ML20138G687
| ML20138G687 | |
| Person / Time | |
|---|---|
| Site: | Millstone, Haddam Neck File:Connecticut Yankee Atomic Power Co icon.png |
| Issue date: | 12/24/1996 |
| From: | CONNECTICUT YANKEE ATOMIC POWER CO. |
| To: | |
| Shared Package | |
| ML20138G685 | List: |
| References | |
| NUDOCS 9701020213 | |
| Download: ML20138G687 (102) | |
Text
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Docket Nos. 50-213 50-245 50-336 i 50-423 B16046 i i
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Attachment 1 i i
Haddam Neck Plant i I
Millstone Nuclear Power Station, Unit Nos.1,2, and 3 Proposed Revision to Technical Specifications Administrative Controls Marked Up Pages December 1936 9701020213 961224 PDR ADOCK 05000213 P PDR
6.0 ADMINISTRATIVE CONTROLS
{ 6.1 RESPONSIBILITY wded e C d WCO"r l f
6.1.1 TheWA-MWMddamMshall be responsible for overall ;
facility operation and shall delegate, in writing, the succession to this responsibility during his absence. l f
f 6.2 ORGANIZATION 6.2.1 ONSITE AND OFFSITE ORGANIZATIONS l 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.
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- a. Lines of authority, responsibility, and communication shall be 3 established and defined for the highest management levels through intermediate levels to and including all operating organization positions. These relationships shall be documented and updated, as appropriate, in the form of organization charts, functional ;
descriptions 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.
D vec k
- b. The *:: h:Vf: :._ :t iff= %d shall be responsible for overall unit safe operation and shall have control over those onsite activities necessary for safe operation and maintenance of the !
plant.
The Executive Vice President
- q a Nx ..)..f.nr,Lew shall haveoMau corporate c.
responsibility for overall plant nuclear safety and shall take any measures needed to ensure acceptable performance of the staff in operating, maintaining, and providing technical support to the plant to ensure nuclear safety. .
- d. The individuals who train the operating staff and those who carry out health physics and quality assurance functions may report to the appropriate onsite manager; however, they shall have sufficient organizational 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. In addition, while the facility is in MODE 1, 2, 3 or 4, at least one licensed Senior Operator shall be in the control room; i
HADDAM NECK 6-1 Amendment No. JJJ JJJ 1
)
1 0139
j JUL 161996 l
ADMINISTRATIVE CONTROLS o !
- f. Successful completion of the Thames Valley State Technical
'. College associate's degree in Nuclear Engineering Technology !
program, provided that the individual was enrolled in the '
program by October 1,1987. 4 I
l 2. Dedicated STA: Must meet the STA training criteria of NUREG-0737, l Item I.A.I.1, and have received specific training in plant design, ;
l and response and analysis of the plant for transients and l accidents. !
6.4 TRAINING l A retraining and replacement training program for the facility staff shall be maintained under the direction of the Nuclear Unit Director and shall meet or :
exceed the requirements and recommendations of Section 5.5 of ANSI N18.1-1971 and 10CFR55.59. The Director-Nuclear Training has the overall responsibility for the implementation of the Training Program.
6.5 REVIEW AND AUDIT 6.5.1 PLANT OPERATIONS REVIEW COMMITTEE (p0RC)
FUNCTION 6.5.1.1 The PORC shall function to advise the Vice 7.diJ..a-iiedd.. . Lek on all matters related to nuclear safety. vid Dick COMPOSITION 6.5.1.2 The PORC.shall be composed of at least eleven members. Members shall collectively have experience and expertise in the following areas:
Plant Operations Engineering Reactor Engineering Mechanical Maintenance Electrical Maintenance Instrumentation and Controls Health Physics Work Planning and Control Quality Services !
Security i Chemistry '
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 !
l their respective field of expertise. The members of PORC shall be appointed in writing by the Vie: We-ident ' " dd:: "::k, who is the PORC Chairperson.
The alternate Chairpersons of the PORC shall be drawn from the PORC members and be appointed in writing by the Vi : Pr::fdent "rddir " :E. 041 DlruJoe
- vist 0;<<<Aor l
HADDAN NECK 6-5 Amendment No. JJJ.JJJ.JJJ.JJJ.
own 17J, 190
r
' FEBRUARY 14, 1995 I
ADMINISTRATIVE CONTROLS i (<
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1 ALTERNATES 6.5.1.3 All alternate members shall be appointed in writing by the PORC Chairperson to serve on a temporary basis; however, no more than two ,
v j
alternates shall participate as voting members in FORC activities at any one j time.
MEETING FREQUENCY j 6.5.1.4 The PORC shall meet at least once per calendar month and as '
j convened by the PORC Chairperson or his/her designated alternate. !
4
- OUORUM I
4 6.5.1.5 The quorum of the PORC shall consist of the Chairperson or his/her
.j designated alternate and four members including alternates. ,
l
] RESPONSIBILITIES i
j 6.5.1.6 The PORC shall be responsible for:
i a. Review of: (1) all procedures required by Specification 6.8 and
' changes thereto, and 2) any other proposed procedures or changes thereto as determined by the "'= ."n:' t .t " "-- "--' to j affect nuclear safety; van oirub
! b. Review of all proposed tests and experiments that affect nuclear j safety; 1
l c. Review of all proposed changes to the Technical Specifications; j 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 covering eyone ues %Ad evaluation and recommendations to prevent recurrence, to the 3 gbe'nnt'n "':: ."n:'tri .";;1eer and to the Chairperson of the
.j g,uc Nuclear Safety Assessment Board; I i f. Review of all REPORTABLE EVENTS;
- g. Review of facility operations to detect potential r,afety hazards;
- h. Performance of special reviews, investigations or analyses and reports thereon as requested by the Chairperson of the Nuclear l Safety Assessment Board or the "'- "--"-" " " - "--'
l val Dlrakr i
a .
HADOAM NECK 66 Amendment No. JJJ,177. JJJ ,181 ones l
I l
APR 241996 mnranTRATm courRou
{s t
- i. Not used. l l j . -- Not used. l l
- k. Review of the Fire Protection Program and ImpTementing Procedures.
AUTHORITY !
l 6.5.1.7 The PORC shall- !
Oni Dincler Report to and be advisory to the "' "-- t -
l
- a. ' " " -
"- ' on !
l those areas of responsibility specified in Section 6.5.1.6(a) through (k); i anik Greelee i
- b. Render deteminations in writing to the t' ice ";;;id::t u.f g=,
Neck if any item considered under Specification 6.5.1.6a. through d., above, as appropriate and as provided by 10CFR50.59 or i 10CFR50.g2 constitutes an unreviewed safety question or requires a j significant hazards consideration detemination. .
I v&c h f+e,)acA a,a cAld Nueb cG<u
- c. Provide written notification,\ meeting minutes may be used for this purpose, to the t ereti": "';; hesiint "rkr and the Chairperson of the Nuclear Safety Assessment Board of disagreement
" - "- ' however, the 4,c.4e Mie A<vAd"between the PORC ter P cifrt and the V+
Effr 2:t shall have responsibility for awa &ef NocJemoMr resolution of such disagreements pursuan to Specification 6.1.1.
On;\ DlrecAer RECORDS 6.5.1.8 The PORC shall maintain written minutes of cach meeting that,- at a minimum, document the results of all PORC activities performed under the responsibility and authority provisions of these Technical Specifications.
A Copy shall be provided to the Chairperson of the Nuclear Safety Assessment Board.
6.5.2 NUCLEAR SAFETY ASSESSMENT BOARD (NSAB)
FUNCTION 6.5.2.1 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 i field, or hold a senior management position, and l
- 2. A minimum of five years technical experience in their respective field of expertise. !
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HADDAN NECK 6-7 Amendment No. 177,'Jg 177, 177, es** 171,
FEBRUARY 14, 1995 ADNINISTRATIVE CONTROLS
- 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; l 4. Metallurgy; t ,
- 5. Instrumentation and control;
- 6. Radiological safety; ;
i
- 7. Nechanical and electrical engineering; and ;
1
- 8. Quality assurance practices. l penobed anb CEo The NSAB serves to advise the h /: Vic; Pr;;id;r.t "::h;r on matters related to nuclear safety and notify the L;;;ti;; Vi:: Pr;;id:r.t "::htr PmMa4 i
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.
COMP 0SITION MkJ<J cra 6.5.2.2 The 5:::ti:: Yt : Pr::!d: .t .";;h:r shall appoint, in writing, a minimum of seven members 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 6.5.2.1.
ALTERNATES -
Pmokod a4 00 6.5.2.3 All alternate members shall be appointed, in writing, by the Err"t%
Yi;e P.niA.J. - ";;l;;r; however, no more than two alternates shall participate as members in NSAB activities at any one time.
NEETING FREQUENCY 6.5.2.4 The NSAB shall meet at least once per calendar quarter.
OV0 RUM 6.5.2.5 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.
! HADDAN NECK 6-8 Amendment No.AA6, A45
- f 58, 181 l
1 FEBRUARY 14, 1995 ADMINISTRATIVE CONTROLS k REVIEW RESPONSIBILITIES 6.5.2.6 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; l c. Proposed tests or experiments that involve an unreviewed safety l question as defined in 10 CFR 50.59; t
l 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 l
significance; i
- 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.
%,beadau Go Reports or records of these reviews shall be forwarded to the Emeev6+ve Yi;; 7.h;i.r.t - Nuclear within 30 days following completion of the review.
AUDIT PROGRAM RESPONSIBILITIES Nodear OwsqlW1*"T" 6.5.2.7 The NSAB audit program shall be the responsibility of th: 0='ity :..d
";;;;:- rt E:rH :; 0;;;
E ' :r.t. NSAB audits shall be performed at least once per l 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; i.*
i NADDAN NECK 6-9 Amendment No. 125, 155 ones 181
FEBRUARY 14o 1995 ADMINISTRATIVE CONTROLS
){
- b. The training and qualifications of the unit staff; i c. The implementation of all programs required by Specification 6.8; i d. The Fire Protection Program and implementing procedures; j e. The fire protection equipment and program implementation utilizing either a qualified offsite license fire protection engineer or an j outside independent fire protection consultant.
j f. Actions taken to correct deficiencies occurring in equipment, i structures, systems, components, or method of operation that affect nuclear safety; and i prrAded J cro
) g. Other activities, and documents as requested by the 0;;.tive "i::
o_ , m _. m._
i l RECORDS 6.5.2.8 Written records of reviews and audits shall be maintained. As a minimum these records shall include:
I a. Results of the activities conducted under the provisions of
- Section 6.5.2;
- b. Recoimeended 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 50.5g.
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 YleUEl'0lEEhe's'l57%"8,,Xhok oNau 6.7 SAFETY LIMIT VIOLATION l 6.7.1 The following actions shall be taken in the event a Safety Limit is violated:
- a. The unit shall be pla;ed in at least HOT STANDBY within one hour.
1 HADOAM NECK 6-10 Amendment No. J7y, Jpp,181 02M
k FEBRUARY 14, 1995 '
ADMINISTRATIVE CONTROLS
- b. The NRC Operations Center shall be notified by telephone as soon as 1
! possible and in all cases within I hour. The '-~" "- "' --
. ;;;id;;t N::h;- <
within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />;(and the gChairperson l N,,94 a of the NSAB shalldide#
be notified i
ggg ck;,g gule,
- c. A Safety Limit Violation Report shall be prepared. The report shall
- be reviewed by the PORC. This report shall describe: (1) applicable i circumstances preceding the violation, (2) effects of the violation upon facility components, systems, or structures, and (3) corrective i action taken to prevent recurrence; s
- d. The Safety Limit Violation Report shall be submitted to the Commission, the Chairperson of the NSAB and the Executive Vice l Presidentmb%::1;;N within 14 days of the violation; Cdc Nwlew on. ces \
) e. Operation will not be resumed until authorized by the Commission.
! 6.8 PROCEDURES AND PROGRAMS j
6.8.1 Written procedures and/or administrative policies shall be established, !
implemented, and maintained covering the activities referenced below:
1 I
4 I !
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HADDAN NECK 6-11 Amendment No. JJJ. JJJ.181 ames
MUF 4/, .Gn ,
' l t.DMINISTRATIVE CONTROLS
- a. The applicable procedures recommended in Appendix A of Regulatory '
Guide 1.33, Revision 2, February 1978;
(_
- b. The requirements and recommendations of. Sections 5.1 and 5.3 of ANSI N 18.7-1976.
- c. Fire Protection Program implementation.
- d. Quality controls for effluent monitoring, using the guidance in Regulatory Guide 1.21 Rev.1, June 1974.
- e. RADIOLOGICAL EFFLUENT MONITORING AND OFFSITE DOSE CALC MANUAL (REMODCM) implementation except for Section I.E, Radiological Environmental Monitoring.
- f. PROCESS CONT?OL PROGRAM implementation.
6.8.2 Each procedure of Specification 6.8.1, and changes thereto, shall be$dd- Un40 reviewed by the PORC and shall be approved by the Y!ce *=:fdst
' Nech prior to implementation and reviewed periodically as set forth in each document or 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 and approved by the
[ l i';ee ,gegg 5dde "r9 within 14 days of implementation.
l 6.8.4 Written procedures shall be established, implemented and maintained l l
covering Section 1.E., Radiological Environmental Monitoring, of the REMODCM.
6.8.5 All procedures and procedure changes required for the Radiological Environmental Monitoring Program of Specification 6.8.4 above shal1 ~be reviewed by an individual (other than the author) from the Radiological Assessment Branch or the Production Operation Services Laboratory (POSL) and approved by appropriate supervision. ,
Temporary changes may be made provided the intent of the original procedure is not altered and the change is documented and reviewed by an individual (other than the author) from the Radiological Assessment Branch or the POSL, within 14 days of implementation.
(
6-12 Amendment No. JJJ, JJJ,158 HADDAM NECK esas
AININISTRATIVE CONTROLS N 2 h Icii
. , . a . : a. .. .. ._,.. .. . . , . .
..f :s .
6.13 RADIOLOGICAL EFFLUENT MONITORING AND OFFSITE DOSE !
( GALCULATION MANUAL (REMODCM) :
Section I, Radiological Effluents Monitoring Manual, shall outline the sampling and analysis programs to detemine the concentration of radioactive <
materia?s. released offsite as well as dose commitments to individuals in -
those exposure pathways and for those radionuclides released as a result of :
facil'ity operation. It shall also specify operating guidelines for RADIDACTIVE WASTE TREATMENT SYSTEMS and report content. :
Ser: tion II, the Offsite Dose Calculation Manual, 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 Alarm / Trip Setpoints '
l consistent with the applicable LCO's contained in these Technical ,
j Specifications.
l l Changes to the REMODCM:
- a. Shall be documented and records of reviews performed shall be retained l as required by Specification 6.10.3.m. This documentation shall l contain:
- 1) Sufficient infomation to support the change together with the l appropriate analyses or evaluations justifying the change (s), and i l 2) A determination that the change will maintain the level of l radioactive effluent control required by 10 CFR 20.106, 40 CFR Part 190,10 CFR 50.36a, and Appendix I to 10CFR Part 50 and not adversely impact the accuracy or reliability of effluent, dose, or i setpoint calculations.
, b. Shall become effective after review and acceptance by PORC and the ledd;;;; 51.
approval of the Vic;giggt
- c. Shall be submitted to the Commission 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.
6.14 RADIOACTIVE WASTE TREATMENT Procedures for liquid and gaseous radioactive effluent discharges from the facility shall be prepared, approved, maintained and adhered to for all operations involving offsite releases of radioactive effluents. These I
procedures shall specify the use of appropriate RADI0 ACTIVE WASTE TREATMENT SYSTEMS utilizing the guidance provided in the REMODCM.
The Solid RADI0 ACTIVE WASTE TREATMENT SYSTEM shall be operated in accordance ii '
with the PROCESS CONTROL PROGRAM to process wet radioactive wastes to meet shipping and burial ground requirements.
l HADDAM NECK 6-20 Amendmei.' No.125, JS, ##
l east 170,
. . =- -- .- _. _ , . -- _ - .
t * '
ADNINISTRAT!YE CONTROL 5 . .
- 4/26/94 -
l i
i
- j. ,
s.1 RESPONSIBILITI '
Thep,ma,a =i:'cu,Na eh 60 aa cW Nuderc,4,, ceug
! 4.1.1 ***e "rnidst
! "illstue tstin shall be responsible for i, p,"'g,wou, Meester shall be responsible for operation of the uni 1
Meid=t .
The :=i;r "in :
- in writing, the succession to these during their absence."111;tse ;;; )
responsibilities j
6.2 ORGANIZATION
-cver on+ oevas. a i
$ 3 6.2.1 0FFSITF AND DNSITE ORGANf7ATf0NS !
Onsite and offsite organizations shall be established for unit operation and corporate management respectively. The onsite and offsite organizations shall include power plant. the pos,itions for activities affecting the safety of the nuclear r
a.
{ Lines of authority, responsibility, and communication shall be established and defined for the higher management levels through l . intermediate levels to and including all operating organization positions.
! These relationships shall be docume~nted and updated as ,
i tions of departmental responsibilities and relationsh
- descriptions for key personnel positions, or in equivalent forms of documentation.
j Quality Assurance Topical Report.These requirements shall be doc
- b. The - --
i for overall unit safe operation and shall have contro
! onsite the plant.activities necessary for safe operation and maintenance of a
',,,"0, 4, em + cwo
- c. The -
sibility for overall plant nuclear safety and shall take a measures operati eeded to ensure acceptable performance of the staff in to ensure nuclear safety. maintaining, and providing technical suppor 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. -
l 6.2.2 FACILITY STAFF
- a. I Each on duty shift shall be composed of at least the minimum shift I 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.
a 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.
h Millstone Unit 1 0123 6-1 Amendment No. #, M, 74 j r_ TigEas .. Y
July 16,1996 ADMIN!$7RATIVE CONTROLS 6.4 TRAIN!HG 6.4.1 A retraining and replacement training program for theth ility staff shall be anjntained nder the direction of the(Se6tefJitV -4 freiiidefit - RMT e and shall meet cFsxceea the requirements and reecernitTions of Section 5.5 of ANSI N!8.1-19]71:
and 10 CFR Part 55.59. The Director Nuclear Training has the i overall responsibility for the implementation of the Training
.Prasram-6.5 REVIEW AND AUDIT f c u n2 % ,.3eu @
6.5.1 plant Deerations Review Cemittee (PORC)
. Function 6.5.1.1 The PORC matters shall related function to nuclear to advise safety. f the h rM att 4t h on all e r, u .c, +
Comoesition e<4. Q 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 Chemistry Work Plan n@d' Cc#tth Quality rdceb juganch 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 B ;,, dv , technical experience in their respective field of expertise. The m.,t members of PORC shall be appointed in writing by the(1[cc14aretinJ.t-W,,it; od A . . . The Chairperson and alternate Chairperson of the PORC
> sha .e drawn from t_he___RORC members and be appointed in writing by the@c1dratt yniA D)fp919)7 w,de , , ue.
Alteenates C'P~'N on b 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 em 65 Amendment No. JJ. M , 7f.
1 1
January 17,1996 i ADMINISTRATIVE CONTROLS 1
Meetina Frenuancy e' j 6.5.1.4 The PORC shall meet at least once per calendar month and as convened by j the PORC Chairperson.
! D k 6.5.1.5
! A Ch!uorum of the- PORC 1rperson Sr.ier shall triseconsist of the hwi '-d, Chairperson,
- Mill;t::: or Vice St:tir and four i
membersinclu:dingalternates.
4 j Resnonsibilities 1
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 connon site programs, required by Specification i 6.8 and changes thereto, 3) any other proposed procedures,
! rograms, or changes thereto, as determined by the NeeleeNhHt l t h e , o,J c Fe d irecter to affect nuclear safety. Procedures and programs l required by Specification 6.8 that are designated for review and
! approval by the Station Qualified Reviewer Program do not require
} PORC review.
i
) 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.
2
- 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 E =th: t't;;
i Presi Ai.i.-% cle; and Assessment Boardkn,to the Chairperson- of-theu,,4 Nuclear Safety wm .
,,a,s em ,cuo ,a suku i Ra_,
- f. Review of all REPORTABLE EVENTS.
- g. Review of facility operations to detect potential safety hazards.
j - h. Performance of special reviews and investigations and reports thereon as requested by the Chairperson of the Nuclear Safety Assessment Board.
1
, 1. Render deteminations in writing if any item considered under i 6.5.1.6(a) through (d) above, as appropriate and as provided by j 10CFR50.5g or 10CFR50.g2, constitutes an unreviewed safety question or requires a significant hazards consideration determination.
Millstone 91M unit 1 6-6 Amendment No. 1,77,77,77,91
1 ADNINISTAATIVE CONTROLS July 16,1996
)
J. Review of the unit-specific Fire Protection Program and Y
1mplementing procedures.
Aut'ority h
6.5.1.7 The PORC shall:
- a. . 0;cAu 00 q'd w Recommend to the Nuclear-Unit .ir;; tor written a disapproval of items considered under 6.5.1.6(a)p royal orhrough (d l above.
m4k umf I becay d'<."
- b. Provide immediate written notification to the 5::ict t'i;e Tre;id;;; - Mf!!:ter: Stettee. E-teettye Yice Tr;;f t:t-
' Neelear and the Chairperson of the Nuclear Safety Assessment Board of disagreement between the PORC and the %.eleer nitog'd,8[I Directer; however, the " :1;;r % t ;;i..dwr shall have responsibility for resolution of such disagreements pursuant to 6.1.1 above. '- omb va es m w '+
Records 6.5.1.8
%gt
+. &,,;x,94ph j
y ocou The PORC shall siaintain written minutes. of each meeting and copies shall be provided to the Senter Yite Pre id:r.t l
Mill:t::: St:ti:r-and Chairperson of the Nuclear Safety Assessment Board.
6.5.2 Site Doerations Review Committee (50RC)
Function hesided, ao t c No 6.5.2.1 The 50RC shall function to advise the Senter Yi:: Tr;;idei.t -
-Mill: ten St; tier.-on all matters related to nuclear safety of the entire Millstone Station Site.
6.5.2.2 The 50RC shall be composed of the:
. wow e Chairperson: 5:;ier t'4aang au Lep!!! tene Statier.r+ Raoavy o M u i.e Tree.d::t _.
" ' "' - ^
Member-Member: Unit 2 Director wheb W+ %M 3 l Member: Unit 3 Director -
Member: Wit 5:re10:: Dire:ter D 'I'd M*
Member: Site ::rvi::: SfeesterNasu onwat Sewks 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 Qe:11ty 5:rvi;ee Nodm, consfM l The Senior %.-1;-- _ it Director in attendance shall be the Vice Chairperson. ,,, M d J Alternates l 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 50RC activities at one time.
Millstone Unit 1 6-7 Amendment No. 77 77, 77, 77. 95 Diet
- % 1
_ _ _ . . _ _ _ __ ._______ _ _ _ _ ~__._._ _ _ . _ _ _ _ _ _ _ _ . __ _ _ __. _ . _ -
! l l April 24,1996 ;
ADEMSTRATIVE CONTROLS
{ Meetina Frenuancy 1
l 6.5.2.4 The 30RC shall meet at least once per six months and as convened by j the 30RC Chairperson.
i l Dunrimi i
- 6.5.2.5 A quorum of the 30RC shall consist of the Chairperson or Vice Chairperson and five members including alternates.
l ksoonsibilities J
l 6.5.2.6 The 30RC shall be responsible for:
l a.
i Review cation 6.8ofan1) d changes thereto, 2) all common site programs,all c i required by Specification 6.8 and changes thereto, 3) any other I i proposed procedures, programs, or changes thereto as determined I l by the_l::1:r Vi : 7..;t t :0 ",i!!:t::: St:t 5 to affect site Ase4 ao s oso- nuclear safety. Common site programs and procedures required l by Specification 6.8 that are designated for review and i j approval by the Station Qualified Review Program do not require l
! SORC review.
- b. Review of all proposed changes to Section 6.0, ' Administrative controls", of these Technical Specifications.
i c. perfomance of special reviews and investigations and reports as requested by the Chairperson of the Nuclear Safety Assessment Board.
- d. Not used. l i
{ e. Not used. l 4
- 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 i systems or equipment that affect nuclear safety.
I
- h. Render determinations in writi , or meeting minutes if any
! item considered under 6.5.2.6 appropriateandasprovidedby(a OCFR50.5g through (g) above, as or 10CFR50.92,
- constitutes an unreviewed safety question or requires a
]
significant hazards consideration determination.
t
- 1. Review of the common site Fire protection Program and i
i implementing procedures. g i
t
! mi11 stone unit 1 6-8 Amen ment no. p , N , N , # 94 em 3
_ _ -- - .- _ . . _ . _ .,..,rs.,, -,. p
ADMINISTRATIVE CONTROL 5 Authority 6.5.2.7 The 50RC shall:
a.
%0cs+
Recommend to the !=ir Vic.,CcomoCAD Tr.:td= t --- Mill:: = p tat % written approval or disapproval, in meeting minutes, of items considered under6.5.2.6(a)through(g)above,
- b. Provide inmediate written notification Exu m u ve L r r-:C.4_ cm n' 'h---or meeting minutes, Chairperson of the to the Nuclear Safety Assessment Board of disagreement between the 50RC 34M and theN=tr Yin P.;;ider.t - Mill:t=; t:ti:n; however, the Cg A"'cto s S=tr Yin Tce.14ent -- Mill:t=: Ot:ti= shall have responsibility for resolution of such disagreements pursuant to 6.1.1 above.
l l Records 6.5.2.8 The 50RC shall maintain written minutes of each meeting and copies l
shall be provided to the Ser.icr Vice 7,oideni. - ;;;11:t=: St: tier, and Chairperson of the Nuclear Safety Assessment Board. 7 6.5.3 NUCLEAR SAFETY ASSESSMENT BOARD (NSAB)
%d%d) CW) *C #
FUNCTION i 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 P.anageeent 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; S. Instrumentation and control; I 6. Radiological safety; gijlstoneunit1 69 AmendmentNo.gy,pp,pp,7p,7p,93 1
l ADMINISTRATIVE CONTROLS 7.
8.
Mechanical and electrical engineering; and Quality assurance practices.
h The NSAB serves to advise the '=Mak;f,un es cae>
=^ . .. "k; Tre.; Ar.' -- Mr h ;r on matters related to nuclear safety and notify the --
"-- "' e ba,4 co "^'*
PM:!frt " = h er 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.
CQliB31119ti Mije4, av -b wo i 6.5.3.2 The n-miv. 46. Tie.;4...;. - ;;.J..r shall a cint, in writing, a i
minimum of seven members to the NSAB and shall signate from this j
membershi , in writing, a Chairperson and a Vice Chairperson. The membershi shall function to provide independent review and audit in j the areas listed in Specification 6.5.3.1.
j ALTERNATES I
6.5.3.3 All alternate members shall be appointed, in writing, by the Emeev64ve-i R ,,,h ,4 m >+e ve, Vict 50:id=t Wcleir; however, no more than two alternates shall j participate as members in NSAB activities at any one time.
{ MEETING FREOUENCY i
! 6.5.3.4 The NSAB shall meet at least once per calendar quarter. 1
! ==
l 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 1
of the quorum shall have line responsibility for operation of the same l Northeast Utilities' nuclear unit. No more than two alternates shall 1 be appointed as members at any meeting in fulfillment of the quorum j requirements.
- REVIN RESPONSIBILITIES i
l 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 I of 10 CFR 50.59, to verify that such actions did not constitute an i
unreviewed safety question as defined in 10 CFR 50.59; i
i b. Proposed changes to procedures, equipment, or systems that involve j an unreviewed safety question as defined in 10 CFR 50.59; 4
- c. Proposed tests or experiments that involve an unreviewed safety l question as defined in 10 CFR 50.59; 3
9
! Millstone Unit 1 6-10
- me Amendment No. JJ, JJ. 7J. 91
ADMINISTRATIVE CONTROLS i
(M
- d. proposed changes to Technical Specifications and the Operating License;
- e. Violations of applicable codes, regulations, orders, license t
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;
! 1. Significant operating abnorma11 tins or deviations from normal and expected performance of equipment that could affect nuclear safety;
- j. The performance of the corrective action program; and 4 k. Audits and audit plans.
Reports or records of these reviews shall be forwarded to the h:::tive 8 Vice hesidei.t .";;h:r within 30 days following completion of the review. L %a,4 -a c ro .,o c u c; AUDIT PROGRAM RESPONSIBfLITIES 6.5.3.7 tooeku ooush OyE The NSAB audit program shall be the responsibilit of the b elity end A!!e:::;;t 0;rvi;ee 0; pert;;;t. NSAB audits shal be performed at -
least once per 24 months in accordance with Nuclear Group Procedures 1 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 41M 6-11 Amendment No. J. M, 77, 91 1
l ADMINISTRATIVE CO U R0LS JInuary 17,1996 ,
! I 1
- g. Other activities and documents as requested by the Lee.'.L. t";;
J. ..Me..t - 1.;;;;r. bee 4, cro + cad EGDEDI 5.5.3.8 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 ites 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 Proaram '
Funetion l 6.5.4.1 TheQ ......
..LhW"55 vui LON PF. un.M.wr or %Y*h%.k..I .......
"Y' " "D'.W
.n........n......... p'.b.. .k. \
may establish a Station Qualified Reviewer Program whereby required i
reviews of designated procedures or classes of procedures required by l Specifications 6.5.1.6.a and 6.5.2.6.a are perfomed by Station Qualified Reviewers and approved by designated managers. These reviews are in lieu of reviews by the PORC or SORC. However, procedures which I require a 10CFR50.5g evaluation must be reviewed by the PORC or 50RC. l Reseensibilities 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.
l c. Ensure cross-disciplinary reviews are perfomed by a Qualified Reviewer (s in affected disciplines, or by other persons l designated)by cognizant sanagers or directors as having specifi l
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 M performed in accordance with the provisions of 10CFR50.5g to verify that g
Millstone 7198 Unit 1 6-12 Amendment No. M, U, 91
i i
, ADMINISTRATIVE CONTROLS '
an unreviewed safety question does not exist. This screening will i be rformed personnel trained and qualified in performing }
j IOC R50.59 ava untions.
4 i e. Provide for written recommendation by the Qualified Reviewer (s) to the responsible Manager for approval or disapproval of procedures i and 6.5. programs considered under specification 6.5.1.6.a and 1.6.a and that the procedure or program was screened by a qualified individual and found not to require a 10CFA50.59 4
evaluation.
j 6.5.4.3 If the responsible manager determines thit a new program, procedure, or
{
change thereto requires a 10CFR50.59 evaluation, that manager will i
1 ensure the "equired evaluation is rformed to detemine if the new 2 procedure, program, or change invo ves an unreviewed safety question.
The new rocedure, program, or chan e will then be fomarded with the 10CFR50. 9 evaluation to PORC/$0RC or o:ndoe, review.M opudim .
i 6.5.4.4 personnel reconnended to the Station Qualified Reviewers shall be t
designated in writing by the St:r Unit Dir;;ta or 5::in V+ee l
! Precid::t - Mi!!stm Stetten for each procedure, program, or class of ;
i procedure or program within the scope of the Station Qualified Reviewer i Program. m.956 cad i Pm,vuy oh, orncWk viu_ EhsiM i i
j . 6.5.4.5 Temporary procedure changes shall be made in accordance with 1
1
- Specification 6.8.3 with the exception that changes to procedures for i witch reviews are assigned to Qualified Reviewers will be reviewed and j approved as described in Specification 6.5.4.2.
l Records I
! 6.5.4.6 The review of procedures and programs performed under the Station
! Qualified Reviewer Program shall be documented in accordance with )
l administrative procedures.
t'
! Trainino and Dualification
- 6.5.4.7 The training and qualification requirements of personnel designated as i
a Qualified Reviewer in accordance with the Station Qualified Reviewer l 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 i
- b. Six years of nuclear power plant experience; i
! OR J
j c. An equivalent combination of education and experience as approved
! by a department manager.
Millstone Unit 1 SIN 6-13 Amendment No. 91
. _ . . . - - _- - . - _ _ . - . _ _ - - - _ . . - - . . - - - . - - ~ _ - -
l
) ,
l ADMINISTRATIVE CONTROLS 6.6 REPORTABLE EVENT ACTION g l 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 shall be submitted to the Chairperson of j the NSAB and the M -tive "in O e;if zt "n h a.
Preuben + cro + cNo 6.7 SAFETY LIMIT VIOLATION l
, 6.7.1 The following actions shall be taken in the event a Safety Limit is
- violated
l a. The unit shall be placed in at least HOT STANDBY within two hours.
i l b. The NRC Operations Center shall be notified by telephone as soon as possible and in all cases within one hour. The E =;tiv i p,u,34, moe"in huii...t "xhn and the Chairperson of the NSAB shall be j 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 (1) applicable circumstances preceding the violation, (2) effects of the vlolation 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 Commiission, the Chairperson of the NSAB and the Dn;tiv: " ::
Enifrt - Mer within 14 days of the violation. Br5<3ra", cmodo
- e. Operation shall not be resumed until authorized by the Commission.
6.8 PROCEDURES 6.8.1 Written proc'sdures shall be established, implemented and maintained !
covering the activities referenced below.
i
- a. The applicable procedures recommended in Appendix 'A" of Regulatory Guide 1.33, February,1978.
- b. Refueling operations,
- c. Surveillance activities of safety related equipment.
- d. Not used. l
- e. Not used. I
- f. Fire Protection Program Implementation.
Millstone Unit 1 6-14 Amendment No. J, M, 77, FJ. 94 j 0233
^C l
J. nuary 17,1996 ADNINISTRATIVE CONTROLS L
} g. Quality Control for effluent monitoring using the guidance in Regulatory Guide 1.21 Rev.1. June 1974.
- h. Radiological Effluent Monitoring and Offsite Dose Calculation Manual (REMODCM Environme)ntal Monitoring. implementation, except for Section I.E.,
6.8.2 a. The O,,y L c,eer%Unit v44 Dir=ter mble o p krusor Set:r %H bm & ~ newk
'.'ic; Tresident - Mill:tene hedesM St4 Mon may designate specific procedures and programs, or classes of procedures and programs to be reviewed in accordance with the Station Qualified Reviewer Pregram in lieu of review by the PORC/50RC. The review per the Qualified Reviewer Program shall be in accordance with Specification 6.5.4. n,4 g c4
- b. Procedures and thereto, shall beprograms a rovedlisted in Specification 6.8.1[and changes by the M= lear l'rit Dire;t.. or SeMar-
-Y! = Pr::id;nt "!gg:4 =: Station or by co nizant Mana er or i N dml / S<way // Directors Unit-Otrewho are designated ter er1Sent:r ase the Yi:: Pr::td ApprovaSt:t!en, t "111:t=: Authority as ytheNueT[a d"" er teewW ~ .
specified in administrative procedures. The Approval Authority for V"' P"5Md each procedure and program or class of procedure and program shall be specified in administrative procedures.
- c. ification 6.8.1, and changes thereto, shall be Each procedure reviewed by the POR of SpkORC and shall be approved by the E:1::
Dir;ctor or;Seter Y!ce Pre:td:nt, Hiiin ... neiien, or bej reviitwe3[
gw ,
m, and approved in accordance with the Station Qualified Reviewer i
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 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 M unit affected. ,5
- c. Thechangeisdocumented,reviewedbythePORCh0RC,ortheStation Qualified Reviewer Program, as applicable, and approved by the- 1 Station Qualified Reviewer Program Managar, ce th: Ecleer Unit Qugptm+tsD tirect;r :r S:ni:r Yin Pr::tdet "M19ane Stetten 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 REMODCM.
Millstone Unit 1 6-15 Amendment No. M , 71, 91 em
ADMINISTRATIVE CONTROLS 4/26/94
! 6.15 RADIOLOGICAL EFFLUENT MONITORING AND OFFSITE DOSE CALCULATION MANUAL
- (REM 00CM)
I section I, Radiolo ical Effluents Monitoring Manual (RD91), shall outline the i sampling and anal is programs to determine the concentration of radioactive materials release offsite as well as dose cosaitments 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 0DCM), shall describe the l
methodology and parameters to be used in the. calcul(ation of offsite doses due i l
. to radioactive gaseous and 11 uid effluents and in the calculations of gaseous l and liquid effluent monitorin instrumentation alars/ trip setpoints consistent with the applicable LC0's con ained in these technical specifications.
l 4
- Changes to the REM 0DCM: .
- a. Shall be documented and records of reviews perfomed shall be retained l as required by specification 6.10.2.s. This documentation shall l l contain:
\
! 1) Sufficient information to support the change together with the j
apgropriate
=" analyses or evaluations justifying the change (s),
!t A determination that the change will maintain the level of l 2) i radioactive affluent control required by 10 CFR 20.106, 40 CFR l l Part 190, 10 CFR 50.36a, and Appendix I to 10 CFR Part 50 and 4 3
not adversely impact the accuracy or reliability of effluent, .
q dose, or retpoint calculations. - l
! b. Shall become effective after review and acceptance by 50RC and the approval of the :g.ig' , gegd:Jt,- lists: Steti n.
l j c. Shall be submitted to the Commission in the fom of a complete, i legible copy of the entire RD91 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, t
clearly indicate indicating the date (e.he area g., manth/ of the year) thechange pagewas thatimplemented.
was changed, and shal 1
)
}
i i e Millstone Unit 1 6-13 Amendment No. 77 77, 77, 74 me
_ . _ _ _ _ . _ _ _ - . _ _ _ . _ .._ _ _ _ _ ___m _
i 4/26/94 ADMIN!57RATIVE CONTROLS l
r.= j 5.1 RESPONSfRILITY !
Q 6.1.1 Theh.aeQCluel ExecAkChee 8f0) M C\kf WOW 0 % d'"*)
knier .in 7.nive - Millets; St; tier, shall be responsible !
for overall operation of the Millstone Station Site while the tinr Unit l l Director
" shall be responsible for opelLLion of the unit. The !=ter t"a NsMmcoo !
.._:fd=t - Milht= St:ti= and4Kn> Unit Director shall each delegate in writing the succession to these responsibilities during their absence.
5.2 ORGANI7ATf0N
~
6.t.1 0FFSITE AND ONSITE ORGANf7AT10NS t
Onsite and offsite organizations shall be established for unit operation and corporate sanagement, respectively. The ensite and offsite organizations i shall include the posititens for activities affecting the safety of the nuclear power plant.
l
- a. Lines of authority, responsibility, and comunication shall be 1
' established and defined for the higher management levels through intermediate levels to and including all operating organization '
positions. These relationships shal be documented and updated, as appropriate, in the fom of organization charts, functional descrip-tions of departmental responsibilities and relationships, and job descriptions for key personnel positions, or in equivalent foms of i documentation. These requirements shall be documented in the Quality Assurance Topical Report.
d M
- b. The .E...@. .i.*^.h.._NM.
. . . . . . . . . - . 89.*/ 9,.$. .D...L.. ,. .. ,_ shall be respons 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.
r,esiaca, cro u cuo
- c. The Imthe in " ;;fdstti;r shall have corporate respon-sibility for overall plant nuclear safety and shall take any measures needed to ensure acceptable perfomance 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 I recovery from reactor trips.
Millstone - Unit 2 6-1 Amendment No. (J. 77 77, 77.
em 9,1,199,119,191,191.
n
ADNINISTRATIVE CONTROLS July 16,1996 1 6.4 TRAINING A retraining and replacement training program for the facility staff shall be maintained under the direction of the Or.;r Yi:: Prc:id.r.t - Mill;ter.. mibW"*'"Y Oa)"2 56et4ea and shall meet or exceed the requirements and reconnendations of Section 5.5 of ANSI N18.1-1g71 and 10 CFR Part 55.5g. The Director-Nuclear Training has the overall responsibility for the implementation of the Training Program.
6.5 REVIEW AND AUDIT 6.5.1 Plant Doerations Review Comittee (PORC)
Function 6.5.1.1 The PORC shall function to advise the Mus4 ear Unit Director on all l 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: !
- l Plant Operations '
Engineering Reactor Engineering j Maintenance Instrumentation and Controls Health Physics Chemistry Work Planning and-Conteel Quality krm;; Assocaeu 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 be appointed in writing by the Neekw Unit Director. The Chairperson and alternate Chairperson of the PORC shall be drawn from the PORC members and be appointed in writing by the .9 :1;;r Unit Director.
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. 1 9 , 177. JJJ
- 200 ..
m
_ . - - . . - _ - - - . - - _ - . _ - - - . - - - - _. _ . - - .- - = - .-. --
l i ADNINISTRATIVE CONTROLS
- 3.n,..m 17 1oog Meetina Freousnev i
8.5.1.4 The PORC shall meet at least once per calendar month and as convened by the PORC Chairperson.
9 i
! ALREE 6.5.1.5 A quorum of the PORC shall consist of the Chairperson, or Vice i Chairperson, ;- S h- Y! e P. ett t Mil ht::: St: tie and four l members including alternates.
i i Reznonsibilities i
j 6.5.1.6 The PORC shall be responsible for:
a.
j Review required byof 1) Specification 6.8 and changes thereto, 2) allall proc programs, except common site programs, required by l
1 Specification 6.8 and changes thereto, 3) any other proposed 1rocedures, programs, or changes thereto as determined by the i
! Ah;r Unit Director to affect nuclear safety. Procedures and i programs required by Specification 6.8 that are designated for i rev' ow and approval by the Station Qualified Reviewer Program j do not require PORC review. j
- 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 g
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 recomendations to prevent recurrence to the herth: Yk Preefden4-Nuelear and to the Chairperson of the Nuclear Safety Assessment Board. Fus&nb eo W CNo d tuwe. Ona a new c%,
- f. Review of all REPORTABLE EVENTS.
- g. Review of facility operations to detect potential safety hazards.
, h. Perfomance of special reviews and investigations and reports thereon as requested by the Chairperson of the Nuclear Safety Assessment Board.
- 1. Render deteminations 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.
g J. Review of the fire protection program and implementing procedure.
Millstone Unit t 66 Amendment No. 17. TJ, 77, ms 19, 111, 171, 111, 106. 191. 193 , a
! July 16,1996 ADNINISTRATIVE CONTROL 5
?
a
! Authority i
6.5.1.7 The PORC shall:
l a. Recomend to the N;;h;r Unit Director written approval or
! disapproval of items considered under 6.5.1.6(a) thrcugh (d) above.
M 6ae.042 %wy c h er
- b. Provide immediate written notification to the 0;;i:r Yi n 1 P=:iir.t - Milhte: St:tien. E==tte Yin P=:iint ";: leer and the Chairperson of the Nuclear Safety Assessment Board of i disagreement between the PORC and the ";;;;;r Unit Director; j however, the "=let- Unit Director shall have responsibility i for resolution of such disagreements pursuant to 6.1.1 above.
Records 1
- 6.5.1.8 The PORC shall maintain written minutes of each meeting and copies
! shall be provided to the S;ni;r Yin Preid;nt ".ilht=: St;tir, OM O.'ecbr
! and Chairperson of the Nuclear Safety Assessment Board. w tL M s4 m. O d a l Ree.vu y e Mug 6.5.2 Site Ooerations Review Committee (50RC) 4 i Function prassbeid,cco A cNo 1
6.5.2.1 The 50RC shall function to advise the S;;i:r Yin Pr=innt -
- W1hte St
- tir on all matters related to nuclear safety of the
- entire Millstone Station Site.
1 Comoosition i
I 6.5.2.2 The 50RC shall be composed of the:
i nuear E4aeeigh Sorrerk
=t:r Yin Prn..;nt L%mi Muu
! Chairperson: ".il uten; St:ti= ., t i
Member: Unit 10;rnt:r oseAr UniF o pua h;ns I Member: Unit 2 Director i Member: Unit 3 Director i
Member: 7 " nit Servin: Dirntarfi;efh M'*
"n.hr E '
. Sit: Services Di-ecte" % ,.og, G e t Gefvie.3
- Member: Designated Member of Unit 1 PORC i Member: Designated Member of Unit 2 PORC 1 Member: Designated Member of Unit 3 PORC i
Member: Designated Member of Q=lity Serri=;o veno Nucb4 j i
- The senior "=he Unit Director in attendance shall be the Vice- l
- Chairperson. m a
1 Alternates: /OM' "
6.5.2.3 Alternate members shall be appointed in writing by the 50RC 1 Chairperson to serve on a temporary basis; however, no more than two
. alternates shall participate in SORC activities at one time.
i Millstone Unit 2 6-7 Amendment No. JJJ. 77J. JJJ.
- 200
)
April 24,1996 j ADMINISTRATIVECONTROLS i
- Meetina Frecuenev i
6.5.2.4 The 50RC shall meet at least once per six months and as convened by j the 50RC Chairperson.
J
{ D
! 6.5.2.5 A quorum of the 50RC shall consist of the Chairperson or Vice !
} Chairperson and five members including alternates. i
} Resnonsibilities i
i 6.5.2.6 The 30RC shall be responsible for:
i a, Review of 1) all common site procedures required by specift-I cation 6.8 and changes thereto, 2) all common site programs, required by Specification 6.8 and changes thereto, 3) any other proposed
- pu,,kd, uo m> cwpby & *-procedures, it" Viceprg; 7;;;.. rams, ;t _orMCh7;; changesSt
- tfan thereto to as affect determined site nuclear safety. Common site programs and procedures required i i i
by specification 6.8 that are designated for review and j approval by the Station Qualified Reviewer Program do no l l require 50RC review. ,
?
i b. Review of all proposed changes to Section 6.0 ' Administrative l c.
Controls" of these Technical specifications.
Performance of special reviews and investigations and reports g
I j as requested by the Chairperson of the Nuclear Safety
- Assessment Board.
J
{ d. Not used. l
- e. Hot used. !
i f. Review of all common site proposed tests and experiments that j affect nuclear safety.
i i g. Review of all common site proposed changes or modifications to l systems or equipment that affect nuclear safety.
I h. Render deteminations in writing or meeting minutes if any ites:
considered under 6.5.2.6(a) through (g) above, as appropriate
- and as provided by 10CFR50.5g or 10CFR50.g2, constitutes an i
unreviewed safety question or requires a significant hazards
} consideration determination.
i
- 1. Review of the common site fire protection program and i implementing procedures.
i 4
i 1,
! N111 stone unit 2 6-s Amendment No. U , g , 19 , 7# ,
j am 15 , #1, #A 196
1 ;
i ADNINISTRATIVE CONTROL 5 t.. . 2 . r 9^- l l Authoritv 6.5.2.7 The 50RC shall:
l(/ a.
% & A ceo eoC w re;;:rm"'"-+-- "J^-
l e
Recommend to the Sestw=MEK '
- written a> proval or disapproval in meeting minutes of items
i considerec under 6.5.2.6(a) through (g) above.
i b. Provide ismediate written notifiestiojtor meeting minutes to !
the Lec. tin '-t :--de-n-ifucisar amDthe Chairperson of the >;
Nuclear safety Assessment Board of disagreement between the ;
50RC and the Senier L. huid.r.t - M!!hten. Einiion:
! however, the $=hr t"= ."=id=t - M!!!st=- St:tte(shal
- have responsibility for resolution of such disagreements
, pursuant to 6.1.1 above. ~ --
l i Records ned, CE0 **
- i
! 6.5.2.8 The 50RC shall maintain written minutes of each meeting and copies i shall be provided to the Seater t' ice Tre;id;r.t ".ilu;;ae Ot .ti=
! and Chairperson of the Nuclear Safety Assessment Board. l' i
4 @ #O 6.5.3 NUCLEAR SAFETY ASSESSMENT BOARD (NSAB) %$hJ g
! FUNCTION l i
6.5.3.1 The minimum qualifications of NSAB members are as follows:
i.
l(
- a. The Chairperson and NSAB members shall have:
]
, 1. An academic degree in an engineering or physical science ,
3 field, or hold a senior management position, and i
1 2. A minimum of five years technical experience in their l respective field of expertise.
- i
- b. The NSAB shall have experience in and shall function to provide j independent oversight review and audit of designated activities -
in the areas of: f'
- 1. Nuclear power plant operations; ,
- 2. Nuclear engineering; ,
- 3. Chemistry and radiochemistry; '
i 4. Metallurgy;
! 5. Instrumentation and control; 4
i j 6. Radiological safety; I
- 7. Mechanical and electrical engineering; and J
l( 8. Quality assurance practices.
! N111 stone Unit t 69 Amendment Nos. FF, 77, 77, me 11,111,171, i 119,IFF,193
ADMINISTRRl!VE CONTROLS J;nuary 17,1996 l l
Paa s bsa,cro ad cNo ;
The NSAB serves to advise the L;;-tiv; Yh; "...We..t - i;1eer on matters related to nuclear. safety and notify the truth: Yue W
i f'+<*ded ec^oJ--r f f--t - Mechr within 14 hours1.62037e-4 days <br />0.00389 hours <br />2.314815e-5 weeks <br />5.327e-6 months <br /> of a safety significant '
disagreement between the NSAB and the organization or function being reviewed. -
COMPOSITION ;
A cNo f ,g;[p P- :tdzt - 5;hr shall appoint, in writing, a 6.5.3.1 The Erds 43r ..- .. -
minimum of seven members 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. I ALTERNATES 6.5.3.3 All alternate members shall be a p,,, g f--"*'"-
- hall - P- :ida.t - 1;1e;ppointud,
- ; ho,tever,innowriting, bytwo more than the
! alternates s participate as members in NSAB activities at any one time.
MEETING FREQUENCY l
l 6.n.3.4 The NSAB shall meet at least once per calendar quarter.
EEBE 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. l The safety and systems, evaluations tests for or changes to procedures,dequipment, experiments complete under theor
! 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; l b. Proposed changes to procedures, equipment, or systems that involve an unreviewed safety question as defined in l 10 CFR 50.59; ;
- c. Proposed tests or experiments that involve an unreviewed safety question as defined in 10 CFR 50.59;
- d. Proposed changcs to Technical Specifications and the Operating
! License; i
N111 stone Unit t 6-10 Amendment No. 17. (J. 77,193 eau lif,191,190,
F;brunry 14,1995
] ADMIN!sTRATIVE CONTROLS I
- 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 6,3,J, uo wetn:tt= Yt:0 ."rxitzt "r er 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 b:'ity u y, r % 17.t Ords;; 5;atr.L NSAB audits shall be performed o,g,ma, )q __-+ M .5:::at least once per 24 months in accordance with Nuclear Gri!
Procedures and shall encompass ,
i
- a. The conformance of unit operation to provisions contained {
within the Technical Specifications and applicable license :
conditions; l
- b. The training and qualifications of the unit staff;
- c. The implementation of all programs required by Specification 6.8; , j
- 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 4
- g. pr,activitiesanddocumentsasrequestedbytheEmesut4ve m .. . . . . . . . . . . . . . . . .
Preside.&, t.go , _b cno Millstone Unit t 6-11 Amendment No.19,45,64, essi 93,126,111,13#,163,184
ADMINISTRATIVE CONTR01.5 Jrnu ry 17,1996 l
RECORDS 6.5.3.8 g
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. Recomended approval or disapproval of items considered under i 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 l
6.5.4 Station Dualified Reviewer Procram Function 6.5.4.1 m,%% dah 3 12uovvy o%u The N;;1::: Unit Director or 5:r.ter Yt:: Presider.t "ill:t:::
Statienemay establish a Station Qualified Reviewer Program whereby NfEdEE required reviews of designated procedures or classes of procedures l 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 ( l the PORC or SORC.
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 Qualtfled 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)inbyaffected designated 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 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 I in performing 10CFR50.59 evaluations.
Millstone Unit 2 6-12 Amendment Nos. JJ, JJ, JJ, JJJ, 193 0207
ADMINISTRATIVE CONTROLS J nuary 17,1996
- 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.gg evaluation.
6.5.4.3 If the responsible manager determines that a new program, procedure, or change thereto requires a 10 CFR 50.5g 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 50.5g evaluation to p0RC/$0RC for review.
6.5.4.4 personnel recommended to be Station Qualified Reviewers shall be designated in writing by the Neolew Unit Director or Sehr Yt:
om wa e-r -Pr::f t:t - Milht;;; St:tt::for each procedure, program, or class of the sco Rev: procedure ewer Program. or program within]ee ou&pe&pf P-es the Station u Qualified 6.5.4.5 Temporary procedure changes shall be made in accordance with Specification 6.8.3 with the exception that changes to procedures i for which reviews are assigned to Qualified Reviewers will be l reviewed and approved as described in Specification 6.5.4.2. '
M 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:
l
- a. A Bachelors degree in engineering, related science, or technical discipline, and two years of nuclear power plant experience; i OR
- b. Six years of nuclear power plant experience; On
- c. An equivalent combination of education and experience as approved by a Department Manager.
(
Millstone Unit R 6-13 Amendment Nos. 193 een
April 24,1996 ADNINISTRATIVE CON NOL5 6.6 rep 0RTABLE 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 O e:: tin "i n 7; aff::t "::h r.
Pre stheO i CCqAM CMC 6.7 SAFETY LIMIT VIOLATION 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 HDT 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 AmesuMwe Pu.W4 un myte; y;;jj t " :hei 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 redewed by the PORC. This report shall describe: &
(1) applicable circumstances preceding the violation, W (2) effects of te ~iolation 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 Commission, the Chairmrson of the NSAB, and the EmesuHve-Hee Pus,64, uv.s coo Pres 4 dent 4heeleer wittin 14 days of the violations.
- 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 1.33, February, 1978.
- b. Refueling operations.
- c. Surveillance activities of safety related guipment.
- d. Not used.
i
- e. Not used.
N4!? stone Unit t 6-14 Amendment Nos. M . H . N JJJ.
sm Hi, in, TN, in,196 m
i
, ADMINISTRATIVE CONTROLS Jinusy 17,1996 i .
- f. Fire Protection Program implementation. !
- g. Quality control for effluent monitoring using the guidance in i Regulatory Guide 1.21 Rev.1, June 1974.
I h. Radiological Effluent Monitoring and Offsite Dose Calculation .
. Manual (REM 0DCM) implementation, except for Section I.E., '
- Radiological Environmental Monitoring.
, 6.8.2 a. The Nuekte Unit Director or....es .gu os,4-1 m e 7. ..Ruevvy oW,us.:
N .nl - Giill;t i
Stetten,may designate specific procedures and programs, or classes J
on nusLc Dec ' of procedures and programs to be reviewed in accordance with the
, PusM Station Qualified Reviewer Program in lieu of review by the PORC/
l 50RC. The review per the Qualified Reviewer Program shall be in
- accordance with Specification 6.5.4. i j b. Procedures and programs listed in Specification 6.8.1, and changes i thereto, shall t>e a roved by the Neeleae Unit Director or 4en+er N'"7 # g""'N +ee-Sros*&rt V
y2 M!g t: : St:ti:1.pr by cognizant Manager or rs who are designated as the Approval Authority by the i Unit Director or ! hr Y! 0 Pre 'ds.t "ill.tene E;D./M 1
1 ornw h We- 56e64ensas specified in administrative procedures. The Approval
- "5" d Authority for each procedure and program or class of procedure and j
E program shall be specified in administrative procedures.
- c. Each procedure of Specif.ication 6.8.1, and changes thereto, shall 4
be reviewed by the PORCMORC and shall be ap9 roved by the Nuclear
- [c.rf6M, cm.cm Di rector - '--'- "'- *--"- " "' " ^ - - " ' ' -
or be
, Eco ty reviewed and approved in accordance with ths 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 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 1
' staff, at least one of whom holds a Senior Reactor Operator's License on the unit affected.
- c. Thechangeisdocumented,reviewedbythePORCNORC,orthe A Station Qualified Reviewer Program as applicable, and approved bfumr Na% bM-+the Station Qualified Reviewer Program Manager ;r "":h:r 'J:'t '
"## ' ^ ' ' <
Sir::t r/S::icr Y! 0 Pr :'d::t M!!ht::: 'tation within 14 days I of implementation.
6.8.4 Written procedures shall be established, implemented and maintained couring Section I.E. Radiological Environmental Monitoring, of the REMODCM.
]b.
Millstone Unit 1 6-15 Amendment Nos. 17,77,77.J/1, em 191, 179, 193
4/26/94 l
{ ADNINISTRATIVE CONTROLS l
5.15 RADIOLOGICAL EFFLUENT MONITORING AND OFFSITE DOSE CALCULAff0N MANUAL
{ fREMODCM) i Section I, Radiological Effluents Monitoring Manual (RDef), shall outline the l
j sampling and analysis programs to determine the concentration of radioactive materials released offsite as well as dose couaiteents 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 j 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 5etpoints consistent with the applicable LC0's contained in these Technical Specifications.
i
! Changes to the REMODCM:
- a. Shall be docuinented and records of reviews perfomed shall be retained as required by Specification 6.10.2m. This documentation
- shall contain
- 1) Sufficient infomation to support the change together with the appropriate analyses or evaluations justifying tse change (s),
and
- 2) A determination that the change will maintain the level of radioactive affluent control required by 10 CFR 20.106, 40 CFR i
Part 190,10 CFR 50.36a, and Appendix ! to 10 CFR Part 50 and
! not adversely impact the accuracy or reliability of affluent,
- dose, or setpoint calculations.
i
't b. ~5 hall become effective after review and acceptance by 50RC and the approval of% th; S:-f: Mice "r::19at - Pill:ter.e Ct: tie:.
,ae v, c eo a a c m I i
- c. Shall be submitted to the Commission in the form of a complete, legible copy of the entire RD91 or 00CM, as appropriate, as a part i
of or concurrent with the Annual Radioactive Effluent Report for the period of the report in which any change was made. Each change j 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
J li j gijlstone Unit t 6-24 Amendment No.177. JJ7,177,174 1
I 1
- i. '
4/26/ 94
, ADMINISTRATIVE CONTROLS 1
6.1 RESPONSIBILITY g h***
{ g 0sA,& he Ckl.ll-OCrie.v(c.A OS-S t4 d(Cd$) f) C)p* y $9 6.1.1 TheG::!:r"':: Ex:it .t Mill:t::: St:tiedshall be rannonsible 4
for overall operation of the M 11 stone Station site while thed::':;SUnit l nir.eter shall be responsihla fo i C. ...wid - T.;11:ter: 5t:t':-Dan n of the unit.
Unit Director shall eacn seisgaT.e in Thr " ""
j writing the succession to triese re lities during their absence.
6.2 ORGANIZATION
[g'[f 6.2.1 l 0FFSITE AND ONSITE ORGANIZATIONS , f
{ Onsite and offsite organizations shall be established for unit operation and
! co}oratemanagement,respectively. The onsite and offsite organizations 1
e the positions for activities affecting the safety of the nuclear j a. Lines of authority, responsibility, and communication shall be 3
- established and defined for the highest management levels through j 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-
} l 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.
g 3g g,
! b.Theki:rYi::7..."en, "
.ill:tr:: Statid shall be responsible l for overall unit safe operation and shal have control over those l i
onsite activities necessary for safe operation and maintenance of i the plant. Etunamur. O C60 t c40 p
i c.The@ecetiveYie a rer!&:t ".;1@ shall have corporate responsi-bili",y for overaii piant nuclear safety and shall take any measures needed to ensure acceptable performance of the staff in operating, maintaining, and providing technical support to the plant to ensure nuclear safety.
- d. The individuals who train the operating staff and those who carry out health physics and quality assurance functions may report to the appropriate onsite manager; however, they shall have sufficient organizational pressures.
freedom to ensure their independence from operating 6.2.2 FACILITY STAFF
- a. Each on-tuty shift shall be composed of at least the minimum shift crew composition shown in Table 6.2-1; MILLSTONE - UNIT 3 6-1 0192 Amendment No. JJ, JA 90 !
09/28/92 ADMINISTRATIVE CONTROLS 6.2.3 INDEPENDENT SAFETY ENGINEERING GROUP (ISEG) r FUNCTION 6.2.3.1 The If,EG shall include, as part of its function, exarination of unit operating characteristics, NRC issuances, industry advisories, Licensee Event Reports, 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, l operations 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 (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 nucle'ar 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 activitics 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 ISEG shall be prepared and maintained, and quarterly reports of completed safety evaluations will be made to the Vice President-Nuclear Q :r:t W.; :: ~'e g g ,, m ,
l 6.2.4 SHIFT TECHNICAL ADVISOR l
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.
MILLSTONE - UNIT 3 64 Amendment No. 21,69 DD12
ADMIN!5TRATIVE CONTROL 5
- .
- y w, r..:
e 6.3 FACILITY STAFF OUALIFICATIONS l l l 6.3.1 Each member of the facility staff shall meet or exceed the minimum 4
qualifications of ANSI N18.1-1971* for comparable positions, except for the l Health Physics Manager who shall meet or exceed the qualifications of I Regulatory Guide 1.8, Revision 1, May 1977.
i 6.4 TRAINING i
! 6.4.1 A retraining and replacement training procram for the facility staff l j
eh=11 be maintained under the direction of them:ter Ytre "r::id::t
! Chul:t:: StetMeand shall meet or exceed the requirements and i recomenamuons if Section 5.5 of ANSI N18.1-1971 and 10 CFR Part 55.59. The i Director-Nuclear Training has the overall responsibility for the implementation of the Training Program. p], , ,y , 4,r 7 l
l 6.4.2 Deleted. MW8" i
o n,cere 6.5 REVIEW AND AUDIT l
! 6.5.1 PLANT OPERATIONS REVIEW COMMITTEE (PORC)
FUNCTION l
6.5.1.1 The PORC shall function to advise th;h:1;:) nit Director on all l matters related to nuclear safety.
i 1
I COMPOSfTION
, 6.5.1.2 The PORC shk11 be composed of nine to eleven members. Members i shall collectively have experience and expertise in the following areas:
1 j Plant Operations
! Engineering
} Reactor Engineering Maintenance j Instrumentation and Controls
! Health Physics i Chemistry l
Work Planning 9 C;;tr O
- Quality Geev4eeb AssocNe4 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 j their respective field of expertise. The members of PORC shall be appointed j in writing by theGluekeO Unit Director. The Chairperson and alternate i Chairperson of the PMC thall be drawn from the PORC members and be appointed j in writing by the @ Unit Director.
l 1 *For the period 9nding three years after the issuance of Amendment No. 94, the j Operations Manager will be permitted to have held a senior reactor operator
- license at a similar Pressurized Water Reactor other than Millstone Unit No. 3 and at least one of the Operations Assistant (s) shall hold a senior reactor
! operator license.
1 MILL 5 TONE - UNIT 3 6-5 Amendment No. JJ JJ. JJ, JJ JJ.
130 ess4 l
ADMINISTRATIVE CONTROLS J nunty 17,1996 ALTERNATES ~-
6.5.1.3 All alternate members shall be a #
Chairpersontoserveonatemporarybasis;phointedinwritink4 owever no moreby thetwo han PORC alternates shall participate as vo';ing members in kORC activities at any one time.
MEETING FREQUENCY 6.5.1.4 The PORC shall meet at least once per calendar month and as convened by the PORC Chairperson.
22381 6.5.1.5 The quor Chairperson n ::;um of the ir *,;e PORC -shall 7...Mei.t consist of the Chairperson Milhttene-64eHort or Vice and four members including alternates.
i l RESPONSIBILITIES i
l 6.5.1.6 The PORC shall be responsible for:
- a. Review of: 1 all rocedures exce c$t comon site procedures required by(Sp)ecifi!ation 6.8,and anges thereto 2
! exceptcommonsiteprogramsrequiredbySpecificalion)allpro, 6.8 and grams, changes thereto, and 3 3 rocedures program: or changes thereto as daue)nined r by the 41any other pro Unit Direc, tor tog affect nuclear safety. Procedures and programs required by Specification 6.8 that are designated for review and approval by 1;he Station --
Qualified Reviewer Program do not require PORC review.
w
- 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 including the preparation and forwarding of reports covering eva,lua-tion and recommendations to prevent recurrence to the E::::.;tive h Yi:: .".::id::t .t?:= and to the Chairperson o,f the Nuclear Safety )
Assessment Board; fresa d dEo and cAJo M
- f. Review of all REPORTABLE EVENTS; " #'
- g. Review of facility operations to detect potential safety huards;
- h. Performance of special reviews investinations the C of the Nuclear l regts thereon s sment Boardas or therequested "ig.F.eete by,g.hairperson,
{.cne or
- 1. Render deterstnations in writing if any ites considered under Specification 6.5.1.6a. through d. above, as appropriate and as provided by 10CFR50.59 or 10CFR50.92 constitutes an unreviewed ge safety question w determination. , or requires a significant hazards consideration NILLSTONE - UNIT 3 66 AmendmentNo.7f,pp,pf,77.J7f.125 was
r I
July 16,1996 ADNINISTRATIVE CONTROLS L 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:
- a. Recommend to the "::1: r' Unit Director written approval or disapproval of items considered under Specification 6.5.1.6a.
through d. above; and mas 4o^c_063 3 fleocery Ner l b. Provide written notification to the -!:rier V!: a r ::id::t -
l MPl ter St:ti n,
- tiv: Yi:: . re:ider.t Mu&r and the
! Chairperson of the Nuclear Safety Assessment Board of disagreement l between the PORC and the M;:1::r Unit Director; however, the M :1:r l Unit Director shall have responsibility for resolution of such disagreements pursuant to Specification 6.1.1.
1 RECORDS 6.5.1.8 The PORC shall maintain written minutes of e_ach meetina and copies shall be provided to the Chairperson of the Nuclear (Senior safety Vice_P_
Assessment resident Board. - Millstone
( gg,1 Ovec k e aStationland the mus4 cat Onil-6.5.2 SITE OPERATIONS REVIEW COMMITTEE fSORC) Rec,voy c#u.3er
- f. E l1QN pres,henk m> and cuc>
6.5.2.1 The SORC shall function to advise the Se&r Yi,:: l'r::id:nt -
Mill: tea St tien on all matters related to nuclear safety of the entire Millstone Station Site.
COMPOSITION 6.5.2.2 The 50RC shall be composed of the:
Noctear En er Chairperson: :::ir Yi::gneecinq cu4 Mill:t
. r::ii..t SvPPod Reawy C4u.
r.: Ste^
Member: "-it 1 Oir;;;r w 'b M rs W + M
- ipa " !
Member: Unit 2 Director Member: Unit 3 Director wlac' Member: Unit 5:rvi::: Dir::ter 0,reckr . S *'Vi( *5 Member: Sit: Servi::: Oire;ter m.aagee, Genera \ scrudes Member: Designated Member of Unit 1 PORC l Member: Designated Member of Unit 2 PORC 1
Member: Designated Member of Unit 3 PORC Member: Designated Member of Q;;1ity !:rd:: rJxtear oeusght I The Senior ""&ar Unit Director in attendance shall be the Vice l l Chairperson. ,
5 f chr s Ub4- (P" MILLSTONE - UNIT 3 6-7 Amendment No. 77. 77 177 117.
- 130 '
e
l l l
April 24,1996 ADMINISTRATIVE 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 50RC activities at one time.
ItEETING FREQUENCY 6.5.2.4 The 30RC shall meet at least once per 6 months and as convened by the 50RC Chairperson.
EEE 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 for:
- a. Review of (1 tion 6.8 and c)hanges theretoall common site procedures required by Spec 2 all common site programs, required i
by Specification 6 l
l 4 DDC"5 C Eot nroceduras.
"';; n;; M;;;
nrocram.8
- s. or chances and thereto as ch,an(ge)s 3 any other prananad thereto,
- r _J d(e Cd "t!!
- - :: : :n ::Jto affect site nucTear safety.
E :-n site prol: rams I ano proceaures required by Specification 6.8 that are designa3ed for review and approval b Reviewer Program do not require 50RC review.y the Station Qualified I b. Review of kil proposed cha es to Section 6.0 " Administrative Controls" of these Technical ifications;
- 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 common site proposed tests and experiments that affect !
nuclear safety;
- g. Review of all conson site proposed changes or modifications to systems or equipment that affect nuclear safety; and
- h. Render determinations in writing or meeting minutes if any item considered under Specification 6.5.2.ti(a) through (g) above, as appropriate and as provided by 10CFR50.59 or 10CFR50.92 constitutes an unreviewed safety question or requires a significant hazards consideration determination.
- 1. Review of the common site Fire Protection Program and implementing procedures.
?
MILLSTONE - UNIT 3 6-8 Amen hent No. pp, pf, 77 J M , J M , 128
h 4
ADNINISTRATIVE CONTROLS January 17,1996 d AUTHORITY t I
, 6.5.1.7 The 50RC shall:
Pruikk, eEb au c^'o
- a. Recommend to the =i:r Y!= ." =tdnt - Mill:t=: St:ti: written l approval or disapproval in.meating minutes of items considered '
l i
under Specification 6.5.1.6(a) through (g) above, and
- b. Provid.e...imme,_diate written no,tification or meeting minutes to the
- m. -.. v _ ___ m .._ ... __2
.'- Chairperson of the Nuclear i Safety Assessment Board of disagreement between the 50RC and the
! Puc,A.4,c a .,a cm" S-a: yare preste-t Mit?:te-- uman, however, the Senfee-Wee fbrad
- . ;=f t-t M;II;t=: St:ti= shall have responsibility for " * " "
resolution of such disagreements pursuant to 6.1.1 above.
l RECORDS 6.5.2.8 The 50RC shall maintain written minutes of each meeting and copies I
shall be provided to the !=t:r YMe Pr=iAr.t - Mill:t=: St:tten and Chairperson of the Nuclear Safety Assessment Board.\Presidenb uo a4 CNo 6.5.3 NUCLEAR SAFETY ASSESSMENT BOARD (NSAB) i
- FUNCTION
- .o 6.5.3.1 The minimum qualifications of NSAB members are as follows
r i
j 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
- 1) Nuclear power plant operations;
- 2) Nuclear engineering;
- 3) Chemistry and radiochemistry; 4
- 4) Metallurgy;
~
- 5) Instrumentation and control; 1
- 6) Radiological safety; p.
1 NILLSTONE - UNIT 3 6-9 Amendment No. JJ. 77, 77. J71 125
==
P j ADMINISTRATIVE CONTROLS January 17,1996
- 7)
Mechanical and electrical engineering; and ) l
! 8). Quality assurance practices.
Passies r,[CEd ' '#
l The NSAB serves to advise thet;;ti;; i;; 7; id::t - 5;;1:TBon matters related to nuclear safety and not1Ty theC M;;tive "iG Tsui Gt - Ed ; -
- 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 d sagreement between the NSAB and_ the organization or function being reviewed.
pg gs ,,,-r, I COMPOSITION A_ g co L Petsootnr, a cgo tcao /
l 6.5.3.2 Thedn..ttr; i":: 'ri;td;r.t .";f ::O sha11 appoint, in writing, a j
minimum of seven members to tle M5AB and shalI designate from this membership, i
in writing, a Chairperson and a Vice Chairperson. The membership shall function to provide independent review and audit in the areas listed in I specification 6.5.3.1.
j ALTERNATES
,,,,,,, egg
} 6.5.3.3 A i Gustm " 1n alternate Truid=t members shall be appointed, in writing, by the
"=1::13 however, no more than two alternates shall i
participate as members in aus activities at any one time.
l MEETING FREQUENCY i
l 6.5.3.4 The NSAB shall meet at least once per calendar quarter. I i
i EXE5 t
6.5.3.5 The quorum cf the NSAB shall consist of a majority of NSAB members I
including the Chairper. ton or Vice Chairperson. No more than a minority of the
! quorum shall have line responsibility for operation of the same Northeast 5
Utilities' nuclear unit. No more than two alternates shall be appointed as j eembers at any meeting in fulfillment of the qtorum 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 experleents 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 la 10 CFR 50.59;
- c. Proposed tests or experiments that involve an unreviewed safety question as defined in 10 CFR 50.59;
)
NILLSTONE - UNIT 3 6-10 Amendment No. 77, JJ PJ,125 eens Corr. Ltr. 4 6 94
' ADMIN!57RATIVE CONTROLS
.i. n , ,, ,, 3 7 3aag i.
i d. proposed changes to Technical Specifications and the Operating l , License;
- e. Violations of applicable codes, regulations, orders, license requirements, or internal procedures having nuclear safety i
significance; l
- f. All Licensee Event Reports required by 10 CFR 50.73;
{ g. Indications of significant unanticipated deficiencies in any aspect i
of design or operation of structures, systems, or components that could affect nuclear safety;
)
i h. Significant accidental, unplanned, or uncontrolled radioactive J
releases, including corrective actions to prevent recurrence; l 1. Significant operating abnormalities or deviations from normal and I
expected performance of equipment that could affect nuclear safety; I J. The performance of the corrective action program; and i k. Audits and audit plans. 7,gs,er6 M Reports or recoris of these reviews shall be forwarded to thebe; M= i'kD i
(fr= M=t N=1gwithin 30 days following completion of the review.
l AUDIT PROGRAM RESPONSIBILITIES y
! 6.5.3.7 The NSAB audit program shall be the responsibility of the .:.li?
Ens J.:n;== isrnce; ;;F.;.e;;b NSAB audits shall be performed a ast i once per 24 months in accoraance with Nuclear Group Procedures and shall
- encompass
- a. The conformance of unit operation to provisions contained within the i Technical Specifications and applicable license conditions; j b. The training and qualifications of the unit staff; j c. The implementation of all programs required by Specification 6.8; 4
- d. The Fire Protection Program and implementing procedures.
! e. The fire protection equipment and program implementation utilizing j
either a qualified offsite license fire protection engineer or an l outside independent fire protection consultant.
- f. Actions taken to correct deffetencies occurring in equipment,
- structures, systems, components, or method of operation that affect nuclear safety; and i
4 g. Other activitten and documents as requested by the@e;etive i'iQ l q=i:=t - r= =9 j
MILLSTONE - UNIT 3 6-11 AmendmentNo.J1.JJ,71,77,125 4
mas N
l, ADMINISTRATIVE CONTROLS Januar/17,1996 i RECORDS
- 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 l Section 6.5.3; j 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. Detemination 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
! unreviewed safety question as defined in 10 CFR 50.59.
4 6.5.4 Station Dualified Reviewer Prearam i
l Function g,gg<_ gg4 3 g,,y,,7 o% e, ,
l 6.5.4.1 The-Lhr Unit Director ors $NNEb$bt - ;;"luter.e l 54et4en 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 i Reviewers and approved by designated managers. These reviews are in lieu of
) reviews by the PORC or 50RC. However, procedures which require a 10 CFR 50.59
- evaluation must be reviewed by the PORC or 50RC.
i Resoonsibilities
) 6.5.4.2 The Station Qualified Reviewer Program shall:
l 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.
1 i 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 i 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 4 unreviewed safety question does not exist. This screening will be
. performed by personnel trained and qualified in performing
! 10 CFR 50.5g evaluations.
1 i
NILL 5 TONE - UNIT 3 6-12 Amendment No. JJ. JJ 77, 77, JPI' 125 0413
ADNIN!$TRATIVE CONTROL 5 .innnarv 17 inom
- e. Provide fee written recomendation by the Qualified Reviewer (s) to the resporuible 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 50.5g evaluation.
6.5.4.3 If the responsible manager detersines that a new program, procsdure, or change thereto requires a 10 CFR 50.5g evaluation, that Manager will ensure the required evaluation is performed to deterstne 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 50.5g evaluation to p0RC/50RC for review.
m.us w ,_ Aum+3 De Re Ma e oGv u newm.
6.5.4.4 personnel recommended to the Station Qua11 fled Reviewers shall be designated in writing by the4hreleer Unit Director or Milhter.. Ot:ti= for each procedure, program, or class of procedure or program within the scope of the Station Qualified Reviewer Program.
5.5.4.5 Temporary procedure changes shall be made id accordance with Specification 6.6.3 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.
Etsardi 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.
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 j discipline, and two years of nuclear power plant experience; 1 OR
- b. Six years of nuclear power plant experience; OR 1 i
- c. An equivalent combination of education and experience as approved by a Department Manager.
j NILLSTONE - LMIT 3 6 13 Amendment No.125 M23
I l 1 .
April 24,1996 '
l . :
j ADNINISTRATIVE CONTROLS 5
- F j 6.6 rep 0RTABLE EVENT ACTION c i
) 6.6.1 The following actions shall be taken for REPORTABLE EVENTS:
l
- a. The Commission shall be notified and a report ' submitted pursuant j 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 NSA8 and the Pre sE = : P"V, wo La47;;;t t t "- 9 r .
i obe Guo i 6.7 SAFETY LIMIT VIOLATION -
f :
} 6.7.1 The following actions shall be taken in the event a Safety Limit is )
- violated
- '
j a. The Unit shall be placed in at least HOT STAND 8Y within one hour.
i j b. The NRC Operations Center shall be notified by telephone as soon as possible and in all cases within I hour. The Mth: Yie: P<es,A,J, proefdent-Nus3 ear and the Chairperson of the NSAB shall be CEo-a cAlo 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: v (1) applicable circumstances preceding the violation, (2) effects of the violation upon facility components, systems, or structures, and (3) corrective action taken to prevent recurrence; i d. The Safety Limit Violation Report shall be submitted to the i Commission, the Chair erson of the NSAB, and the n;;.: n; Yi:2 Pre.a4
{ Pree4 dent-48ue4eer wittin 14 days of the violation; and a N+ cAjo
! e. Operation shall not be resumed until authorized by the Commiission.
6.8 PRDCEDURES AND PROGRAMS 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 1.33, Revision 2, February 1978; l 3 4
- b. The applicable procedures required to implement the requirements of NUREG-0737 and supplements thereto; ;
i
] c. Refueling operations;
)
i d. Surveillance activities of safety related equipment; .
, e. Not used.
NILLSTONE - LIIIT 3 6-14 Amendment No. #, 77, JM, gy,128 eens
+
A j April 24,1996 l 1 l ADMINISTRATIVE CONTROLS I
. 1 i F i (
l f. Not used.
- g. Fire Protection Program implementation; l h. Quality controls for effluent monitoring, using the guidance in j Regulatory Guide 1.21, Rev.1, June 1974; and i
j 1. Radiological Effluent Monitoring and Offsite Dose Calculation
- Manual (REM 00CM) implementation except for Section I.E, j Radiological Environmental Monitoring.
~
! The 40meleer Unit Director .r or S...fE. . IU7 6.8.2 a. n i .. N.._: .. . - k b h,gi[M"!:t:--
l 46e64en may designate specific procedures and programs, or classes
- of procedures and programs to be reviewed in accordance with the j Station Qualified Reviewer Program in lieu of review by the PORC/
j S0RC. The review per the Qualified Reviewer Program shall be in
- accordance with Specification 6.5.4.
l b. Procedures and programs listed in Specification 6.8.1, and changes
- ube md3Ec".*f. thereto, shall be approved by the Noeleer Unit Director or Senfor.
p('Q ""k V" ;Yice I
7.;;iir.t Directors - Mi.letz: who areOt; designatedtic. or by as the cognizant Approval Authority Manager by theor !
! "xleer Unit Director orAr.:: Ytre P---id;;.t - Mill:tne i l
j } Ste64en, as~specified in administrative procedures. The Approval Authority for each procedure and program or class of procedure and j program shall be specified in administrative procedures.
i c. Each procedure of Specification 6.8.1, and changes thereto, shall .
- be reviewed by the POR0750RC and shall be approved by the Nes4 ear 0^4 l l p,"' Director ori ent
- r Yi n N xtf xt Mill:ter.; Otetin, or be ;
j 4%iy# 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
{ administraive procedures.
l l 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 I ok j c. The change is documented, reviewed by the PORCfS0RC or Station i Qualified Reviewer Program, as appropriate, and approved by the A4 j C-Q StationQualifiedReviewerProgramManagererM
- :leerU..it tirn' r r 50.1:r Yi;; Ezit.t "il.eten Ot:ti- within Cgc ^"-"='s',
j 14 days of implementation. e3 ~^M i :-
j NILLSTONE - LBIIT 3 6-15 Amendment No. # , g , 75, 128 i
- \
4/26/94 !
\
ADMINISTRATIVE CONTROLS 6.13 RADIOLOGICAL I
(REMODCM) EFFLUENT MONITORING AND OFFSITE DOSE CALCULATION .
Section I, Radiological Effluent Monitoring Manual (RDei), shall outline the sampling and analysis programs to determine the concentration of radioactive materials released offsite as well as dose commitments to individuals in t exposure pathways and for those radionuclides released as a result of station operation. It shall also specify operating guidelines for radioactive wn # 2 treatment systems and report content.
l Section II the Offsite Dose Calculation Manual (0DCM , shall describe the i
! methodology, and parameters to be used in the calculation o)f offsite doses d I radioactive gaseous and liquid effluents and in the calculations of gaseous and liquid effluent monitoring instrumentation alarm / trip setpoints consistent with the applicable LCOs contained in these technical specifications. ;
Changes to the REMODCM:
a.
Shall be documented required and 6.10.3o.
by Specification records of reviews perfomed shall be retained as 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 Igo, -
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.
p rova obhe $ P d t Preiebe,L az> a.O uso i ht t$t ;. l c.
, Shall be submitted to the Commission in the form of a complete, legible copy of the entire REMM or ODCM, as appropriate, as a part of or concurrent with the change any Annualwas Radioactive made. Effluent Report for the period of the report in which margin of the affected pages, clearly indicatinEach change shall be identif was changed, and shall indicate the date (e.g.,gmonth implemented.
the area
/ year)of the thechange page that was 6.14 RADIDACTIVE WASTE TREATMENT Procedures for liquid and gaseous radioactive ' effluent discharges from the Unit shall be prepared, approved, maintained and adhered to for all operations involving offsite releases of radioactive effluents. These procedures shall specify ,
i the use of appropriate waste treatment systems utilizing the guidance provided in the REMODCM.
The Solid Radioactive Waste Treatment System shall be operated b accordance with and burial the Process Control Program to process wet radioactive wastes to meet shipping ground requirements.
i -
MILLSTONE - UNIT 3 6-24 Otte- Amendment No. JJ, JJ, JJ 90
l Docket Nos. 50-213 '
50-245 50-336 l 50-423 l B16046 j i
)
i I
1 Attachment 2 l I
Millstone Nuclear Power Station, Unit Nos.1,2, and 3 l Proposed Revision to Technical Specifications Administrative Controls Retyped Pages December 1996 I
r 6.0 ADMINISTRATIVE CONTROLS !
6.1 RESPONSIBILITY :
- i. ,
6.1.1 The Executive Vice President and Chief Nuclear Officer shall be responsible for overall facility operation and shall delegate, in writing, the l succession to this responsibility during his absence. l l 6.2 ORGANIZATION ,
6.2.1 ONSITE AND OFFSITE ORGANIZATIONS j Onsite and offsite organizations shall be established for unit operation and !
4-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 'l 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, l as appropriate, in the form of organization charts, functional descriptions of departmental responsibilities and relationships, i' and job descriptions for key personnel positions, or in equivalent forms of documentation. These requirements shall be documented in i the Quality Assurance Topical Report. l
- b. The Unit Director shall be responsible for overall unit safe l l operation and shall have control over those onsite activities necessary for safe operation and maintenance of the plant.
- c. The Executive Vice President and Chief Nuclear Officer, shall have corporate responsibility for overall plant nuclear safety and shall l take any measures needed to ensure acceptable performance of the staff in operating, maintaining, and providing technical support to the plant to ensure nuclear safety.
- d. The individuals who train the operating staff and those who carry out health physics and quality assurance functions may report to the appropriate onsite manager; however, they shall have sufficient organizational 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 i fuel is in the reactor. In addition, while the facility is in !
MODE 1, 2, 3 or 4, at least one licensed Senior Operator shall be in the control room; i
HADDAN NECK 6-1 Amendment No. J77. JJJ, 177, 0410
- ADMINISTRATIVE CONTROLS 1
d
- f. Successful completion of the Thames Valley State Technical College associate's degree in Nuclear Engineering Technology program, provided that the individual was enrolled in the
) program by October 1, 1987. i j 2. Dedicated STA: Must meet the STA training criteria of NUREG-0737,
! Item I.A.I.1, and have received specific training in plant design,
- and response and analysis of the plant for transients and accidents.
- 6.4 TRAINING
- A retraining and replacement training program for the facility staff shall be maintained under the direction of the Nuclear Unit Director and shall meet or i exceed the requirements and recommendations of Section 5.5 of ANSI N18.1-1971 i and 10CFR55.59. .The Director-Nuclear Training has the overall responsibility j for the implementation of the Training Program.
! 6.5 REVIEW AND AUDIT 6.5.1 PLANT OPERATIONS REVIEW COMITTEE (PORC) i
! i FUNCTION 1 i
! 6.5.1.1 The PORC shall function to advise the Unit Director on all matters l !
j related to nuclear safety. ,
1 l COMPOSITION j 4 .
! 6.5.1.2 The PORC shall be composed of at least eleven members. Members
- shall collectively have experience and expertise in the following areas
! Plant Operations l Engineering l Reactor Engineering i Mechanical Maintenance Electrical Maintenance
! Instrumentation and Controls
- Health Physics j Work Planning and Control L Quality Services
! Security i Chemistry i
- The minimum qualifications of PORC members shall be that all members have an 2
academic degree in an engineering or physical science field, or hold a management position, and have a minimum of five years technical experience in 3
their respective field of expertise. The members of PORC shall be appointed i in writing by the Unit Director, who is the PORC Chairperson. The alternate 1 Chairpersons of the PORC shall be drawn from the PORC members and be appoin
- in writing by the Unit Director. l j HADOAM NECK 6-5 Amendment No. J7).J77.JJJ.Jpp, j om 119,199,
. ADMINISTRATIVE CONTROLS t
j ALTERNATES l 6.5.1.3 All alternate members shall be appointed in writing by the PORC i Chairperson to serve on a temporary basis; however, no more than two
) alternates shall participate as voting members in PORC activities at any one l time.
i MEETING FREQUENCY i 6.5.1.4 The PORC shall meet at least once per calendar month and as convened by the PORC Chairperson or his/her designated alternate.
AUQlE 6.5.1.5 The quorum of the PORC shall consist of the Chairperson or his/her designated alternate and four members including alternates.
RESPONSIBILITIES 1
6.5.1.6 The PORC shall be responsible for:
- a. Review of: (1) all procedures required by Specification 6.8 and changes thereto, and 2) any other proposed procedures or changes i theretoasdeterminedbytheUnitDirectortoaffectnuclearsafety;l l
- b. Review of all proposed tests and experiments that affect nuclear safety;
- c. Review of all proposed changes to the Technical Specifications;
- d. Review of all proposed changes or modifications to plant system or equipment that affect nuclear safety;
- a. Investigation of all violations of the Technical Specifications, including the preparation and forwarding of reports covering evaluation and recommendations to prevent recurrence, to the Executive Vice President and Chief Nuclear Officer 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, investigations or analyses and reports thereon as requested by the Chairperson of the Nuclear Safety Assessment Board or the Unit Director.
MADDAN NECK 6-6 Amendment No. JJJ JJJ, JJJ Idi
ADNINISTRATIVE CONTROLS
- 1. Not used.
J. Not used.
- k. Review of the Fire Protection Program and Implementing Procedures.
AUTHORITY 6.5.1.7 The PORC shall:
- a. Report to and be advisory to the Unit Director on those areas of l responsibility specified in Section 6.5.1.6(a) through (k);
- b. RenderdeterminationsinwritingtotheUnitDirectorifanyiteml considered under Specification 6.5.1.6a. through d., above, as appropriate and as provided by 10CFR50.59 or 10CFR50.92 constitutes an unreviewed safety ouestion or requires a significant hazards consideration determinasion.
- c. Provide written notification, meeting minutes may be used for this purpose, to the Executive Vice President and Chief Nuclear Officer and the Chairperson of the Nuclear Safety Assessment Board of !
disagreement between the PORC and the Unit Director; however, the Executive Vice President and Chief Nuclear Officer shall have responsibility for resolution of such disagreements pursuant to Specification 6.1.1.
RECORDS 6.5.1.8 The PORC shall maintain written minutes of each meeting that, at a minimum, document the results of all PORC activities performed under the responsibility and authority provisions of these Technical Specifications.
A Copy shall be provided to the Chairperson of the Nuclear Safety Assessment Board.
6.5.2 NUCLEAR SAFETY ASSESSMENT BOARD (NSAB)
FUNCTION 6.5.2.1 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.
HADOAN NECK 6-7 Amendment No. JJJ. J)J JJf. 177.
0411 19Je 199
ADNINISTRATIVE CONTROLS ;
- 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-
- 7. Mechanical and electrical engineering; and
- 8. Quality assurance practices. !
1 The NSAB serves to advise the President and Chief Executive Officer on matters related to nuclear safety and notify the President and Chief Executive Officer l 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.
COMPOSITION 6.5.2.2 The President and Chief Executive Officer shall appoint, in writing, a minimum of seven members to the NSAB and shall designate from this member in writing, a Chairperson and a Vice Chairperson. The membership shall function to provide independent review and audit in the areas listed in Specification 6.5.2.1.
ALTERNATES 6.5.2.3 All alternate members shall be appointed, in writing, by the President and Chief Executive Officer; however, no more than two alternates shall participate as members in NSAB activities at any one time.
MEETING FREQUENCY 6.5.2.4 The NSAB shall meet at least once per calendar quarter.
OV0 RUM 6.5.2.5 The quorum of the NSAB shall consist of a majority of NSAB members l including the Chairperson or Vice Chairperson. No more than a minority of the i quorum shall have line responsibility for operation of the same Northeast l Utilities' nuclear unit. No more than two alternates shall be appointed as '
members at any meeting in fulfillment of the quorum requirements. j l
HADDAN NECK 6-8 Amendment No. J/J, JJJ, JJJ, JJ/, 4 0411 1
ADNINISTRATIVE CONTROLS REVIEW RESPONSIBILITIES 6.5.2.6 The NSA8 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 i 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 i License; i
- e. Violations of applicable codes, regulations, orders, license requirements, or internal proce: lures having nuclear safety significance;
- f. All Licensee Event Reports required by 10 CFR 50.73;
- g. Indications of significant unanticipated defi::iencies in any aspect of design or operation of structures, systems, or components that could affect nuclear safety; 1
- 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 Chief Executive Officer within 30 days following completion of the review.
AUDIT PROGRAM RESPONSIBILITIES 6.5.2.7 The NSAB audit program shall be the responsibility of Nuclear Oversight organization. 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 applied.e license conditions; HADOAN NECK 6-9 Amendment No. JJ), J)J Jpf, 0411
ADMINISTRATIVE CONTROL 5
- b. The training and qualifications of the unit staff;
- c. The implacentation 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 Chief Executive Officer.
RECORDS 6.5.2.8 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 6.5.2;
- 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. )
6.6 REF94 TABLE EVENT ACTION l 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 NSA8 and the Executive Vice President and Chief Nuclear Officer. l i
6.7 SAFETY LIMIT VIOLATION !
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.
l I
HADOAN NECK 6-10 Amendment No. JJJ. J)J. J71. I 0411
1 I i
i ADNIWISTRATIVE CONTROLS I 2
- l
- b. The NRC Operations Center shall be notified by telephone as soon as !
- possible and in all cases within I hour. The Executive Vice !
President and Chief Nuclear Officer and the Chairperson of the NSAB !
i 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 pre >ared. The report shall '
j be reviewed by the PORC. This report shall oescribe: (1) applicable ,
- circumstances preceding the violation, (2) effects of the violation l 3 upon facility components, systems, or structures, and (3) corrective 1 action taken to prevent recurrence- '
I l d. The Safety Limit Violation Report shall be suhaitted to the i
- Commission, the Chairperson of the NSAB and the Executive Vice l President and Chief Nuclear Officer within 14 days of the violation;
] e. Operation will not be resumed until authorized by the Commission. l 1
J 6.8 PROCEDURES AND PROGRAMS I 6.8.1 Written procedures and/or administrative policies shall be established, implemented, and maintained covering the activities referenced below:
1 I
i i
i I
i 1
i 1
1 i
i l
i i
+
t i
i i
j HADDAN NECK 6-11 Amendment No. 17), 17), Jpf,
- wii i
I l ADMINISTRATIVE CONTROLS
{ a. The applicable procedures recommended in Appendix A of Regulatory Guide 1.33, Revision 2, February 1978;
- b. The requirements and recommendations of Sections 5.1 and 5.3 of ANSI N 18.7-1976.
- c. Fire Protection Program implementation.
[ d. Quality controls for effluent monitoring, using the guidance in Regulatory Guide 1.21 Rev.1, June 1974.
- e. RADIOLOGICAL EFFLUENT MONITORING AND OFFSITE DOSE CALCULATION MANUAL
! (REMODCM) implementation except for Section I.E, Radiological l Environmental Monitoring.
- f. PROCESS CONTROL PROGRAM implementation.
6.8.2 Each procedure of Specification 6.8.1, and changes thereto, shall be reviewed by the PORC and shall be approved by the Unit Director prior to l implementation and reviewed periodically as set forth in each document or in j 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; 1
- 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 and approved by the ,
Unit Director within 14 days of implementation. l l 6.8.4 Written procedures shall be established, implemented and maintained i covering Section I.E., Radiological Environmental Monitoring, of the REMODCN.
6.8.5 All procedures and procedure changes required for the Radiological I Environmental Monitoring Program of Specification 6.8.4 above shall be ,
reviewed by an individual (other than the author) from the Radiological !
Assessment Branch or the Production Operation Services Laboratory (POSL) and l approved by appropriate supervision.
Temporary changes may be made provided the intent of the original procedure is not altered and the change is documented and reviewed by an individual (other !
than the author) from the Radiological Assessment Branch or the POSL, within 14 days of implementation.
,HADDAN NECK 6-12 Amendment No. J77. Jpp, Jpp,
- .-. .. . - - - - . ,.- - . ~ .- .
- ADMINISTRATIVE CONTROLS I
6.13 RADIOLOGICAL EFFLUENT MONITORING AND OFFSITE DOSE CALCULATION MANUAL (REMODCM)
Section I, P;diological Effluents Monitoring Manual, shall outline the j sampling and analysis programs to determine the concentration of radioactive i materials released offsite as well as dose commitments to individuals in '
those exposure pathways and for those radionuclides released as a result of facility operation. It shall also specify operating guidelines for RADI0 ACTIVE WASTE TREATMENT SYSTEMS and report content.
Section II, the Offsite Dose Calculation Manual, 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 Alarm / Trip Setpoints consistent with the applicable LCO'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 6.10.3.m. This documentation shall l i
contain: j
- 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 10CFR 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 PORC and the approval of the Unit Director. l
- c. Shall be submitted to the Commission 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.
6.14 RADIOACTIVE WASTE TREATMENT Procedures for liquid and gaseous radioactive effluent discharges from the i facility shall be prepared, approved, maintained and adhered to for all i operations involving offsite releases of radioactive effluents. These procedures shall specify the use of appropriate RADI0 ACTIVE WASTE TREATMENT SYSTEMS utilizing the guidance provided in the REM 0DCM.
HADDAM NECK 6-20 Amendment No. JJJ. JJJ, JJJ, 1 0411 177.
l i
ADMINISTRATIVE CONTROLS 1
i 6.1 RESPONSIBILITY !
i 6.1.1 The President, Chief Executive Officer (CEO) and Chief Nuclear Officer l 1 (CNO) shall be responsible for overall operation of the Millstone Station Site
' whiie the Director, Unit Operations shall be responsible for operation of the i
unit. The President, CEO and CN0 and Director, Unit Operations shall each delegate, in writing, the succession to these responsibilities during their i
- absence. 1 i
6.2 ORGANIZATION !
6.2.1 OfFSITE AND ONSITE ORGANIZATIONS
. 1 i
Onsite and ofhite organizations shall be established for unit operation and {
- corporate mant.;tment, respectively. The onsite and offsite organizations '
- shall include the positions for activities affecting the safety of the nuclear
! ,oower plant.
1
- 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 fom 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 l
j Quality Assurance Topical Report. i l
l b. The Millstone Unit 1 Recovery Officer shall be responsible for 4
overall unit safe operation and shall have control over those onsite l
+
activities necessary for safe operation and maintenance of the plant.
j c. The President, CEO and CNO shall have corporate responsibility for l i overall plant nuclear safety and shall take any measures needed to
! ensure acceptable performance of the staff in operating, l
! maintaining, and providing technical support to the plant to ensur<,
j nuclear safety.
j d. The individuals who train the operating staff and those who carry l out health physics and quality assurance functions may report to the 1
appropriate onsite manager; however, they shall have sufficient j organizational freedom to ensure their independence from operating i pressures.
i
- 6.2.2 FACILITY SJAEE i
f 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. # , M. M.
0266
4 i
ADNINISTRATIVE CONTROLS 6.4 TRAINING 4
6.4.1 A retraining and replacement training program for the facility staff shall be maintained under the direction of the Millstone Unit 1 i Recovery Officer and shall meet or exceed the requirements and recommendations of Section 5.5 of ANSI N18.1-1971 and 10 CFR Part 1.
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) i Function 6.5.1.1 The PORC shall function to advise the Director, Unit Operations on l j all matters related to nuclear safety.
Composition i 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 Chemistry
- Work Planning ,
Quality Assurance '
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 management position, and have a mit.imum 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 i 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.
N111 stone Unit 1 6-5 Amendment No. JJ. JJ, 7J. JJ.
0257
l l
ADMINISTRATIVE CONTROLS
- 1 Neating Frequency I 6.5.1.4 The PORC shall meet at least once per calendar month and as convened by ,
the PORC Chairperson.
Quorum 6.5.1.5 A quorum of the PORC shall consist of the Chairperson, or Vice l Chairperson, and four members including alternates. [ ]
Responsibilities l t
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, r6 quired 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.
l
- 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 President, CEO and CN0 and Millstone Unit 1 Recovery Officer to the Chairperson of the Neclear 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 investigai. ions 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. J. M , 7(, 77, 71, 0257 l
l
{ ADMINISTRATIVE CONTROL 5 i
1
- j. Review of the unit-specific Fire Protection Program and implementing procedures.
l Authority
! 6.5.1.7 The PORC shall:
i i a. Recommend to the Director, Unit Operations written approtal or
, disapproval of items considered under 6.5.1.6(a) through (d) 4 above.
l b. Provide immediate written notification to the Millstone Unit 1 1
Recovery Officer and the Chairperson of the Nuclear Safety Assessment Board of disagreement between the PORC and i the Director, Unit Operations; however, the Director, Unit j Operations shall have responsibility for resolution of such i 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 Director, Unit Operations, Millstone Unit 1 l Recovery Officer and Chairperson of the Nuclear Safety Assessment Board.
6.5.2 Site Ooerations Review C - ittee (SORC)
Function 6.5.2.1 The SORC shall function to advise the President, CEO and CN0 on all matters related to nuclear safety of the entire Millstone Station Site.
6.5.2.2 The 50RC shall be composed of the:
Chairperson: Nuclear Engineering and Support Recovery Officer Member: Director, Unit Operations Member: Unit 2 Director Member: Unit 3 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.
Alternates 6.5.2.3 Alternate members shall be appointed in writing by the SORC Chairperson to serve on a temporary basis; however, ao more than two alternates shall participate in SORC activities at one time.
Millstone Unit 1 6-7 Amendment No. pp. 77, 77 77, 77, 0267
ADMINISTRATIVE CONTROLS Meetina Freauency i 6.5.2.4 The SORC shall meet at least once per six months and as convened by the SORC Chairperson.
- Ouorum i '
{ 6.5.2.5 A quorum of the SORC shall consist of the Chairperson or Vice l Chairperson and five monkrs including alternates.
Responsibilities j 6.5.2.6 The SORC shall be responsible for:
i a. Review of 1) all common site procedures required by Specification 6.8 and changes thereto, 2) all common site programs, required by i Specification 6.8 and changes thereto, 3) any other proposed l procedures, programs, or changes thereto as determined by the President, CEO and CN0 to affect site nuclear safety. Commonsitel
! programs and procedures required by Specification 6.8 that are i designated for review and approval by the Station Qualified Review j Program do not require SORC review.
j b. Review of all proposed changes to Section 6.0, " Administrative 4
Controls", of these Technical Specifications.
I c. Performance of special reviews and investigations and reports as requested by the Chairperson of the Nuclear Safety Assessment Board,
- d. Not used.
- e. Not used.
- f. Review of all common site proposed tests and experiments that affect nuclear safety. j
- g. Review of all common site proposed changes or modifications to l 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 ;
as provided by 10CFR50.59 or 10CFR50.92, constitutes an unreviewed !
safety question or requires a significant hazards consideration determination.
- 1. Review of the common site Fire Protection Program and implementing procedures.
l N111 stone Unit 1 6-8 Amendment No. pp. 7J 77, 71, 77, 0257
.. . . -. . - - . - . - - . . . . - - - - ~ . - . . - . .
l ADMINISTRATIVE CONTROLS l
i Authority 6.5.2.7 The 50RC shall:
I a. Recommend to the President, CEO and CN0 written approval or l
- disapproval, in meeting minutes, of items considered under j 6.5.2.6(a) through (g) above. ;
j b. Provide immediate written notification, or meeting minutes, to the l
! Chairperson of the Nuclear Safety Assessment Board of disagreement between the SORC and the President, CEO and CN0; however, the !
! President, CEO and CN0 shall have responsibility for resolution of i
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 President, CEO and CN0 and Chairperson of the j Nuclear Safety Assessment Board.
l 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 NSA8 shall have experience in and shall function to provide independent oversight review and audit of designated activities in l the areas of:
- 1. Nuclear power plant operations; ;
- 2. Nuclear engineering;
- 3. Chemistry and radiochemistry;
- 4. Metallurgy;
- 5. Instrumentation and control;
- 6. Radiological safety; N111 stone Unit 1 6-9 Amendment No. JJ, JJ, JJ, 7J 77, U ,
0257
! ADMINISTRATIVE CONTROLS t
- 7. Mechanical and electrical engineering; and
- 8. Quality assurance practices.
- The NSA8 serves to advise the President, CEO and CN0 on matters related
- to nuclear safety and notify the President, CEO and CN0 within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> i of a safety significant disagreement between the NSAB and the j organization or function being reviewed.
COMPOSITION l
j 6.5.3.2 The President, CEO and CN0 shall appoint, in writing, a minimum of 3 l seven members to the NSA8 and shall designate from this membership, in writing, a Chairperson and a Vice Chairperson. The membership shall l function to provide independent review and audit in the areas listed in l Specification 6.5.3.1.
i j ALTERNATES
! 6.5.3.3 All alternate members shall be appointed, in writing, by the President, i CEO and CN0; however, no more than two alternates shall participate as
{ members in NSAB activities at any one time.
i NEETING FREQUENCY j 6.5.3.4 The NSA8 shall meet at least once per calendar quarter.
000 RUM i
! 6.5.3.5 The quorum of the NSA8 shall consist of a majority of NSAB members j including the Chairperson or Vice Chairperson. No more than a minority l of the quorum shall have line responsibility for operation of the same
! Northeast Utilities' nuclear unit. No more than two alternates shall j be appointed as members at any meeting in fulfillment of the quorum l requirements.
REVIEW RESPONSIBILITIES 6.5.3.6 The NSA8 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; N111 stone Unit 1 6-10 Amendment No. U , M. U , M ,
0257
I ADNINISTRATIVE CONTROLS
- d. Proposed changes to Technical Specifications and the Operating l 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; i
- g. Indications of significant unanticipated deficiencies in any
- aspect of design or operation of structures, systems, or s
components that could affect nuclear safety; i
- h. Significant accidental, unplanned, or uncontrolled radioactive a releases, including corrective actions to prevent recurrence; i 1 1. Significant operating abnormalities or deviations from normal and i expected performance of equipment that could affect nuclear
! safety;
- j. The perfonsance of the corrective action program; and I k. Audits and audit plans.
j Reports or records of these reviews shall be forwarded to the 2
President, CEO and CN0 within 30 days following completion of the
- review.
l AUDIT PROGRAM RESPONSIBILITIES 4 6.5.3.7 The NSAB audit program shall be the responsibility of the Nuclear Oversight organization. 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; i
- c. The implementation of all programs required by specification 6.8; l
- 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.
j f. Actions taken to correct deficie..cies occurring in equipment, i structures, systems, components, or method of operation that j affect nuclear safety; and N111 stone Unit 1 6-11 Amendment No. J, pp. 77, Pf, 0257 l
l
ADMINISTRATIVE CONTROLS l g. Other activities and documents as requested by the President, CEO and CNO.
l
] RECORDS 6.5.3.8 Written records of reviews and audits sLol be maintained. As a
- minimum these records shall include
i
- a. Results of the activities conducted under the provisions of Section 6.5.3; I 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 50.59.
i 6.5.4 Station Qualified Reviewer Proaram !
Function 6.5.4.1 The Director, Unit Operations or Millstone Unit 1 Recovery Officer or l Executive Vice President 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.
1 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 aersons designated by cognizant managers or directors as laying 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 Millstone Unit 1 6-12 Amendment No. # , 77, 77, 0257
- g. ._ _ _ - _ _ _ _ _ _ _ _ _ - _ _ . . . . _ . _ _ _ _ . - -_.__.__-_.__._._.m_
! ADMINISTRATIVE CONTROLS in accordance with the provisions of 10CFR50.59 to verify that an
- unreviewed safety question does not exist. This screening will be j performed by personnel trained and qualified in performing ;
10CFR50.59 evaluations. '
i
! e. Provide for written recommendation by the Qualified Reviewer (s) to i
1 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, i ,
l 6.5.4.3 If the responsible manager determines that a new program, procedure, or i change thereto requires a 10CFR50.59 evaluation, that manager will l ensure the required evaluation is performed to determine if the new ,
1 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/SORC for review.
I !
{ 6.5.4.4 Personnel recommended to the Station Qualified Reviewers shall be designated in writing by the Director, Unit Operations or Millstone i Unit 1. Recovery Officer or Executive Vice President for each procedure, i program, or class of procedure or program within the scope of the i Station Qualified Reviewer Program.
i 6.5.4.5 Temporary procedure changes shall be made in accordance with j Specification 6.8.3 with the exception that changes to procedures for
- which reviews are assigned to Qualified Reviewers will be reviewed and i 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 j administrative procedures.
2 l Trainina and Qualification j 6.5.4.7 The training and qualification requirements of personnel designated as a Qualified Reviewer in accordance with the Station Qualified Reviewer 3
i Program shall be in accordance with administrative procedures.
j Qualified reviewers shall have:
1
! a. A Bachelors degree in engineering, related science, or technical i discipline, and two years of nuclear power plant experience; j OR i-i b. Six years of nuclear power plant experience; i
OR i
j c. An equivalent combination of education and experience as approved j by a department manager.
i t Millstone Unit 1 6-13 Amendment No. 71, d 0267 1
l" ADMINISTRATIVE CONTROLS 6.6 REPORTABLE EVENT ACTION i
j 6.6.1 The following actions shall be taken for REPORTABLE EVENTS:
I a. The Commission shall be notified and a report submitted j pursuant to the requirement of 10 CFR 50.73. '
i i b. Each REPORTABLE EVENT shall be reviewed by the PORC and the
, results of this review shall be submitted to the Chairperson of
l i ,
j 6.7 SAFETY LIMIT VIOLATION l 1 '
! 6.7.1 The following actions shall be taken in the event a Safety Limit is ;
j violated: i l a. The unit shall be placed in at least HOT STAND 8Y within two hours.
!c b. The NRC Operations Center shall be notified by telephone as I 1 soon as possible and in all cases within one hour. The President, '
l CEO and CN0 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 />. 1 i 1 i c. A Safety Limit Violation Report shall be prepared. The report I i shall be reviewed by the PORC. This report shall describe j (1) applicable circumstances preceding the violation, (2) effects i 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
- Commission, the Chairperson of the NSAB and the President, CEO and i CN0 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 1.33, February,1978.
- b. Refueling operations.
- c. Surveillance activities of safety related equipment.
- d. Not used.
- e. Not used.
- f. Fire Protection Pronram Implementation.
Millstone Unit 1 6-14 Amendment No. J. M U , N , M.
0257
_ _. . . . - _ _ . _ . . _ . ~ __ _ _
- ADMINISTRATIVE CONTROLS
- g. Quality Control for effluent monitoring using the guidance in Regulatory Guide 1.21 Rev.1, June 1974.
- h. Radiological Effluent Monitoring and Offsite Dose Calculation Manual (REM 0DCM) implementation, except for Section I.E., Radiological j Environmental Monitoring.
- 6.8.2 a. The Director, Unit Operations or Millstone Unit 1 Recovery Officer l
- or Executive Vice President may designate specific arocedures and
, programs, or classes of procedures and programs to >e reviewed in i
- accordance with the Station Qualified Reviewer Program in lieu of i 4
review by the PORC/SORC. The review per the Qualified Reviewer j 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 Director, Unit Operations or l l Millstone Unit 1 Recovery Officer or Executive Vice President or by cognizant Manager or Directors who are designated as the Approval Authority by the Director, Unit Operations or Millstone Unit 1 I Recovery Officer or Executive Vice President, as specified in 4
administrative procedures. The Approval Authority for each procedure and program or class of procedure and program shall be specified in j administrative procedures. l
- c. Each procedure of Specification 6.8.1, and changes thereto, shall be l reviewed by the PORC or SORC and shall be approved by the Director, i Unit Operations or President, CEO and CNO, or be reviewed and approved in accordance with the Station Qualified Reviewer Program, prior to implementation. Each procedure of Specification 6.8.1 shall l be reviewed periodically as set forth in administrative procedures.
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, i at least one of whom holds a Senior Reactor Operator's License on the unit affected.
- c. The change is documented, reviewed by the PORC or SORC, or the Station Qualified Reviewer Program, as applicable, and approved by i the Director, Unit Operations, President, CEO and CN0 or Station Qulaified Reviewer Program Manager, within 14 days of implementation.
4 6.8.4 Written procedures shall be established, implemented and maintained 4 covering Section I.E, Radiological Environmental Monitoring, of the REMODCM.
I Millstone Unit 1 6-15 Amendment No. pp 7J, 77 0267 4
i
! ADMINISTRATIVE CONTROLS i
1 6.15 RADIOLOGICAL EFFLUENT MONITORING AND OFFSITE DOSE CALCULATION MANUAL (REM 00CM) i Section I, Radiological Effluents Monitoring Manual (REM), shall outline the j sampling and analysis programs to determine the concentration of radioactive materials released offsite as well as dose commitments to individuals in those j 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.
l Section II, the Offsite Dose Calculation Manual
- methodology and parameters to be used in the calcul(ation of offsite doses due00CM), sh i to radioactive gaseous and liquid effluents and in the calculations of gaseous j and liquid effluent monitoring instrumentation alars/ trip setpoints consistent j with the applicable LCO's contained in these technical specifications.
Changes to the REMODCM:
1 i a. Shall be documented and records of reviews perfore) shall be retained i as required by Specification 6.10.2.m. This documentation shall i contain:
4 l- 1) Sufficient information to support the change together with the i appropriate analyses or evaluations justifying the change (s),
j ad 1
l 2) A determination that the change will maintain the level of i 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, j or setpoint calculations.
I
- b. Shall become effective after review and acceptance by SORC and the approval of the President, CEO and CNO. l
- c. Shall be submitted to the Commission in the form of a complete, legible l copy of the entire REM or 00CM, as appropriate, as a part of or concurrent with tF.e 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.
l Nillstone Unit 1 6-23 Amendment No. 5 , pp, pp. 77, 0268
i
[ ADNINISTRATIVE CONTROLS 6.1 RESPOE IBILITY !
6.1.1 The President, Chief Executive Officer (CEO) and Chief Nuclear ;
Officer (CNO) shall be responsible for overall operation of the Millstone i Station Site while the Unit Director shall be responsible for operation of the unit. The President, CEO and CN0 and Unit Director shall each delegate in !
writing the succession to these responsibilities during their absence. l 6.2 ORGANIZATION 6.2.1 0FFSITE AIE) ONSITE ORGANIZATIONS Onsite and offsite organizations shall be established for unit operation and i corporate management, respectively. The onsite and offsite organizations shall include the positions for activities affecting the safety of the nuclear l power plant.
i
- 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 :
positions. These relationships shal be documented and updated, as !
appropriate, in the form of o m anization charts, functional descrip-
! tions of departmental responsibilities and relationships, and job i descriptions for key personnel positions, or in equivalent forms of '
documentation. These requirements shall be documented in the ;
- Quality Assurance Topical Report. i l b. The Millstone Unit 2 Recovery Officer shall be responsible for l l overall unit safe operation and shall have control over those onsite
4 activities necessary for safe operation and maintenance of the !
plant.. t
- c. The President, CEO and CN0 shall have corporate responsibility for l overall plant nuclear safety and shall take any measures needed to ensure acceptable performance of the staff in operating, l maintaining, and providing technical support to the plant to ensure nuclear safety. j
- d. The individuals who train the operating staff and those who carry ,
out health physics and quality assurance functions may report to the appropriate onsite manager; however, they shall have sufficient !
organizational freedom to ensure their independence from operating pressures. .
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. i
- 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. (7, M , 77, 71, un N 1% , 1M , 1H 1H 179,
- ADMINISTRATIVE CONTROLS i
- 6.4 TRAINING !
A retraining and replacement training program for the facility staff shall be
, maintained under the direction of the Millstone Unit 2 Recovery Officer and l 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 j overall responsibility for the implementation of the Training Program.
6.5 REVIEW AND AUDIT 6.5.1 Plant Onorations Review C-ittee (PORC)
] Function
- 6.5.1.1 The PORC shall function to advise the Unit Director on all matters 2
related to nuclear safety. l Composition
- 6.5.1.2 The PORC shall be composed of nine to eleven members. Members shall j
collectively have experience and expertise in the following areas: ;
i Plant Operations
{ Engineering i
i Reactor Engineering Maintenance i Instrumentation and Controls >
Health Physics
- 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, i
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 Unit Director. j
. The Chairperson and alternate Chairperson of the PORC shall be drawn i from the PORC members and be appointed in writing by the Unit ]
l Director.
1 i
Alternates
- 6.5.1.3 Alternate members shall be appointed in writing by the PORC i Chairperson to serve on a temporary basis; however, no more than two
- alternates shall participate in PORC activities at any one time. .
1 l
l
, Millstone Unit 2 6-5 Amendment No. JpJ. J7J J7J.
0278 [%%,
.-. - . - - - . . - - - . . ~ . - . _ - - . - . - - - - - - . - - ~ - -
- ADMINISTRATIVE CONTROLS I i ___
- Meeting Frequency 9
i 6.5.1.4 The PORC shall meet at least once per calendar month and as convened
! by the PORC Chairperson.
Quorum 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 i 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 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 President, CEO and CN0 the Millstone Unit 2 Recovery Officer 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 l 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. '
- j. Review of the fire protection program and implementing procedure.
Millstone unit 2 6-6 Amendment No. 17. H. H ,
un H 111, in.1H, In. Hi,1H,
i -
! ADNINISTRATIVE CONTROLS I Authority ;
j 6.5.1.7 The PORC shelb l
! a. Recommer.J to the Unit Director written approval or disapproval l l l of items considered under 6.5.1.6(a) through (d) above. ,
I b. Provide immediate written notification to the Millstone Unit 2 '
4 Recovery Officer and the Chairperson of the Nuclear Safety i Assessment Board of disagreement between the PORC and the Unit
- Director; however, the Unit Director shall have responsibility l for resolution of such disagreements pursuant to 6.1.1 above.
i Records
! 6.5.1.8 The PORC shall maintain written minutes of each meeting and copies
! shall be provided to the Unit Director and the Millstone Unit 2
- Recovery Officer, and Chairperson of the Nuclear Safety Assessment
! Board.
l j 6.5.2 Site coerations Review C---ittee (SORC) l Function i
e 6.5.2.1 The SORC shall function to advise the President, CEO and CN0 on all l matters related to nuclear safety of the entire Millstone Station Site.
j Composition 6.5.2.2 The SORC shall be composed of the:
4 l Chairperson: Nuclear Engineering and Support Recovery Officer i Member: Director, Unit Operations l Member: Unit 2 Director
- Member
- Unit 3 Director j Member: Director, Nuclear Services
- Member: Manager, General Services
{ Member: Designated Member of Unit 1 PORC
, Member: Designated Member of Unit 2 PORC j Member: Designated Member of Unit 3 PORC i Member: Designated Member of Nuclear Oversight I
, The senior Unit Director / Director, Unit Operations in attendance shall be the Vice-Chairperson.
l Alternates:
1 i 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, i
i Millstone Unit 2 6-7 Amendment No. J M , JM , J M ,
J FM,
. 1 i !
ADMINISTRATIVE CONTROLS Meetina Freauency 1
- 6.5.2.4 The SORC shall meet at least once per six months and as convened by !
i the SORC Chairperson.
Ouorum i 6.5.2.5 A quorum of the SORC shall consist of the Chairperson or Vice j
- Chairperson and five members including alternates.
Responsibilities l 6.5.2.6 The SORC shall be responsible for: ,
i i
- a. Review of 1) all common site procedures required by Specifi-
, 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 i by the President, CEO and CN0 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 Reviewer Program do no require SORC
. review.
- b. Review of all proposed changes to Section 6.0 " Administrative i Controls" of tiese Technical Specifications,
- c. Performance of special reviews and investigations and reports ,
as requested by the Chairperson of the Nuc1 car Safety i
]
Assessment Boa'd.
4
- d. Not used. 1
- e. Not used.
- 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 l j systems or equipment that affect nuclear safety. i
- h. Render determinations in writing or meeting minutes if any item 2
considered under 6.5.2.6(a) through (g) above, as appropriate and as provided by 10CFR50.59 or 10CFR50.92, constitutes an unreviewed safety question or requires a significant hazards consideration determination.
- 1. Review of the common site fire protection program and l implementing procedures.
- 1 l
1 Millstone Unit 2 6-8 Amendment No. [p. JJ, [J[, [7J, 0275 [ff,[f[,[ff,[ff, 1
ADMINISTRATIVE CONTROLS Authority 6.5.2.7 The SORC shall:
1
- a. Recommend to the President, CEO and CN0 written approval or-i 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, CEO and CN0 and the Chairperson of the Nuclear l Safety Assessment Board of disagreement between the 50RC and i
the President, CEO and CN0 however, the President, CEO and CN0 l shall have responsibility for resolution of such disagreements pursuant to 6.1.1 above, f
j Records 4
l 6.5.2.8 The 50RC shall maintain written minutes of each meeting and copies j shall be provided to the President, CEO and CN0 and Chairperson of
- the Nuclear Safety Assessment Board.
i
- 6.5.3 NUCLEAR SAFETY ASSESSMENT BOARD (NSAB) i FUNCTION i
6.5.3.1 The minimum qualifications of NSAB members are as follows:
j a. The Chairperson and NSA8 members shall have:
- 1. An academic degree in an engineering or physical science 4 field, or hold a senior management position, and i 2. A minimum of five years technical experience in their l I respective field of expertise.
- b. The NSAB shall have experience in and shall function to provide j independent oversight review and audit of designated activities
- in the areas of
j 1. Nuclear power plant operations; i
- 2. Nuclear engineering;
- 3. Chemistry and radiochemistry;
! 4. Metallurgy; !
- 5. Instrumentation and control; l
1 l
- 6. Radiological safety; ;
I
- 7. Mechanical and electrical engineering; and 4
i 8. Quality assurance practices, i
1 :
- "=" Millstone Unit 2 6-9 Amendment Nos. 19, 99, 79, om 91,119,191, ;
) lif,199,191, i
1 ADNINISTRATIVE COMR0L5 i The NSAB serves to advise the President, CEO and CNO on matters :
i related to nuclear safety and notify the President, CEO and CN0 i 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 disagressent between the ,
j NSA8 and the organization or function being reviewed. ,
COMPOSITION i ,
l 6.5.3.2 The President, CEO and CN0 shall appoint, in writing, a minimum of l
! seven members to the NSA8 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 j listed in Specification 6.5.3.1. j
! ALTERNATES l
- 6.5.3.3 All alternate members shall be appointed, in writing, by the l President, CEO and CN0; however, no more than two alternates shall l 1 participate as members in NSAB activities at any one time.
l MEETING FEFOUENCY i
j 6.5.3.4 The n 34 shall meet at least once per calendar quarter. !
000 RUM 'l l
j 6.5.3.5 The quorum of the NSA8 shall consist of a majority of NSA8 members j including the Chairperson or Vice Chairperson. No more than a
] minority of the quorum shall have line responsibility for operation i of the same Northeast Utilities' nuclear unit. No more than two i alternates shall be appointed as members at any meeting in fulfillment of the quorum requirements.
- REVIEW RESPONSIBILITIES i l
- 6.5.3.6 The NSAB shall be responsible for the review of:
l l a. The safety evaluations for changes to procedures, equipment, or i 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 i 10 CFR 50.59; 1
- b. Proposed changes to procedures, equipment, or systems that involve an unreviewed safety question as defined in 8
10 CFR 50.59; a
- 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; i
Millstone Unit 2 6-10 Amendment No. 17. (J. JJ.
one l}$,191,199,191,
ADMINISTRATIVE CONTROLS i
l
! e. Violations of applicable codes, regulations, orders, license j 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 of design or operation of structures, systems, or
! components that could affect nuclear safety; a
l h. Significant accidental, unplanned, or uncontrolled radioactive re' eases, including corrective actions to prevent recurrence; l
! 1. Significant operating abnormalities or deviations from normal l and expected performance of equipment that could affect nuclear i safety; l j. The performance of the corrective action' program; and 4
- k. Audits and audit plans.
1 Reports or records of these reviews shall be forwarded to the President, CEO and CN0 within 30 days following completion of the l review.
AUDIT PROGRAN RESPONSIBILITIES 6.5.3.7 The NSA8 audit program shall be the responsibility of the Nuclear Oversight organization. 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 j within the Technical Specifications and applicable license :
conditions; i
- b. The training and qualifications of the unit staff; I
- c. The implementation of all programs required by Specification 6.8; i
- d. The Fire Protection Program and implementing procedures.
- e. The fire protection equipment and program implementation l 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 2 6-11 Amendment No. M M. M ,
un M, FM,111,1H, M1,1H,
1 i
ADMINISTRATIVE CONTROLS i
RECORDS j 6.5.3.8 Written records of reviews and audits shall be maintained. As a 4 minimum these records shall include:
1
- a. Results of the activities conducted under the provisions of j Section 6.5.3; 4
) 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. Detemination as to whether each item considered under I Specification 6.5.1.6.a. 6.5.1.6.b, 6.5.1.6.d, and 6.8 ,
1 constitute an unreviewed safety question as defined in 1
- 10 CFR 50.59. j 1 1 j 6.5.4 Station Qualified Reviewer Proaram Function
- 6.5.4.1 The Unit Director or Millstone Unit 2 Recovery Officer or Executive l Vice President may establish a Station Qualified Reviewer Program 1 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 j performed by Station Qualified Reviewers and approved by designated ;
3 managers. These reviews are in lieu of reviews by the PORC or SORC. )
However, procedures which require a 10CFR50.59 evaluation must be j
- reviewed by the PORC or SORC.
Responsibilities 6.5.4.2 The Station Qualified Reviewer Program shall:
j 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.
3 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 j Reviewer (s) in affected disciplines, or by other persons j designated by cognizant Managers or Directors as having
, specific expertise required to assess a particular procedure, j program, or change. Cross-disciplinary reviewers may function as a committee, i .
j d. Provide for a screening of designated procedures, programs and 3 changes thereto to determine if an evaluation should be i performed in accordance with the provisions of 10CFR50.59 to i verify that an unreviewed safety question does not exist. This i screening will be performed by personnel trained and qualified y in performing 10CFR50.59 evaluations.
i Millstone Unit 2 6-12 Amendment Nos. J7, JJ, pf, Jpp, Jpf,
i ADMINISTRATIVE CONTR0LS i' 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 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/SORC for review.
6.5.4.4 Personnel recommended to be Station Qualified Reviewers shall be ,
designated in writing by the Unit Director or Millstone Unit 2 Recovery Officer, or Executive Vice President for each procedure, program, Jr 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:
- a. A Bachelors degree in engineering, related science, or technical discipline, and two years of nuclear power plant experience; OR
- b. Six years of nucloar power plant experience; l OR
- c. An equivalent combination of education and experience as ;
approved by a Department Manager. l l
l Millstone Unit 2 6-13 Amendment Nos. J77, one i
)
ADMINISTRATIVE CONTROLS f
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 i results of this review shall be submitted to the Chairperson of the NSA8 and the President, CEO and CNO. l 6.7 SAFETY LIMIT VIOLATION 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. ,
l
- b. The NRC Operations Center shall be notified by telephone as l soon as possible and in all cases within I hour. The ;
President, CEO and CN0 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 />; s <
- c. A Safety Limit Violation Report shall be prepared. The report i j shall be reviewed by the PORC. This report shall describe: I l (1) applicable circumstances preceding the violation, (2) effects of the violation upon facility components, systems, '
or structures, and (3) cerrective action taken to prevent recurrence;
- d. The Safety Limit Violation Report shall be submitted to the Commission, the Chairperson of the NSAB, and the President, CEO l and CN0 within 14 days of the violations.
- 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 appitcable procedures recommended in Appendix "A" of Regulatory Guide 1.33, February,1978.
- b. Refueling operations.
- c. Surveillance activities of safety related equipment.
- d. Not used,
- e. Not used.
N111 stone Unit 2 6-14 Amendment Nos. 77, JJ. 77, JJJ.
one 191,191,199,191,199,
1 ADMINISTRATIVE CONTROLS 2
j f. Fire Protection Program implementation.
- 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 (REMDDCM) implementation, except for Section I.E.,
i Radiological Environmental Monitoring.
j 6.8.2 a. The Unit Director or Millstone Unit 2 Recovery Officer or l Executive Vice President may designate specific procedures and i programs, or classes of procedures and programs to be reviewed in i accordance with the Station Qualified Reviewer Program in "eu of
- review by the PORC/SORC. The review per the 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 Director or Millstone Unit ,
2 Recovery Officer or Executive Vice President or by cognizant l l Manager or Directors who are designated as the Approval Authority i by the Unit Director or Millstone Unit 2 Recovery Officer or l Executive Vice President, as specified in administrative procedures. The Approval Authority for each procedure and program
- or class of procedure and program shall be specified in
- administrative procedures.
1
! c. Each procedure of Specification 6.8.1, and changes thereto, shall i be reviewed by the PORC or SORC and shall be approved by the Unit l l Director or Executive Vice President respectively, or be reviewed and approved in accordance with the Station Qualified Reviewer i Program, prior to implementation. Each procedure of Specification
! 6.8.1 shall be reviewed periodically as set forth in
- administrative procedures.
{
1 1 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 !
i staff, at least one of whom holds a Senior Reactor Operator's
- License on the unit affected.
! c. The change is documented, reviewed by the PORC or SORC, or the
- Station Qualified Reviewer Program as applicable, and approved by i the Unit Director or the President, CEO and CNC or the Station l )
- Qualified Reviewer Program Manager within 14 days of implementation.
! 6.8.4 Written procedures shall be established, implemented and maintained l covering Section I.E, Radiological Environmental Monitoring, of the l
- REMODCM.
i i
Millstone Unit 2 6-15 Amendment Nos. Jp, Jp, 77. JJJ,
, Olle hhh,[ff,hhh.
- - __ - - - - - . _ ~ - - - . - - . - - - - - . _ . . - - - - _ _ . -
1 I
- )
i ADNINISTRATIVE CONTROLS '
4 6.15 RADIOLOGICAL EFFLUENT MONITORING AND OFFSITE DOSE CALCULATION "^."9AL (REM 00CM) i Section I, Radiological Effluents Monitoring Manual (REM), shall outline the sampling and analysis programs to determine the concentration of radioactive mat 1 rials 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 i 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 REMODCM: '
- a. Shall be documented and records of reviews perfomed shall be r 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 reli.Sility of effluat, !
dose, or setpoint calculations. !
- b. Shall become effective after review and acceptance by SORC and the l approval of the President, CEO and CNO. l 1
- c. Shall be submitted to the Commission in the form of a complete, '
legible copy of the entire REM or 00CM, 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, 0279
ADMINISTRATIVE CONTROLS 6.1 RESPONSIBILITY 6.1.1 The President, Chief Executive Officer (CEO) and Chief Nuclear -
Officer (CN0) shall be responsible for overall operation of the Millstone Station site while the Unit Director shall be responsible for operation of the unit. The President, CEO and CN0 and Unit Director shall each delegate in writing the succession to thase responsibilities during their absence.
6.2 ORGANIZATION 1
6.2.1 0FFSITE AND QNSITE 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 poter plant.
- a. Lines of authority, responsibility, and communication shall be established and defined for the highest management levels through intermediate levels to and including all operating organization positions. These relationships sha'l 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 3 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 President, CEO and CN0 shall have corporate responsibility for overall plant nuclear safety and shall take any measures needed to ensure acceptable performance of the staff in operating, maintaining, and providing technical support to the plant to ensure nuclear safety.
- d. The individuals who train the operating staff and those who carry out health physics and quality assurance functions may report to the appropriate onsite manager; however, they shall have sufficient organizational 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; NILLSTONE - LSIIT 3 6-1 Amendment No. JJ. JJ. 77, 0463
. _ - _ _ _ . . . _ . . _ _ _- _ _ _ . _ = - , _ - . _ . , _ _ _ _ _ _ _ _ - . , . _ , , - ,
,I
i ADNINISTRATIVE CONTROLS h
i 6.2.3 INDEPENDENT SAFETY ENGINEERING GROUP fISEG)
FUNCTION l'
6.2.3.1 The ISEG shall include, as part of its function, examination of unit operating characteristics, NRC issuances, industry advisories, Licensee Event
! Reports, and other sources of unit design and operating experience information, including units of similar design, which may indicate areas for 2 improving unit safety. The ISEG shall make detailed recommendations for revised procedures, equipment modifications, maintenance activities, operations activities, or other means of improving unit safety to appropriate station / corporation management.
COMPOSITION 6.2.3.2 The ISEG shall be composed of at least few full-time personnel i located on site to perform the functions described in 6.2.3.1 for Millstone Unit 3. Each person rhall 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 l 6.2.3.3 The ISEG shall be responsible for maintaining surveillance of unit activities to provide independent verification
- that these activities are ,
performed correctly and that human errors are reduced as much as practical. I MCORDS )
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 l 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. J/, pp, 0464
l ADMINISTRATIVE CONTROLS 6.3 FACILITY STAFF QUALIFICATIONS !
l 6.3.1 Each member of the facility staff shall meet or exceed the minimum 1 qualifications of ANSI N18.1-1971* for comparable positions, except for the Health Physics Manager who shall meet or excee6 the qualifications of Regulatory Guide 1.8, Revision 1 May 1977. l 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 Millstone Unit 3 Recovery i Officer and shall meet or exceed the requirements and recommendatP.,ns 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.I PLANT OPERATIONS REVIEW COMITTEE (PORC)
FUNCTION 6.5.1.1 The PORC shall function to advise the Unit Director on all matters l related to nuclear safety.
COMPJSITION 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 Chemistry Work Planning .
Quality Assurance The minimum qualifications of PORC members shall be that all members have an i 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 Unit Director. The Chairperson and alternate Chairperson of the PORC shall be drawn from the PORC members and be appointed in writing by the Unit Director.
l *For the period ending three years after the issuance of Amendment No. 94, the Operations Manager will be permitted to have held a senior reactor operator license at a similar Pressurized Water Reactor other than Millstone Unit No. 3 and at least one of the Operations Assistant (s) shall hold a senior reactor l l operator license.
MILLSTONE - L51IT 3 6-5 Amendment No. 77, pp. 77, 77, 77, un 117,
ADMINISTRATIVE CONTROLS ALTERNATES 6.5.1.3 All alternate members shall be a Chairperson to serve on a temporary basis;ppointed howeverinnowriting by the more than PORC two alternates shall participate as voting members in bC activities at any one time.
MEETING FREQUENCY 6.5.1.4 The PORC shall meet at least once per calendar month and as convened by the PORC Chairperson.
QUORUM 6.5.1.5 The quorum of the PORC shall consist of the Chairperson or Vice Chairperson and four members including citernates. l RESPONSIBILITIES 6.5.1.6 The PORC shall be responsible for:
- a. Review of: 1) all procedures, exce >t common site procedures, required by(Specification 6.8 and cianges thereto2 except common site pr rams required by Specificalion) 6.8 andall programs, changes thereto, and ) any other proposed procedures, programs or changestheretoasdeetsinedbytheUnitDirectortoaffectnuclearl 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 Spec.ifications, including the preparation and forwarding of reports c.overing evalua-tion and recommendations to prevent recurrence to the President, CEOandCNO,theMillstoneUnit3RecoveryOfficeransttothe 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, investigations, or analyses and reports thereon as requested by the Chairperson of the Nuclear Safety Assessment Board or the Millstone Unit 3 Recovery Officer; l and
- 1. 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 - LNIIT 3 6-6 Amendment No. JJ pp. 77, JP, Jpf, oees Jil
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:
- a. Recommend to the Unit Director written approval or di-approval of l items considered under Specification 6.5.1.6a. thro w d. above; and
- b. Provide written notification to the Millstone Unit 3 Recovery Officer and the Chairperson of the Nuclear Safety Assessment Board of disagreement between the PORC and the Unit Director; however, the Unit Director shall have responsibilit disagreements pursuant to Specification 6.y 1.1.for resolution of such RECORDS 6.5.1.8 The PORC shall maintain written minutes of each meeting and copies shall be provided to the Unit Director and Millstone Unit 3 Recovery Officer l and the Chairperson of the Nuclear Safety Assessment Board.
6.5.2 SITE OPERATIONS REVIEW COMITTEE (SORC)
FUNCTION 6.5.2.1 The SORC shall function to advise the President, CEO and CN0 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: Nuclear Engineering and Support Recovery Officer Member: Director Unit Operations Member: Unit 2 Un,it Director Member: Unit 3 Unit Director Member: Director Nuclear Services Member: Manager , General Services Member: DesignaledMemberofUnit1PORC Member: Designated Member of Unit 2 PORC Member: Design ted Member of Unit 3 PORC Member: Designated Member of Nucisar Oversight l The Senior Unit Director / Director, Unit Operations in attendance shall be the Vice Chairperson. l MILLSTONE - UNIT 3 6-7 Amendment Mo. 77, pp, Jpp, J77, ones Jip
ADNINISTRATIVE CONTROLS ;
I 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.
I MEETING FREQUENCY I
6.5.2.4 The 50RC shall meet at least once per 6 months and as convened by
- the SORC Chairperson.
000 RUM 6.E.2.5 A quorum of the SORC shall consist of the Chairperson or Vice Chairperson and five members including alternates.
RESPONSIBILITIES l
6.5.2.6 The SORC shall be responsible for: I
- a. 1 Review tion 6.8 of an(d) changes thereto, (2) all common site pro rams,all common site
, required by Specification 6.8 and changes thereto, (3 any other proposed procedures, programs, or changes thereto as the President, CEO and CN0 to affect site nuclear safety. eterminedbyl Common site programs and procedures required by Specification 6.8 that are designated for review and approval by the Station Qualified Reviewer Program do not require 50RC review.
- 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 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 j systems or equipment that affect nuclear safety; and
- h. Render determinations in writing or meeting minutes if any item considered under appropriate and as Specification 6.5.2.6(a) through provided by 10CFR50.59 (g)92above, as or 10CFR50.
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. '
I MILLSTONE - UNIT 3 6-8 Amendment No. J7, pp, J7J. JJJ.
o*** JJP
-.-- - - _ . - - . . _ , --- . _ . = - . . . -. __ ..- . . .
i ADMINISTRA1IVE CONTR6!3 i,
! AUTHORITY 6.5.2.7 The SORC shall:
. a. Recommend to the President, CEO an( CN0 written approval or l
] disapproval in weting minutes of items considered under Specification o.n.2.6(a) through (g) above, and
- b. Provide immediate written notification or meeting minutes to the i
Chairperson of the Ntclear Safety Assessment Board of disagreement i between the SORC and the President, CEO and CN0; however, the
- President, CEO and CNC dall have responsibility for resolution of j such disagreements pursuant to 6.1.1 above.
RECORDS i
6.5.2.8 The SORC shall maintain written minutes of each meeting and copies shall be provided to the President, CEO and CN0 and Chairperson of the Nuclear
- Safety Assessment Board.
l
- 6.5.3 Elg. LEAR SAFETY ASSESSMENT BOARD (NSAB) j FUNCTION i 6.5.3.1 The minimum qualificati'ans of NSAB members are as follows
- a. The Chairperson and NSAB members shall have
- 1
! 1) An academic degree in an engineering or physical science j 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 plat operations;
- 2) Nuclear engineering;
- 3) Chemistry and radiochemistry;
- 4) Metallurgy;
- 5) Instrumentation and control;
- 6) Radiological safety; NILLSTONE - UNIT 3 6-9 Amendment R9. #, pp, pp, Jpp, JM, um
l ADNINISTRATIVE CONTROLS i
- 7) Mechanical and electrical engineering; and
, 8) Quality assurance practices.
4 i
- The NSAB serves to advise the President, CEO and CN0 on matters related to i nuclear safety and notify the President, CEO and CNO 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 4
function being revi w d.
J
- COMPOSITION 6.5.3.2 The President, CEO and CN0 shall appoint, in writing, a minimum of l l aven members to the NSA8 and shall designate from this membership, in i
writing, a Chairperson and a Vice Chairperson. The membership shall function to provide independent review and audit in the areas listed in !
j Specification 6.5.3.1. '
, ALTERNATES l 6.5.3.3 All alternate members shall be appointed, in writing, by the l President, CEO and CN0; however, no more than two alternates shall participate l ,
j as members in NSAB activities at any one time. l l MEETING FREQUENCY j 6.5.3.4 The NSAB shall meet at least once per calendar quarter. 1 900 RUM 6.5.3.5 The quorum of the NSAB shall consist of a majority of NSA8 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 CFM 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 l 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; NILLSTONE - INIIT 3 6-10 Amendment No. # , # , J M , J# ,
um Corr. Ltr. 4/6/94
i ADNINISTRATIVE 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; j
- 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; j
- 1. Significant operating abnormalities or deviations from normal and l expected performance of equipment that could affect nuclear safety; 1
- 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, CEO and CN0 following completion of the review. l AUDIT PROGRAN RESPONSIBILITIES l
6.5.3.7 The NSAB audit program shall be the responsibility of the Nuclear j oversight organization. NSAB audits shall be performed at least once per 24 months in accordance with Nuclear Group Procedures and shall encompass: 1
- a. The conformance of unit operation to provisions contained within l the Technical Specifications and applicable license conditions; '
- b. The training and qualifications of the unit staff; j
- 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 '
NILLSTONE - UNIT 3 6-11 Amendment No. JJ. 77, JJ. JP, ones 199,119,
.. -. - -. - _. _ . . . _ -. - - - - - - . - ~ - . - - - . _ - - - - - . .
ADMINISTRATIVE CONTROLS '
i
- nraans i
6.5.3.8 Written records of reviews and audits shall be maintained. As a ;
minimum these records shall include:
i '
- a. Results of the activities conducted under the provisions of l Section 6.5.3; ;
I :
i '
- 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 l
< c. Detemination as to whether each item considered under- !
I Specification 6.5.1.6.a, 6.5.1.6.b, 6.5.1.6.d, and 6.8 constitute i i an unreviewed safety question as defined in 10 CFR 50.59. '
6.5.4 Station Qualified Reviewer Proaram i
- I l Function i 6.5.4.1 The Unit Director or Millstone Unit 3 Recovery Officer or i Executive Vice President and Chief Nuclear Officer may establish a Station j Qualified Reviewer Program whereby required reviews of designated procedures j 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 l managers. These reviews are in lieu of reviews by the PORC or 50RC. However, '
procedures which require a 10 CFR 50.59 evaluation must be reviewed by the 4
PORC or SORC.
\
Responsibilities
)
l 6.5.4.2 The Station Qualified Reviewer Program shall:
i a. Provide for the review of designated procedures, programs, and changas thereto by a Qualified Reviewer (s) other than the 4 individual who prepared the procedure, program, or change. 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.
i 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 performed by personnel trained and qualified in performing i 10 CFR 50.59 evaluations.
NILLSTONE - UNIT 3 6-12 Amendment No. JJ, JJ, JJ. JJ, JJJ om JJJ.
- -- pr .-
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.
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 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/SORC for review.
6.5.4.4 Personnel recommended to the Station Qualified Reviewers shall be designated in writing by the Unit Director or Millstone Unit 3 Recovery Officer or Executive Vice President 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. i Qualified reviewers shall have:
- a. A Bachelors degree in engineering, related science, or technical discipline, and two years of nuclear power plant experience; OR l
- b. Six years of nuclear power plant experience; l
- c. An equivalent combination of education and experience as approved by a Department Manager.
NILLSTONE - UNIT 3 6-13 Amendment No. JU ,
==
i 1
1 i ADMINISTRATIVE CONTROLS i
6.6 REPORTABLE EVENT ACTION ,
)
6.6.1 The following actions shall be taken for REPORTABLE EVENTS:
i a. The Commission shall be notified and a report submitted pursuant j to the requirements of Section 50.73 to 10 CFR Part 50, and ,
1 1
- b. Each REPORTABLE EVENT shall be reviewed by the PORC and the I results of this review shall be submitted to the Chairperson of j the NSA8 and the President, CEO and CNO.
l l
j 6.7' SAFETY LIMIT VIOLATION i 6.7.1 The following actions shall be taken in the event a Safety Limit is j violated:
i
- a. The Unit shall be placed in at least HOT 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 I hour. The President, CEO l
i and CN0 and the Chairperson of the 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 i shall be reviewed by the PORC. This report shall describe:
(1) applicable circumstances preceding the violation, (2) effects ;
{ of the violation upon facility components, systems, or structures, l and (3) corrective action taken to prevent recurrence; .l 4
' 1
- d. The Safety Limit Violation Report shall be submitted to the
, Commission, the Chairperson of the NSAB, and the President, CEO j and CN0 within 14 days of the violation; and 4
l e. Operatic 1 shall not be resumed until authorized by the Commission.
I
- 6.8 PROCEDURES AND PROGRAMS 1 6.8.1 Written procedures shall be established, implemented, and maintained
- covering the activities referenced below:
?
i a. The applicable procedures recommended in Appendix A of Regulatory l Guide 1.33, Revision 2, February 1978;
! b. The applicable procedures required to implement the requirements of NUREG-0737 and supplements thereto; j c. Refueling operations;
- d. Surveillance activities of safety related equipment; i e. Not used.
i i
MILLSTONE - UNIT 3 6-14 Amendment No. 77, 77, Jpf, JJJ, ones J19, i
1
ADNINISTRATIVE CONTROLS
- f. Not used.
- g. Fire Protection Program implementation;
- h. Quality controls for effluent monitoring, using the guidance in Regulatory Guide 1.21, Rey, 1, June 1974; and
- 1. Radiological Effluent Monitoring and Offsite Dose Calculation Manual (REMODCM) implementation except for Section I.E, Radiological Environmental Monitoring.
6.8.2 a. The Unit Director or Millstone Unit 3 Recovery Officer or Executive Vice President may designate specific procedures and programs, or classes of proceduras and programs to be reviewed in accordance with the Station Qualified Reviewer Program in lieu of review by the PORC/SORC. The review per the 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 >e approved by the Unit Director or Millstone Unit 3 Recovery Officer or Executive Vice President or by cognizant Manager or Directors who are designated as the Approval Authority by the Unit Director or M111stc;.v Unit 3 Recovery Officer or Executive Vice President, as specified in administrative procedures. The Approval Authority for each procedure and program or class of procedure and program shall be specified in administrative procedures.
- 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 Unit Director, President, CEO and CNO, respectively, 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 reviewml 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 Qualified Reviewer Program, as appropriate, and approved by the Unit Director or President, CEO and CNO or Station Qualified Reviewer Program Manager within 14 days of implementation.
MILLSTONE - UNIT 3 6-15 Amendment No. pp, pp, 177 177.
0464
! ADMINISTRATIVE CONTROLS 4
l 6.13 RADIOLOGICAL EFFLUENT MONITORING AND OFFSITE DOSE CALCULATION MANUAL (REMODCM) i Section I, Radiological Effluent 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 1 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 l to radioactive gaseous and liquid effluents and in the calculations of gaseous ;
and liquid effluent monitoring instrumentation alare/ trip setpoints consistent -
with the applicable LCOs contained in these technical specifications. I Changes to the REMODCM: ;
- a. Shall be documented and records of reviews performed shall be retained as !
required by Specification 6.10.30. 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 radioac-tive affluent 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 l approval of the President, CEO and CNO. l 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 sage that was changed, and shall indicate the date (e.g., month / year) the ciange was implemented. j i
6.14 RADI0 ACTIVE WASTE TREATMENT i Procedures for liquid and gaseous radioactive affluent discharges from the !
Unit shall 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 00CM.
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 ground requirements.
MILLSTONE - UNIT 3 6-24 Amendment No. pp, 77, pp. 79, 0466
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