineering i Maintenance i
Instrumentation and Controls Health Physics i Chemistry '
j Work Planning
! Quality Assurance t
l The minimum qualifications of PORC members shall be that all members have an
, academic degree in an engineering or physical science field, or hold a j management position, and have a minimum of five years technical experience in 4 their respective field of expertise. The members of PORC shall be appointed in writing by the Unit 3 Unit Director. The Chairperson and alternate l
, Chairperson of- the PORC shall be drawn from the PORC members and be appointed in writing by the Unit 3 Unit Director. l I
NILLSTONE - UNIT 3 6-5 Amendment No. 77, pp, pf, 77. PJ, em 119s ill i
1
_ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ - _ _ _ _ _ _ ._ _ _ _ _ . _ _ m . _ -
~
ADMINISTRATIVE CONTROLS ALTERNATES l
i 6.5.1.3 All alternate members shall be a
! Chairperson to serve on a temporary basis;ppointed howeverin nowriting by the more than PORC two i alternates shall participate as voting members in kRC activities at any one
! time.
l MEETING FREQUENCY l
- 6.5.1.4 The PORC shall meet at least once per calendar month and as convened
] by the PORC Chairperson.
. 6.5.1.5 The quorum of the PORC shall consist of the Chairperson or Vice
! Chairperson and four members including alternates. l
! RESPONSIBILITIES l 6.5.1.6 The PORC shall be responsible for:
i a. Review of: 1 all procedures, except common sita procedures, f required by(Sp)ecification 6.8 and changes thereto2 l exceptcommonsiteprgramsrequiredbySpecificafion)6.8andall programs, i changes thereto, and 3 any other proposed procedures, programs or 1 changes thereto as de er) mined by the Unit 3 Unit Director to affect l
! nuclear safety. Procedures and programs required by Specification 4 6.8 that are designated for review and approval by the Station Qualified Reviewer Program do not require PORC review.
- b. Review of all proposed tests and experiments that affect nuclear safety;
- c. Review of all proposed changes to Sections 1.0-5.0 of these Technical Specifications;
- d. Review of all proposed changes or modifications to plant systems or equipment that affect nuclear safety; e.
Investigation including the preparationof all violations of the Technical and forwarding Specifications,lua-of reports covering eva tion and recommendations to prevent recurrence, to the Senior Vice President and CN0 - Millstone Vice President - Millstone Unit 3 and totheChairpersonoftheNuclearSafetyAssessmentBoard;
- f. Review of all REPORTABLE EVENTS;
- g. Review of facility operations to detect potential safety hazards;
- h. Performance of special reviews, investigations, or analyses and reports thereon as requested by the Chairperson of the Nuclear Safety Assessment Board or the Senior Vice President and CN0 -
Millstone or Vice President - Millstone Unit 3; and
- i. Render determinations in writing if any item considered under ^
Specification 6.5.1.6a. through d. above, as appropriate and as provided by 10CFR50.59 or 10CFR50.92 constitutes an unreviewed safetyquestion,orrequiresasignificanthazardsconsideration determination.
MILLSTONE - UNIT 3 6-6 Amendment No. 7J. pp, pf, PP, 177, un fil
ADMINISTRATIVE CONTROLS
! j. Review of Unit Turbine overspeed Protection Maintenance and
] Testing Program and revision thereto.
- k. Review of the Fire Protection Program and implementing procedures.
AUTHORITY j 6.5.1.7 The PORC shall:
(
l a. Recommend to the Unit 3 Unit Director written approval or l
- disapproval of items considered under Specification 6.5.1.6a.
8 through d. above; and ,
j b. Provide written notification to the Senior Vice President and I
- CNO - Millstone Vice President - Millstone Unit 3 and the !
- ChairpersonoffheNuclearSafetyAssessmentBoardofdisagreement 3
between the PORC and the Unit 3 Unit Director; however, the Unit 3 i Unit Director shall have responsibility for resolution of such
,! disagreements pursuant to Specification 6.1.1.
l RECORDS 6.5.1.8 The PORC shall maintain written minutes of each meeting and copies i shall be provided to the Senior Vice President and CN0 - Millstone and the l Chairperson of the Nuclear Safety Assessment Board.
1 j 6.5.2 SITE OPERATIONS REVIEW COMMITTEE (SORC) ]
l FUNCTION j 6.5.2.1 'The SORC shall function to advise the Senior Vice President and
- CN0 - Millstone on all matters related to nuclear safety of the entire
- Millstone Station Site.
COMPOSITION
{
i 6.5.2.2 The SORC shall be composed of the:
! Chairperson: Senior Vice President and CN0 - Millstone Member: Director, Unit Operations Member: Unit 2 Unit Director Member: Unit 3 Unit Director Member: Director, Nuclear Services Member: Mana er, General Services Member: Desi nated Member of Unit 1 PORC Member: Desi nated Member of Unit 2 PORC Member: Desi nated Member of Unit 3 PORC Desi nated Member of Nuclear Oversight l Member: l The Senior Unit Director / Director, Unit Operations in attendance shall l be the Vice Chairperson.
MILLSTONE - UNIT 3 6-7 Amendment No. 77, PP, JPJ, # 7, un Up,
)
i- ADNINISTRATIVE CONTROLS
. w ALTERNATES i 6.5.2.3 Alternate members shall be appointed in writing by the SORC l Chairperson to serve on a temporary basis; however, no more than two i alternates shall participate in SORC activities at one time.
4 MEETING FREQUENCY 4
i 6.5.2.4 The SORC shall meet at least once per 6 months and as convened by
- the SORC Chairperson.
000 RUM .
6.5.2.5 A quorum of the SORC shall consist of the Chairperson or Vice Chairperson and five members including alternates.
3 RESPONSIBILITIES 6.5.2.6 The SORC shall be responsible for: i
! a. 1 all common site
, Reviewof(d)changesthereto,kroceduresrequiredbySpecifica-all tion 6.8 an 2 common site prI
. by Specification 6.8 and changes)thereto, (3) any other proposed '
! procedures, programs, or changes thereto as determined by the Senior
- Vice President and CN0 - Millstone to affect site nuclear safety. l Common site programs and procedures required by Specification 6.8
) that are designated for review and approval by the Station Qualified j Reviewer Program do not require SORC review.
- b. Review of all roposed chan
- Controls" of t$ese Technica$es Specifications; to Section 6.0 " Administrative
! c. Performance of special reviews and iavestigations and reports as j requested by the Chairperson of the Nuclear Safety Assessment Board;
- d. Not used.
l l
! e. Not used.
! I
- f. Review of all common site proposed tests and experiments that affect '
l nuclear safety; 1
- g. Review of all common site proposed changes or modifications to I systems or equipment that affect nuclear safety; and 1
- h. Render determinations in writing or meeting minutes if any item above, as considered under Specification 6.5.2.6(a)orthrough (g)92 constitutes I appropriate and as provided by 10CFR50.59 10CFR50.
- an unreviewed safety question or requires a significant hazards
! consideration determination.
! 1. Review of the common site Fire Protection Program and implementing procedures, i
i T
i
.i i
NILLSTONE - UNIT 3 6-8 Amendment No. 77, pf, pp, Jpp, 11) osn J$9,
2 ADMINISTRATIVE CONTROLS i
i AUTHORITY l 6.5.2.7 The SORC shall:
4 l a. Recommend to the Senior Vice President and CNO - Millstone written l l ,. approval or disapproval in meeting minutes of items considered i under Specification 6.5.2.6(a) through (g) above, a'ad
- b. Provide immediate written notification or meeting minutes to the President and Chief Executive Officer (CEO) and the Chairperson of the Nuclear Safety Assessment Board of disagreement between the SORC j and the Senior Vice President and CN0 - Millstone; however, the
- Senior Vice President and CN0 - Millstone shall have responsibility for resolution of such disagreements pursuant to 6.1.1 above.
l
- RECORDS i
6.5.2.8 The 50RC shall maintain written minutes of each meeting and copies shall be provided to the Senior Vice President and CN0 - Millstone and l Chairperson of the Nuclear Safety Assessment Board.
6.5.3 NUCLEAR SAFETY ASSESSMENT BOARD (NSAB)
FUNCTION 6.5.3.1 The minimum qualifications of NSAB members are as follows:
- a. The Chairperson and NSAB members shall have:
- 1) An academic degree in an engineering or physical science field, or hold a senior management position, and
- 2) A minimum of five years technical experience in their respective field of expertise.
- b. The NSAB shall have experience in and shall function to provide independent oversight review and audit of designated activities in the areas of:
- 1) Nuclear power plant operations;
- 2) Nuclear engineering;
- 3) Chemistry and radiochemistry;
- 4) Metallurgy;
- 5) Instrumentation and control;
- 6) Radiological safety; NILLSTONE - UNIT 3 6-9 Amendment No. JJ, JJ, JJ, JJJ, 177, 0472
ADMINISTRATIVE CONTROLS
- 7) Mechanical and electrical engineering; and
- 8) Quality assurance practices.
The NSAB serves to advise the President and CEO on matters related to nuclear safety and notify the President and CEO within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> of a safety significant l disagreement between the NSAB and the organization or function being reviewed.
COMPOSITION 6.5.3.2 The President and CEO shall appoint, in writing, a minimum of seven l me.mbers to the NSAB and shall designate from this membership, in writing, a
- Chairperson and a Vice Chairperson. The membership shall function to provide independent review and audit in the areas listed in Specification 6.5.3.1.
ALTERNATES
- 6.5.3.3 All alternate members shall be appointed, in writing, by the President and CE0; however, no more than two alternates shall participate as l members in NSAB activities at any one time.
MEETING FRE0VENCY 6.5.3.4 The NSAB shall meet at least once per calendar quarter.
000 RUM 6.5.3.5 The quorum of the NSAB shall consist of a majority of NSAB members
, including the Chairperson or Vice Chairperson. No more than a minority of the
! quorum shall have line responsibility for operation of the same Northeast
, Utilities' nuclear unit. No more than two alternates shall be appointed as members at any meeting in fulfillment of the quorum requirements.
REVIEW RESPONSIBILITIES 6.5.3.6 The NSAB shall be responsible for the review of:
- a. The safety evaluations for changes to procedures, equipment, or systems, and tests or experiments completed under the provisions of 10 CFR 50.59, to verify that such actions did not constitute an unreviewed safety question as defined in 10 CFR 50.59;
- b. Proposed changes to procedures, equipment, or systems that involve an unreviewed safety question as defined in 10 CFR 50.59;
]
- c. Proposed tests or experiments that involve an unreviewed safety question as defined in H CFR 50.59; j
i MILLSTONE - UNIT 3 6-10 Amendment No. 77, 77 Jpf, J7),
0472 Corr. Ltr. 4/6/94
ADMINISTRATIVE CONTROLS q l
- d. Proposed changes to Technical Specifications and the Operating l License; l
l e. Violations of applicable codes, regulations, orders, license requirements, or internal procedures having nuclear safety significance; l - f. All Licensee Event Reports required by 10 CFR 50.73; l ;
! g. Indications of significant unanticipated deficiencies in any aspect I
of design or operation of structures, systems, or components that )
could affect nuclear safety,
- h. Significant accidental, u1 planned, or uncontrolled radioactive l releases, including corrective actions to prevent recurrence; 4
- 1. Significant operating abnormalities or deviations from normal and !
expected performance of equipment that could affect nuclear safety; ;
- j. The performance of the corrective action program; and
- k. Audits and audit plans.
Reports or records of these reviews shall be forwarded to the President and CEO l within 30 days following completion of the review. l AUDIT PROGRAM RESPONSIBILITIES 6.5.3.7 The NSAB audit program shall be the responsibility of the Audits and Evaluation Department. NSAB audits shall be performed at least once per 24 months in accordance with Nuclear Group Procedures and shall encompass:
- a. The conformance of unit operation to provisions contained within the Technical Specifications and applicable license conditions;
- b. The training and qualifications of the unit staff;
- c. The implementation of all programs required by Specification 6.8;
- d. The Fire Protection Program and implementing procedures.
- e. The fire protection equipment and program implementation utilizing either a qualified offsite license fire protection engineer or an outside independent fire protection consultant.
- f. Actions taken to correct deficiencies occurring in equipment, structures, systems, components, or method of operation that affect nuclear safety; and
- g. Other activities and documents as requested by the President and CEO. l l
l l
NILLSTONE - UNIT 3 6-11 Amendment No. [J, [J 77, pp, 0472 [ff,((f, 1
-- -~ .- --__- - - _ - . - - . - - - - - - _ _ _ - . . -
ADMINISTRATIVE CONTROLS RECORDS 6.5.3.8 Written records of reviews and audits shall be maintained. As a minimum these records shall include:
- a. Results of the activities conducted under the provisions of Section 6.5.3;
' b. Recommended approval or disapproval of items considered under f l Specifications 6.5.1.6.a through 6.5.1.6.d, and 6.8; and :
- c. Determination as to whether each item considered under Specification 6.5.1.6.a, 6.5.1.6.b, 6.5.1.6.d, and 6.8 constitute an unreviewed safety question as defined in 10 CFR 50.59.
6.5.4 Station Qualified Reviewer Proaram l
l Function I 6.5.4.1 The Unit 3 Unit Director or Vice President - Millstone Unit 3 or
! Senior Vice President and CN0 - Millstone may establish a Station Qualified Reviewer Program whereby required reviews of designated procedures or classes of procedures required by Specifications 6.5.1.6.a and 6.5.2.6.a are performed by Station Qualified Reviewers and approved by designated managers. These reviews i are in lieu of reviews by the PORC or SORC. However, procedures which require a 10 CFR 50.59 evaluation must be reviewed by the PORC or SORC.
Responsibilities l
6.5.4.2 The Station Qualified Reviewer Program shall: !
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.
- c. Ensure cross-disciplinary reviews are performed by a Qualified Reviewer (s) in affected disciplines, or by other persons designated ,
by cognizant Managers or Directors as having specific expertise required to assess a particular procedure, program, or change. ;
Cross-disciplinary reviewers may function as a committee.
- 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 l performed by personnel trained and qualified in performing 10 CFR 50.59 evaluations.
l NILLSTONE - UNIT 3 6-12 Amendment No. JP, 77,77,77.J7J ens J77,
l ADMINISTRATIVE CONTROLS !
- e. Provide for written recommendation by the Qualified Reviewer (s) to the responsible Manager for approval or disapproval of procedures and programs considered under Specification 6.5.1.6.a and 6.5.2.6.a and that the procedure or program was screened by a qualified
, individual and found not to require a 10 CFR 50.59 evaluation.
i 6.5.4.3 If the responsible manager determines that a new program, procedure,
, or change thereto requires a 10 CFR 50.59 evaluation, that Manager will ensure r the required evaluation is performed to determine if the new procedure, program, or change involves an unreviewed safety questic.1. The new procedure, program,
, or change will then be forwarded with the 10 CFR 50.59 evaluation to PORC or SORC for review. l 6.5.4.4 Personnel recommended to the Station Qualified Reviewers shall be designated in writing by the Unit 3 Unit Director or Vice President - Millstone Unit 3 or Senior Vice President and CN0 - Millstone for each procedure, program, or class of procedure or program within the scope of the Station Qualified Reviewer Program.
6.5.4.5 Temporary procedure changes shall be made in accordance with Specification 6.8.3 with the exception that changes to procedures for which
- reviews are assigned to Qualified Reviewers will be reviewed and approved as q described in Specification 6.5.4.2.
, Records 6.5.4.6 The review of procedures and programs performed under the Station
- Qualified Reviewer Program shall be documented in accordance with administrative procedures.
l Trainina and Oualification 6.5.4.7 The training and qualification requirements of personnel designated j as a Qualified Reviewer in accordance with the Station Qualified Reviewer
- Program shall be in accordance with administrative procedures. Qualified
- reviewers shall have:
l 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 equivalent combination of education and experience as approved by a Department Manager.
MILLSTONE - UNIT 3 6-13 Amendment No. JU.
0472
I ADMINISTRATIVE CONTROLS i
6.6 REPORTABLE EVENT ACTION ,
1 6.6.1 The following actions shall be taken for REPORTABLE EVENTS:
1
- a. The Comission shall be notified and a report submitted pursuant to the requirements of Section 50.73 to 10 CFR Part 50, and
- b. Each REPORTABLE EVENT shall be reviewed by the PORC and the i results of this review shall be submitted to the Chairperson of 1 I
the NSAB and the Senior Vice President and CN0 - Millstone. l 6.7 SAFETY LIMIT VIOLATION I
6.7.1 The following actions shall be taken in the event a Safety Limit is violated:
- a. The Unit shall be placed in at least HOT STANDBY within one hour. !
- 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 Senior Vice President and CN0 - Millstone and the Chairperson of the NSAB shall be notified within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />;
- c. A Safety Limit Violation Report shall be prepared. The report shall be reviewed by the PORC. This report shall describe: l
(!) applicable circumstances preceding the violation, (2) effects of th? violation upon facility components, systems, or structures, '
and (3) corrective action taken to prevent recurrence; ;
- d. The Safety Limit Violation Report shall be submitted to the Comission, the Chairperson of the NSAB, and the Senior Vice l President and CNO - Millstone within 14 days of the violation; and
- e. Operation shall not be resumed until authorized by the Comission.
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 recomended in Appendix A of Regulatory I Guide 1.33, Revision 2, February 1978;
- b. The applicable procedures required to implement the requirements of NUREG-0737 and supplements thereto;
- c. Refueling operations;
- d. Surveillance activities of safety related equipment;
- e. Not used.
MILLSTONE - UNIT 3 6-14 Amendment No. 77, 77. JPF, J77, 0472 (($
ADMINISTRATIVE CONTROLS
- f. Not used.
- g. Fire Protection Program implementation;
- h. Quality controls for effluent monitoring, using the guidsnce in
-' Regulatory Guide 1.21, Rev.1, June 1974; and
- 1. Radiological Effluent Monitoring and Offsite Dose Calculation Manual (REM 0DCM) implementation except for Section I.E, Radiological Environmental Monitoring.
i 6.8.2 a. The Unit 3 Unit Director or Vice President - Millstone Unit 3 or Senior Vice President and CN0 - Millstone may designate specific proc 6dures and programs, or classes of procedures and programs to be reviewed in accordance with the Station Qualified Reviewer Program in lieu of review by the PORC or SORC. Thereviewperthel Qualified Reviewer Program shall be in accordance with Specification 6.5.4.
- b. Procedures and programs listed in Specification 6.8.1, and changes thereto, shall be approved by the Unit 3 Unit Director or Senior Vice President and CN0 - Millstone or by cognizant Manager or Directors who are designated as the Approval Authority by the Unit 3 Unit Director or Senior Vice President and CN0 - Millstone, as specified in administrative procedures. The Approtal Authority for each procedure and program or class of procedure and program shall be specified in administrative procedures.
- c. Each procedure of Spe:ification 6.8.1, and changes thereto, shall ,
be reviewed by the PORC or SORC and shall be approved by the l Unit 3 Unit Director or Senior Vice President and CN0 - Millstone, '
or be reviewed and approved in accordance with the Station Qualified Reviewer Program, prior to implementation. Each procedure of Specification 6.8.1 shall be reviewed periodically as set forth in administrative procedures.
6.8.3 Temporary changes to procedures of Specification 6.8.1 may be made provided:
- a. The intent of the original procedure is not altered;
- b. The change is approved by two members of the plant management staff, at least one of whom holds a Senior Operator license on the unit affected; and
- c. The change is documented, reviewed by the PORC or SORC or Station l Qualified Reviewer Program, as appropriate, and approved by the Station Qualified Reviewer Program Department Manager or Unit 3 Unit Director or Senior Vice President and CN0 - Millstone within 14 days of implementation.
MILLSTONE - UNIT 3 6-15 Amendment No. 77, 77 J77, 177, 0472
_ _ _ _ . _ _ _ _ _ _ _ . _ _ _ _ _ _ _ . = _ . _ _ _ _ _ _ _ . _ . _ _ .
1 .
i .
ADNINISTRATIVE C6iiiaeLS l a
6.13 RADIOLOGICAL EFFLUENT MONITORING AND OFFSITE DOSE CALCULATION MANUAL i (REMODCM)
I i Section I, Radiological Effluent Monitoring Manual (REM), shall outline the i sampling and stalysis programs to determine the concentration of radioactive materials released offsite as well as dose commitments to individuals in those
- exposure pathways and for those radionuclides released as a result of station j operation. It shall also specify operating guidelines for radioactive waste treatment systems and report content.
! Section II, the Offsite Dose Calculation Manual (ODCH), shaii describe the
- methodology and parameters to be used in the calculation of offsite doses due
! to radioactive gaseous and liquid effluents and in the calculations of gaseous j and liquid effluent monitoring instrumentation alarsVtrip setpoints consistent l with the applicable LCOs contained in these technical specifications.
- Changes to the REMODCM:
i j a. Shall be documented and records of reviews performed shall be retained as l required by Specification 6.10.30. This documentation shall contain:
i
! 1) Sufficient information to support the change together with the j appropriate analyses or evaluations justifying the change (s), and i
4
- 2) A determination that the change will maintain the level of radioactive j effluent control required by 10 CFR 20.106, 40 CFR Part 190,
- 10 CFR 50.36a, and Appendix I to 10 CFR Part 50 and not adversely j impact the accuracy or reliability of effluent, dose, or setpoint
- calculations.
- b. Shall become effective after review and acceptance by SORC and the j approval of the Senior Vice President and CN0 - Millstone. l 4
- c. Shall be submitted to the Commission in the form of a complete, legible copy of i the entire REM or ODCM, as appropriate, as a part of or concurrent with the Annual Radioactive Effluent Report for the period of the report in'which any
- change was made. Each change shall be identified by markings in the margin of i
the affected pages, clearly indicating the area of the page that was changed, and i
shall indicate the date (e.g., month / year) the change was implemented.
6.14 RADIOACTIVE WASTE TREATMENT Procedures for liquid and gaseous radioactive effluent discharges from the Unit shdl be prepared, approved, maintained and adhered to for all operations involving offsite releases of radioactive effluents. These procedures shall specify the use of appropriate waste treatment systems utilizing the guidance provided in the REM 0DCM.
2 The Solid Radioactive Waste Treatment System shall be operated in accordance with the Process Control Program to process wet radioactive wastes to meet shipping and burial a ground requirements.
E 1
J MILLSTONE - UNIT 3 6-24 Amendment No. pp, 77, 77, pp, 0473