ML20137U296
| ML20137U296 | |
| Person / Time | |
|---|---|
| Site: | Millstone  |
| Issue date: | 04/10/1997 |
| From: | Mckee P NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML20137U273 | List: |
| References | |
| NUDOCS 9704160346 | |
| Download: ML20137U296 (49) | |
Text
.
% "4 g
21 UNITED STATES g
g
,j NUCLEAR REGULATORY COMMISSION o
WASHINGTON, D.C. 20565-0001 49.....,o NORTHEAST NUCLEAR ENERGY COMPANY DOCKET NO. 50-245 MILLSTONE NUCLEAR POWER STATION. UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.99 License No. DPR-21 1.
The Nuclear Regulatory Commission (the Comission) has found that:
A.
The application for amendment by Northeast Nuclear Energy Company (the licensee) dated February 3, 1997, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Comission's rules and regulations set forth in 10 CFR Chapter I; B.
The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Comission; C.
There is reasonable assurance (1) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Comission's regulations; D.
The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E.
The issuance of this amendment is in accordance with 10 CFR Part i
51 of the Comission's regulations and all applicable requirements have been satisfied.
i s
J l
)
I 9704160346 970410 PDR ADOCK 05000245 p
PDR 1
I
_n
e
' 2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. DPR-21 is hereby amended to read as follows:
(2)
Technical Soecifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 99, are hereby incorporated in the license.
The licensee shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment is effective as of the date of issuance, to be implemented within 60 days of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION Phillip F. McKee Deputy Director for Licensing Special Projects Office.
Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance: April 10, 1997
ATTACHMENT TO LICENSE AMENDMENT NO. 99 FACILITY OPERATING LICENSE NO. DPR-21 DOCKET NO. 50-245 Replace the following pages of the Appendix A, Technical Specifications, with the attached pages.
The revised pages are identified by amendment number and contain vertical lines indicating the areas of change.
1 Remove Insert 6-1 6-1 6-5 6-5 6-6 6-6 6-7 6-7 6-8 6-8 6-9 6-9 6-10 6-10 6-11 6-11 6-12 6-12 1
6-13 6-13 i
6-14 6-14 6-15 6-15 6-23 6-23 1
L 4
m..
o ADMINISTRATIVE CONTROLS 6.1 RESPONSIBILITY 6.1.1 The Senior Vice President and Chief Nuclear Officer (CNO) - Millstone shall be responsible for overall operation of the Millstone Station Site while the Millstone Unit 1 Recovery Officer shall be responsible for overall unit safe operation and the Director, Unit Operations shall be responsible for i
operation of the unit. The Senior Vice President and CNO - Millstone, i
Millstone Unit 1 Recovery Officer, and Director, Unit Operations shall each delegate, in writing, the succession to these responsibilities during their absence.
{
6.2 ORGANIZATION i
j 6.2.1 0FFSITE AND ONSITE ORGANIZATifM Onsite and offsite organizations shall be established for unit operation and curporate management, respectively. The onsite and offsite organizations l
shall include the positions for activities affecting the safety of the nuclear power plant.
a.
Lines of authority, responsibility, and communication shall be established and defined for the higher management levels through j
intermediate levels to and including all operating organization positions. These relationships shall be documented and updated, as appropriate, in the forr 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, b.
The Millstone Unit 1 Recovery Officer shall be responsible for l
overall unit safe operation and shall have control over those onsite activities necessary for safe operation and maintenance of the plant.
c.
The Senior Vice President and CN0 - Millstone shall have corporate l
responsibility for overall plant nuclear safety and shall take any measures needed to ensure acceptable performance of the staff in operation, maintaining, and providing technical support to the plant to ensure nuclear safety.
d.
The individuals who train the operating staff and those who carry out health physics and quality assurance functions may report to the appropriate onsite manager; however, they shall.have sufficient organizational freedom to ensure their independence from operating I
pressures.
6.2.2 FACILITY STAFF a.
Each on duty shift shall be composed of at least the minimum shift.
crew composition shown in Table 6.2-1.
b.
At least one licensed Operator shall be in the control room when fuel is in the reactor, c.
At least two licensed Operators shall be present in the control room during reactor start-up,. scheduled reactor shutdown and during recovery from reactor trips.
Millstone Unit 1 6-1 Amendment No. 77, pp, 7J, 99 0281
i i.
ADMINISTRATIVE CONTROLS 6.4 TRAINING i
I 6.4.1 A retraining and replacement training program for the facility staff shall be maintained under the direction of the Senior Vice President l
and CN0 - Millstone and shall meet or exceed the requirements and l
recommendations of Section 5.5 of ANSI N18.1-1971 and 10 CFR Part 55.59. The Director-Nuclear Training has the overall responsibility j
for the implementation of the Training Program.
6.5 REVIEW AND AUDIT 1
6.5.1 Plant Doerations Review Committee (PORC)
Function l
4 6.5.1.1 The PORC shall function to advise the Director, Unit Operations on l
l all matters related to nuclear safety.
1 Comoosition 6.5.1.2 The PORC shall be composed of nine to eleven members. Members shall i
collectively have experience and expertise in the following areas:
J Plant Operations i
Engineering j
Reactor Engineering i
Maintenance l
Instrumentation and Controls Health Physics Chemistry i
Work Planning Quality Assurance The minimum qualifications of PORC members shall be that all members have an academic degree in an engineering or physical science field, or hold a management position, and have a minimum of five years technical experience in their respective field of expertise. The members of PORC shall be appointed in writing by the Director, Unit 0)erations. The Chairperson and alternate Chairperson of the PORC l
sia11 be drawn from the PORC members and be appointed in writing by the Director, Unit Operations.
l Alternates 6.5.1.3 Alternate members shall be appointed in writing by the PORC Chairperson to serve on a temporary basis; however, no more than two alternates shall participate in PORC activities at any one time.
I Millstone Unit 1 6-5 Amendment No. 77, 77, 77. 77, 99 0282
f f
ADNINISTRATIVE CONTROLS Jigg. tina Freauency 6.5.1.4 The PORC shall meet at least once per calendar month and as convened by the PopC 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 Responsibilities 6.5.1.6 The PORC shall be responsible for:
Review of 1) all procedures, except conson tite procedures, a.
required by Specification 6.8 and changes thereto, 2) all programs, except common site programs, required b3 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 reqcired 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.
Review of all proposed changes to Sections 1.0 - 5.0 of these c.
Technical Specifications.
d.
Review of all proposed changes or modifications to piirt systems or equipment that affect nuclear safety.
Investigation of all violations of the Technical Specifications e.
and preparation and forwarding of a report covering evaluation and recommendations to prevent recurrence to the Senior Vice President and CN0 - Millstone and to the Chairperson of the Nuclear Safety Assessment Board.
f.
Review of all REPORTABLE EVENTS.
Review of facility operations to detect potential safety hazards.
g.
h.
Performance of special review:..:d investigations and reports thereon as requested'by the Chairperson of the Nuclear Safety l
Assessment Board.
I Render determinations in writing if any item considered under t
1.
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, pp. 77, 77, 51, 99 ossa
a
+.
ADMINISTRATIVE CONTROLS 1
~
l' l
j.
Review of the unit-specific Fire Protection Program and implementing procedures.
l Authority i
6.5.1.7 The PORC shall:
i l
a.
Recommend to the Director, Unit Operations written approval or l
disapproval of items considered under 6.5.1.6(a) through (d) above.
b.
Provide immediate written notincation to the Senior Vice 1
President and CNO - Millstone, Millstone Unit 1 Recovery Officer, l
j and the Chairperson of the Nuclear Safety Assessment Board of disagreement >etween the PORC and the Director, Unit Operations; i
however, the Director, Unit Operations shall have responsibility i-for resolution of such disagreements pursuant to 6.1.1 above.
i Records i
6.5.1.8 The PORC shall maintain written minutes of each meeting and copies shall be provided to the Senior Vice President and CNO - Millstone and l Chairperson of the Nuclear Safety Assessment Board.
6.5.2 Site Operations Review Committee (SORC)
Function 1
6.5.2.1 The SORC shall function to advise the Senior Vice President and CN0 -
Millstone on all matters related to nuclear safety of the entire Millstone Station Site.
)
6.5.2.2 The SORC shall be composed of the:
1 l
Chairperson:
Senior Vice President and CNO - Millstone Member:
Director, Unit Operations Member:
Unit 2 Unit Director Member:
Unit 3. Unit Director Member:
Director, Nuclear Services Member:
Manager, General Services l
Member:
Designated Member of Unit 1 PORC l
Member:
Designated Member of Unit 2 PORC i
Member:
Designated Member of Unit 3 PORC l
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, no more than-two alternates shall participate in 50RC activities at one time.
Millstone Unit 2 6-7 Amendment No. pp, 7(, 77, JJ, 7J, 99 0393
ADNINISTRATIVE CONTROLS Meetina Freauency 6.5.2.4 The 50RC shall meet at least once per six months and as convened by the i
SORC Chairperson.
All2 DIE 6.5.2.5 A quorum of the 50RC shall consist of the Chairperson or Vice Chairperson and five members including alternates.
Resnonsibilities 6.5.2.6 The 50RC 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 Specification 6.8 and changes thereto, 3) any other proposed procedures, programs, or changes thereto as determined by the Senior Vice President and CN0 - Nillstone'to affect site nuclear l
safety. Common site programs ar.d procedures required by Specification 6.8 that are designated for review and approval by the Station Qualified Review Program do not require 50RC review.
I b.
Review of all proposed changes to Section 6.0, " Administrative Controls", of these Technical Specifications.
c.
Performan~ce 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.
g.
Review of all common site proposed changes or modifications to systems or equipment that affect nuclear safety.
h.
Rendar 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.
N111 stone Unit 1 6-8 Amendment No. 77, 77, 77, 71, 77, 99 oas
4 ADMINISTRATIVE CONTROL 5 1
Authority 6.5.2.7 The SORC shall:
Recommend to the Senior Vice President and CNO - Millstone written l a.
approval or disapproval, in meeting minutes, of items considered under 6.5.2.6(a) through (g) above.
b.
Provide immediate written notification, or meeting minutes, to the President and Chief Executive Officer (CEO) and the Chairperson of the Nuclear Safety Assessment Board of disagreement between the 50RC and the Senior Vice President and CNO - Millstone; however.
the Senior Vice President and CN0 - Millstone shall have responsibility for resolution of such disagreements pursuant to 6.1.1 above.
Records 6.5.2.8 The 50RC shall maintain written minutes of each meeting and copies shall be provided to the Senior Vice President and CNO - Millstone and l Chairperson of the Nuclear Safety Assessment Board.
6.5.3 NUCLEAR SAFETY ASSESSMENT BOARD (NSAB)
FUNCTION 6.5.3.1 The minimum qualifications of NSAB members are as follows:
a.
The Chairperson and NSAB members shall have:
1.
An acv.iemic degree in an engineering or physical science field, or hold a senior management position, and 2.
A minimum of five years technical experience in their respective field of expertise.
b.
The NSAB shall have experience in and shall function to provide independent oversight review and audit of designated activities in the areas of:
1.
Nuclear power plant operations; 2.
Nuclear engineering; 3.
Chemistry and radiochemistry; 4.
Metallurgy; j
5.
Instrumentation and control; 6.
Radiological safety; j
Millstone Unit 1 6-9 Amendment No. U, 5, #, 7(, 77. N, 99 nu
c ADNINISTRATIVE CONTROLS 7.
Mechanical and electrical engineering; and d.
Quality assurance practices.
l The NSAB serves to advise the President and CEO on matters related to nuclear safety and notify the President and CE0 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 6.5.3.2 The President and CEO shall appoint, in striting, a minimum of seven l
members to the NSAB and shall designate from this membershi), in writing, a Chairperson and a Vice Chairperson. The memberstip shall function to provide independent review and audit in the areas listed in Specification 6.5.3.1.
ALTERNATES 6.5.3.3 All alternate members shall be appointed, in writing, by the President and CE0; however, no more than two alternates shall participate as members in NSAB activities at any one time.
{
MEETING FREQUENCY 6.5.3.4 The NSAB shall meet at least once per calendar quarter.
DUORUM 6.5.3.5 The quorum of the NSAB shall consist of a majority of NSAB members including the Chairperssn or Vice Chairperson. No more than a minority of the quorum shall have line responsibility for operation of the same Northeast Utilities' nuclear unit. No more than two alternates shall be appointed as members at any meeting in fulfillment of the quorum requirements.
REVIEW RESPONSIBILITIES 6.5.3.6 The NSAB shall be responsible for the review of:
a.
The safety evaluations for changes to procedures, equipment, or systems, and tests or experiments completed under the provisions of 10 CFR 50.59, to verify that such actions did not constitute an unreviewed safety question as defined in 10 CFR 50.59; b.
Proposed changes to procedures, equipment, or systems that involve an unreviewed safety question as defined in 10 CFR 50.59; c.
Proposed tests or experiments that involve an unreviewed safety question as defined in 10 CFR 50.59; N111 stone Unit 1 6-10 Amendment No. pp, pp. 77, JJ 99 0282
4 i
ADMINISTRATIVE CONTROLS 3
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 j
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.
l Reports or records of these reviews shall be forwarded to the President and CEO within 30 days following completion of the review.
AUDIT PROGRAM RESPONSIBILITIES 6.5.3.7 The NSAB audit program shall be the responsibility of the Audit and Evaluation Department. NSAB audits shall be performed at least once per 24 months in accordance with Nuclear Group Procedures and shall encompass:
a.
The conformance of unit operation to provisions contained within.
the Technical Specifications and applicable license conditions; b.
The training and qualifications of the unit staff; c.
The implementation of all programs required by Specification 6.8; d.
The Fire Protection Program and implementing procedures.
e.
The fire protection equipment and program implementation utilizing either a qualified offsite license fire protection engineer or an outside independent fire protection consultant.
f.
Actions taken to correct deficiencies occurring in equipment, structures, systems, components, or method of operation that affect nuclear safety; and Millstone Unit 1 6-11 Amendment No. J. 77, 77, 71 99 0292
......--.-_.--.-7.-..
i ADMINISTRATIVE CONTROLS g.
Other activities and documents as requested by the President and CEO.
j RECORDS i
l 6.5.3.8 Written records of reviews and audits shall be maintained. As a i
minimum these records shall include:
l l
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 i
i c.
Determination 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 an unreviewed safety question as defined in 10 CFR 50.59.
l 6.5.4 Station Qualified Reviewer Proaram Function 6.5.4.1 The Director, Unit Operations or Millstone Unit 1 Recovery Officer, or Senior Vice President and CN0 - Millstone may establish a Station Qualified Reviewer Program whereby required reviews of designated procedures or classes of procedures required by Specifications 6.5.1.6.a and 6.5.2.6.a are performed by Station Qualified Reviewers and approved by designated managers. These reviews are in lieu of reviews by the PORC or 50RC. However, procedures which require a 10CFR50.59 evaluation must be reviewed by the PORC or 50RC.
Responsibilities 6.5.4.2 The Station Qualified Reviewer Program shall:
a.
Provide for the review of designated procedures, programs, and changes thereto by a Qualified Reviewer (s) other than the individual who prepared the procedure, program, or change.
b.
Provide for cross-disciplinary review of procedures, programs, and changes thereto when organizations other than the preparing organization are affected by the procedure, program, or change.
c.
Ensure cross-disciplinary reviews are performed by a Qualified Reviewer (s) in affected disciplines, or by other persons designated by cognizant managers or directors as having specific expertise required to assess a particular procedure, program, or change. Cross-disciplinary reviewers may function as a committee.
d.
Provide for a screening of designated procedures, programs and changes thereto to determine if an evaluation should be performed in accordance with'the provisions of 10CFR50.59 to verify that Millstone Unit 1 6-12 Amendment No. #, 77, 77 99 0282'
2 l-ADMINISTRATIVE CONTROLS i.
2 an unreviewed safety question does not exist. This screening will j
be performed by personnel trained and qualified in performing i
[
10CFR50.59 evaluations.
t e.
Provide for written recomendation by the Qualified Reviewer (s) to the responsible Manager for approval or disapproval of procedures and programs considered under Specification 6.5.1.6.a and 6.5.2.6.a and that the procedure or program was screened by a qualified individual and found not to require a 10CFR50.59 l
evaluation.
6.5.4.3 If the responsible manager determines that a new program, procedure, or j
change thereto requires a 10CFR50.59 evaluation, that manager will ensure the required evaluation is performed to determine if the new procedure, program, or change involves an unreviewed safety question.
The new procedure, program, or change will then be forwarded with the 4
i 10CFR50.59 evaluation to PORC or SORC for review.
l 1
i 6.5.4.4 Personnel recommended to the Station Qualified Reviewers shall be l
designated in writing by the Director, Unit Operations, Millstone i
Unit 1 Recovery Officer, or Senior Vice President and CNO - Millstone for each procedure, program, or class of procedure or program withir.
.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
>rocedures for which reviews are assigned to Qualified Reviewers will
>e reviewed and j
approved as described in Specification 6.5.4.2.
Records 6.5.4.6 The review of precedures and programs performed under the Station l
Qualified Reviewer Program shall be documented in accordance with j
administrative procedures.
l Trainina and Oualification 1
6.5.4.7 The training and qualification requirements of personnel designated as a Qualified Reviewer in accordance with the Station Qualified Reviewer i
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; j
t OR j
b.
Six years of nuclear power plant experience; OR i
i c.
An equivalent combination of education and experience as approved by a department manager.
r N111 stone Unit 1 6-13 Amendment No. N 99 0282
I' ADMINISTRATIVE CONTROLS 6.6 REPORTABLE EVENT ACTION l
6.6.1 The following actions shall be taken for REPORTABLE EVENTS:
j a.
The Commission shall be notified and a report submitted j
pursuant to the requirement of 10 CFR 50.73.
b.
Each REPORTA8LE EVENT shall be reviewed by the PORC and the results of this review shall be submitted to the Chairperson of the NSAB and the Senior Vice President and CN0 - Millstone.
l 6.7 SAFETY LIMIT VIOLATION j
6.7.1 The following actions shall be taken in the event a $4fety Limit is violated:
a.
The unit shall be placed in at least H0T STANDBY within two hours.
i l
b.
The NRC Operations Center shall be notified by telephone as j
soon as possible and in all cases within one hour. The Senior Vice President and CN0 - Millstone and the Chairperson of the NSAB l
shall be notified within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
l c.
A Safety Limit Violation Report shall be prepared. The report i.
shall be reviewed by the PORC. This report shall describe (1) applicable circumstances preceding the violation, (2) effects l.
of the violation upon facility components, systems or structures, and (3) corrective action taken to prevent recurrence.
1 l
d.
The Safety Limit Violation Report shall be submitted to the 1
Comission, the Chairperson of the NSAB and the Senior Vice l
President and CN0 - Millstone within 14 days of the violation.
l l
e.
Operation shall not be resumed until authorized by the Comission.
I t
l 6.8 PROCEDURES l
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 j
Regulatory Guide 1.33, February, 1978.
j b.
Refueling operations.
l c.
Surveillance activities of safety related equipment.
d.
Not used, e.
Not used.
f.
Fire Protection Program Implementation.
Millstone Unit 1 6-14 Amendment No. J. 77, 77. JJ, JJ,99 0202
-_ -=
ADMINISTRATIVE CONTROLS
)
g.
Quality Control for effluent monitoring using the guidance in Regulatory Guide 1.21 Rev.1, June 1974.
4 h.
Radiological Effluent Monitoring and Offsite Dose Calculation Manual (REMODCM) implementation, except for Section I.E., Radiological Environmental Monitoring.
6.8.2 a.
The Director, Unit Operations or Millstone Unit 1 Recovery Officer, or Senior Vice President and CN0 - Millstone may designate specific procedures and programs, or classes of procedures and programs to be reviewed in accordance with the Station Qualified Reviewer Program in lieu of review by the PORC or SORC. The review per the Qualified l
Reviewer Program shall be in accordance with Specification 6.5.4.
b.
Procedures and programs listed in Specification 6.8.1, and changes 4
thereto, shall be approved by the Director, Unit Operations or Senior Vice President and CN0 - Millstone or by cognizant Manager or a
Directors who are designated as the Approval Authority by the Director, Unit Operations or Senior Vice President and CN0 -
J Millstone as specified in administrative procedures.
Tiie Approval Authority for each procedure and progtam or class of procedure and j
program shall be specified in administrative procedures.
Each procedure of Specification 6.8.1, and changes thereto, shall be c.
reviewed by the PORC or SORC and shall be approved by the Director, Unit Operations or Senior Vice President and CN0 - Millstone, or be reviewed and approved in accordance with the Station Qualified Reviewer Program, prior to implementation.
Each procedure of l
Specification 6.8.1 shall be reviewed periodically as set forth in administrative procedures.
l 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 staff, at least one of whoin holds a Senior Reactor Operator's License on the unit affected.
The change is documented, reviewed by the PORC or SORC, or the l
i c.
Station Qualified Reviewer Program, as applicable, and approved by the Director, Unit Operations, or the Senior Vice President and CN0 -
Millstone or Station Qualified Reviewer Program Department Manager within 14 days of implementation.
J 6.8.4 Written procedures shall be established, implemented and maintained covering Section I.E, Radiological Environmental Monitoring, of the 2
REMODCM.
I 1
Millstone Unit 1 6-15 Amendment No. 77, 77,71.99 0282
l.
i-ADMINISTRATIVE CONTROLS 4
i 6.15 RADIOLOGICAL EFFLUENT MONITORING AND OFFSITE DOSE CALCULATION MANUAL j
(REM 00CM)
Section I, Radiological Effluents Monitoring Manual (REM), shall outline the sampling and analysis programs to determine the cor. centration of radioactive 1
materia s released offsite as well as dose comitments to individuals in those i
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 i
Section II, the Offsite Dose Calculation Manual (0DCM), shall describe the methodology and parameters to be used in the calculation of offsite doses due j
to radioactive gaseous and liquid affluents and in the calculations of gaseous and liquid effluent monitoring instrumentation alarWtrip setpoints consistent 1
with the applicable LCO's contained in these technical specifications.
1 Changes to the REM 0DCM:
a.
Shall be documented and records of reviews performed shall be retained as required by Specification 6.10.2.m.
This documentation l
shall contain:
i i
1)
Sufficient information to support the change together with the
{
appropriate analyses or evaluations justifying the change (s),
4 l
and a
{
2)
A determination that the change will maintain the level of j
radioactive effluent control required by 10 CFR 20.106, 40 CFR
~
Part 190, 10 CFR 50.36a, and Appendix ! to 10 CFR Part 50 and not adversely impact the accuracy or reliability of effluent, i
dose, or setpoint calculations.
i l
b.
Shall become effective after review and acceptance by SORC and the l
approval of the Senior Vice President and CN0 - Millstone.
l i
c.
Shall be submitted to the Comission in the form of a complete,
{
legible copy of the entire REM or ODCM, 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 4
shall be identified by markings in the margin of the affected pages, i
clearly indicating the area of the page that was changed, and shall j
indicate the date (e.g., month / year) the change was implemented.
i i
i 1
Millstone Unit 1 6-23 Amendment No. 7J, 77, 77, 7J. 99 0283
paun g
k UNITED STATES g
,j NUCLEAR REGUL ATORY COMMISSION
%..... /j WASHINGTON, D.C. 20556 4001 o
NORTHEAST NUCLEAR ENERGY COMPANY THE CONNECTICUT LIGHT AND POWER COMPANY ltiLWESTERN MASSACHUSETTS ELECTRIC COMPANY DOCKET NO. 50-336 MILLSTONE NUCLEAR POWER STATION. UNIT N0. 2 Bj!NDMENT TO FACILITY OPERATING LICENSE Amendment No.206 License No. DPR-65 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Northeast Nuclear Energy Company, et al. (the licensee) dated February 3, 1997, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations set forth in 10 CFR Chapter I; B.
The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C.
There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; D.
The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's ' regulations and all applicable requirements have been satisfied.
- 2.
Accordindy, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. DPR-65 is hereby amended to read as follows:
(2)
Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 205, are hereby incorporated in the licens9.
The licensee shall operate the facility in accordance with the Technical Specifications.
3.
This license amend.nent is effective as of the date of issuance, to be implemented within 60 days of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
'O Phillip. McKee Deputy Director for Licensing Special Projects Office Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance: April 10, 1997
__.. ~. _ -. _ _ _
ATTACHMENT TO LICENSE AMENDMENT NO.206 FACILITY OPERATING LICENSE NO. DPR-65 1
DOCKET NO. 50-336 Replace the following pages of the Appendix A, Technical Specifications, with the attached, ages. The revised pages are identified by amendment number and n
contain vertical lines indicating the areas of change.
l l
Remove Insert 6-1 6-1 6-5 6-5 6-6 6-6 6-7 6-7 l
6-8 6-8 6-9 6-9 l
6-10 6-10 6-11 6-11 1
6-12 6-12 6-13 6-13 6-14 6-14 j
6-15 6-15 l
6-24 6-24 l-
\\
l l
I i
I t
l 4
I I
I
l l.
AbMINISTRATIVE CONTROLS 6.1 RESPONSIBILITY 6.1.1 The Senior Vice President and Chief Nuclear Officer (CNO) -
4 Millstone shall be responsible for overall operation of the Millstone Station Site while the Millstone Unit 2 Recovery Officer shall be responsible for i
overall unit safe operation and the Unit 2 Unit Director shall be responsible i
for operation of the unit. The Senior Vice President and CN0 - Millstone,
[
Millstone Unit 2 Recovery Officer and Unit 2 Unit Director shall each delegate in writing the succession to these responsibilities during their absence.
i l
6.2 ORGANIZATION 6.2.1 0FFSITE AND ONSITE ORGANIZATIONS 4
i i
Onsite and offsite organizations shall be established for unit operation and j
corporate managennt, respectively.
The onsite and.offsite organizations i
shall include the positions for activities affecting the safety of the nuclear power plant.
a.
Lines of authority, responsibility, and communication shall be l
e str.*A ished and defined for the higher management levels through intermediate levels to and including all operating organization l
positions. These relationships shall be documented and updated, as 2
app 'opriate, in the form of organization charts, functional descrip-tiras of departmental responsibilities and relationships, and job d'escriptions for key personnel positions, or in equivalent forms of documentation. These requirements shall be documented in the Quality Assurance Topical Report.
1 b.
The Millstone Unit 2 Recovery Officer shall be responsible for l
i overall unit safe operation and shall have control over those onsite l
activities necessary for safe operation and maintenance of the i
plant.
}
c.
The Senior Vice President and CN0 - Millstone shall have corporate l
responsibility for overall plant nuclear safety and shall take any measures needed to ensure acceptable performance of the staff in operation, maintaining, and providing technical support to the plant J
to ensure nuclear safety.
I d.
The individuals who train the operating staff and those who carry out health physics and quality assurance functions may report to the i
appropriate onsite manager; however, they shall have sufficient organizational freedom to ensure their independence from operating pressures.
6.2.2 FACILITY STAFF 1
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.
)
1 Millstone - Unit 2 6-1 Amendment No. (J. pp. 77, pg, 91,199,1H, il1,191e 206 ms
- 179, 1
ADMINISTRATIVE CONTROLS
~
6.4 TRAINING A retraining and replacement training program for the facility staff shall be maintained under the direction of the Senior Vice President and CN0 -
Millstone and shall meet or exceed the requirements and recommendations of Section 5.5 of ANSI N18.1-1971 and 10 CFR Part 55.59. The Director-Nuclear Training has the overall responsibility for the implementation of the Training Program.
i 6.5 REVIEW AND AUDIT 6.5.1 Plant Operations Review Committee (PORC)
]
Function 6.5.1.1 The PORC shall function to advise the Unit 2 Unit Director on all l
matters related to nuclear safety.
Comoosition j
6.5.1.2 The PORC shall be composed of nine to eleven members. Members shall collectively have experier.ce and expertise in the following areas:
{
Plant Operations Engineering Reactor Engineering j
Maintenance Instrumentation and Controls I
Health Physics Chemistry Work Planning Quality Assurance 1
1 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 Unit 2 Unit l
i Director. The Chairperson and alternate Chairperson of the PORC shall be drawn from the PORC members and be appointed in writing by the Unit 2 Unit Director.
l Alternates I
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.
4 Millstone Unit 2 6-5 Amendment No. JJJ, 77J, Jpf, ora gpg 206
A6MINISTRATIVECONTROLS i
Meetina Freauency l
6.5.1.4 The PORC shall meet at least once per calendar month and as convened by the PORC Chairperson.
l Quorum 6.5.1.5 A quorum of the PORC shall consist of the Chairperson, or Vice Chairperson, and four members including alternates.
l t
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 Unit 2 Unit Director to affect nuclear safety.
Procedures and l
programs required by Specification 6.8 that are designated for l
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 pla~nt systems or equipment that affect nuclear safety.
e.
Investigation of all violations of the Technical Specifications and preparation and forwarding of a report covering evaluation and recommendations to prevent recurrence to the Senior Vice President and CN0 - Nillstone and to the Chairperson of the Nuclear Safety Assessment Board.
f.
Review of all REPORTABLE EVENTS.
g.
Review of facility operations to detect potential safety hazards.
h.
Performance of special reviews and investigations and reports thereon as requested by the Chairperson of the Nuclear Safety Assessment Board.
1.
Render determinations in writing if any item considered under 6.5.1.6(a) through (d) above, as appropriate and as provided by 10CFR50.59 or 10CFR50.92, constitutes an unreviewed safety question or requires a significant hazards consideration determination.
j.
Review of the fire protection program and implementing procedure.
N111 stone Unit 2 6-6 Amendment No. J7, pp. 77, 19,111,191, lif,199,171, m, 206
l ADMINISTRATIVE CONTROLS Authority 6.5.1.7 The PORC shall.
a.
Recommend to the Unit 2 Unit Director written approval or
[
disapproval of items considered under 6.5.1.6(a) through (d) above.
b.
Provide immediate written notification to the Senior Vice l
President and CN0 - Millstone, Millstone Unit 2 Recovery i
l Officer and the Chairperson of the Nuclear Safety Assessment l
Board of disagreement between the PORC and the Unit 2 Unit i
Director; however, the Unit 2 Unit Dirt.ctor shall have responsibility for resolution of such disagreements pursuant to j
6.1.1 above.
Records i
6.5.1.8 The PORC shall maintain written minutes of each meeting and copies i
shall be provided to the Senior Vice President and CN0 - Millstone i
and Chairperson of the Nuclear Safety Assessment Board.
6.5.2 Site Doerations Review Committee (SORC) i i
l Function-6.5.2.1 The SORC shall function to advise the Senior Vice President and CN0 - Millstone 'on all matters related to nuclear safety of the entire Millstone Station Site.
Comoosition 6.5.2.2 The SORC shall be composed of the:
Chairperson:
Senior Vice President and CNO - Millstone Member:
Director, Unit Operations Member:
Unit 2 Unit Director Member:
Unit 3 Unit Director Member:
Director, Nuclear Services Member:
Manager, General Services Member:
Designated Member of Unit 1 PORC Member:
Designated Member of Unit 2 PORC Member:
Designated Member of Unit 3 PORC Member:
Designated Member of Nuclear Oversight l
The senior Unit Director / Director, Unit Operations in attendance l
shall be the Vice-Chairperson.
Alternates:
6.5.2.3 Alternate members shall be appointed in writing by the SORC Chairperson to serve on a temporary basis; however, no more than two alternates shall participate in SORC activities at one time.
Millstone Unit 2 6-7 Amendment No. Jpp, J7(, 7pp. 2%
oass
- 7pp,
i-i l
ADNINISTRATIVE CONTROLS j
j i~
Meetina Freauency 6.5.2.4 The 50RC shall meet at least once per six months and as convened by the 50RC Chairperson.
Duorum 6.5.2.5 A quorum of the 50RC shall consist of the Chairperson or Vice j
Chairperson and five members including alternates.
Resnonsibilities 6.5.2.6 The SORC shall be responsible for:
l 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 by the Senior Vice President and CNO - Millstone to affect site l nuclear safety. 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 i
require SORC review.
b.
Review of all roposed chan Controls" of t ese Technica$es to Section 6.0 " Administrative Specifications.
c.
Performance of special reviews and investigations and reports
)
as requested by the Chairperson of the Nuclear Safety Assessment Board.
l d.
Not used.
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 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 30CFR50.59 or 10CFR50.92, constitutes an unreviewed safety question or requires a significant hazards consideration determination.
i 1.
Review of the common site fire protection program and implementing procedures.
Nillstone Unit 2 6-8 Amendment No. 27 f), 177, 177, 199, 191 191, 199.tos om
.. _ _ -..~
m.
ADMINISTRATIVE CONTROLS 1
l 1
Authority l
1 6.5.2.7 The 50RC shall:
4 i
a.
Recommend to the Senior Vice President and CN0 - Millstone l
j-written approval or disapproval in meeting minutes of items considered under 6.5.2.6(a) through (g) above.
b.
Provide immediate written notification or meeting minutes to I-the President and Chief Executive Officer (CEO) and the l
1 l
Chairperson of the Nuclear Safety Assessment Board of disagreement between the 50RC and the Senior Vice President and CN0 - Millstone; however, the Senior Vice President and CN0 -
Millstone shall have responsibility for resolution of such j
disagreements pursuant to 6.1.1 above.
Records 6.5.2.8 The 50RC shall maintain written minutes of each meeting and copies l
shall be provided to the Senior Vice President and CNO - Millstone l
and Chairperson of the Nuclear Safety Assessment Board, i
6.5.3 NUCLEAR SAFETY ASSESSMENT BOARD (NSAB) 1 FUNCTION j
6.5.3.1 The minimum qualifications of NSAB members are as follows:
j_
a.
The Chairperson and NSAB members shall have:
i 1.
An academic degree in an engineering or physical science j
field, or hold a senior management position, and l
2.
A minimum of five years technical experience in their 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 j
in the areas of:
i 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.
Millstone Unit 2 6-9 Amendment Nos. 4, M, 75, ms N.1H. M1 206 1H.IM.IN.
s
?-
j ADMINISTRATIVE CONTROLS 1
4 The NSAB serves to' advise the President and CEO on matters related to nuclear safety and notify the President and CEO within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> of a safety significant disagreement between the NSAB and the i
organization or function being reviewed.
COMPOSITION i
I
]
6.5.3.2 The President and CEO shall appoint, in writing, a minimum of seven l
i members to the NSAB 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 4
j in Specification 6.5.3.1.
ALTERNATES i
i 6.5.3.3 All alternate members shall be appointed, in writing, by the President and CE0; however, no more.than two alternates shall l
participate as members in NSAB activities at any one time.
MEETING FREQUENCY 6.5.3.4 The NSAB shall meet at least once per calendar quarter.
l OUORUM 6.5.3.5 The quorum J the NSAB shall consist of a majority of NSAB members including the Cha'irperson or Vice Chairperson. No more than a i
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 l
fulfillment of the quorum requirements.
I REVIEW RESPONSIBILITIES j
6.5.3.6 The NSAB shall be responsible for the review of:
4 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; i-b.
Proposed changes to procedures, equipment, or systems that i
involve an unreviewed safety question as defined in 10 CFR 50.59; i
i c.
Proposed tests or experiments that involve an unreviewed safety j
question as defined in 10 CFR 50.59; a
d.
Proposed changes to Technical Specifications and the Operating License; i
Millstone Unit 2 6-10 Amendment No. H. #, H.
1H, Hi, 1H,1H ' 206 mm
1 l'
ADMINISTRATIVE Colmt0LS i.
e.-
Violations of applicable codes, regulations, orders, license requirements, or internal procedures having nuclear safety l
significance; I
i f.
All Licensee Event Reports required by 10 CFR 50.73; j
g.
Indications of significant unanticipated deficiencies in any aspect of design or operation of structures, systems, or i
components that could affect nuclear safety; h.
Significant accidental, unplanned, or uncontrolled radioactive releases, including corrective actions to prevent recurrence; i.
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 k.
Audits and audit plans.
f Reports or records of these reviews shall be forwarded to the a
j PresidentandCEOwithin30daysfollowingcompletionofthereview.l 6
j AUDIT PROGRAM RESPONSIBILITIES 6.5.3.7 The NSAB audit program shall be the responsibility of the Audits and z
Evaluation Department. NSAB audits shall be performed at least once l
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; J
b.
The training and qualifications of the unit staff; c.
The implementation of all programs required by Specification 6.8; d.
The Fire Protection Program and implementing procedures.
e.
The fire protection equipment and program implementation utilizing either a qualified offsite license fire protection engineer or an outside independent fire protection consultant.
f.
Actions taken to correct deficiencies occurring in equipment, structures, systems, components, or method of operation.that affect nuclear safety; and g.
Other activities and documents as requested by the President and CEO.
Millstone Unit 2 6-11 Amendment No. 17 J), 77, 91, lif,111, lif,191,199, 206 osos
ADMINISTRATIVE CONTROLS l
RECORDS 6.5.3.8 Written records of reviews and audits shall be maintained. As a
[
minimum these records shall include:
a.
Results of the activities conducted under the provisions of Section 6.5.3; i
b.
Recommended approval or disapproval of items considered under j
Specifications 6.5.1.6.a through 6.5.1.6.d, and 6.8; and i
f 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 l
constitute an unreviewed' safety question as defined in 10 CFR 50.59.
l 6.5.4 Station Qualified Reviewer Proaram I
Function 6.5.4.1 The Unit 2 Unit Director or Millstone Unit 2 Recovery Officer or Senior Vice President and CN0 - Millstone may establish a Station 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.
Resnonsibilities 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 )rocedures, programs, and changes thereto when organizations otier than the presaring organization are affected by the procedure, program, or c1ange.
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 cosmiittee.
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.
)
i Millstone Unit 2 6-12 Amendment Nos. JJ pp, pp, Jpf, Jp;, 206 0286 l
ADMINISTRATIVE CONTROLS e.
Provide for written recommendation by the Qualified Reviewer (s) to the responsible Manager for approval or disapproval of procedures and programs considered under Specification 6.5.1.6.a and 6.5.2.6.a and that the procedure or program was screened by a qualified individual and found not to require a 10 CFR 50.59 evaluation.
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 or SORC for I
review.
6.5.4.4 Personnel recommended to be Station Qualified Reviewers shall be designated in writing by the Unit 2 Unit Director or Millstone Unit 2 Recovery Officer or Senior Vice President and CN0 - Millstone for each procedure, program, or class of procedure or program within the scope of the Station Qualified Reviewer Program.
6.5.4.5 Temporary procedure changes shall be made in accordance with Specification 6.8.3 with the exception that changes to procedures for which reviews are assigned to Qualified Reviewers will be reviewed and approved as 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 nuclear power plant experience; OR c.
An equivalent combination of education and experience as approved by a Department Manager.
I l
Millstone Unit 2 6-13 Amendment Mos. Jpp,206 i
I oan
ADMINISTRATIVE CONTROLS 6.6 REPORTABLE EVENT ACTION 6.6.1 The following actions shall be taken for REPORTABLE EVENTS:
l 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 sita11 be submitted to the Chairperson of the NSAB and the Senior Vice President and CN0 - Millstone.
l 6.7 SAFETY LIMIT VIOLATION 6.7.1 The following actions shall be taken in the event a Safety Limit is 3
violated:
a.
The unit shall be placed in at least HOT STANDBY within one hour.
q b.
The NRC Operations Center shall be notified by telephone as j
soon as possible and in all cases within I hour. The Senior Vice President and CN0 - Millstone and the Chairperson of the i
NSAB shall be notified within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />; c.
A Safety Limit Violation Report shall be prepared. The report shall be reviewed by the PORC. This report shall describe:
(1) applicable circumstances preceding the violation, (2) effects of the violation upon facility components, systems, 4
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 Senior Vice President and CN0 - Millstone 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 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.
J e.
Not dsed.
Millstone Unit 2 6-14 Amendment Nos. 5, #, M, 111, Hi,1H,1H,in,1H,206 om
g 1
i ADNINISTRATIVE CONTROLS l
f.
Fire Protection Program implementation.
g.
Quality Control for effluent monitoring using the guidance in Regulatory Guide 1.21 Rev.1, June 1974.
4 h.
Radiological Effluent Monitoring and Offsite Dose Calculation j
Manual (REMODCM) implementation, except for Section I.E.,
i Radiological Environmental Monitoring.
1 i
6.8.2 a.
The Unit 2 Unit Director or Millstone Unit 2 Recovery Officer or Senior Vice President and CN0 - Millstone may designate specific procedures and programs, or classes of procedures and programs to
>e reviewed in accordance with the Station Qualified Reviewer j
Program in lieu of review by the PORC or 50RC. Thereviewperthel Qua'ified Reviewer Program shall be in'accordance with Specification 6.5.4.
b.
Procedures and >rograms listed in Specification 6.8.1, and changes thereto, shall >e approved by the Unit 2 Unit Director or Senior i
Vice President and CN0 - Millstone or by cognizant Manager or i
Directors who are designated as the Approval Authority by the Unit 2 Unit Director or Senior Vice President and CN0 - Millstone, as specified in administrative procedures. The Approval Authority i
for each procedure and program or class of procedure and program j
shall be specified in administrative procedures.
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 2 Unit Director or Senior Vice President and CN0 - Millstone, i
or be reviewed and approved in accordance with the Station j
Qualified Reviewer Program, prior to implementation.
Each procedure of Specification 6.8.1 shall be reviewed periodically as set forth in administrative procedures.
i 6.8.3 Temporary changes to procedures of 6.8.1 above may be made provided:
a.
The intent of original procedure is not altered.
b.
The change is approved by two members of the plant management staff, at least one of whom holds a Senior Reactor Operator's License on the unit affected.
c.
The change is documented, reviewed by the PORC or SORC, or the l
Station Qualified Reviewer Program as applicable, and approved by the Unit 2 Unit Director or Senior Vice President and CN0 -
Millstone or Station Qualified Reviewer Program Department Manager 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 2 6-15 Amendment Mos. #, S. #, J #,
1H,1#,193, 206
d ADMINISTRATIVE CONTROLS 6.15 RADIOLOGICAL EFFLUENT MONITORING AND OFFSITE DOSE CALCULATION MANUAL l
(REM 0DCM)
Section I, Radiological Effluents Monitoring Manual (REMM), shall outline the sampling and analysis programs to determine the concentration of radioactive materials released offsite as well as dose commitments to individuals in those exposure pathways and for those radionuclides released as a result of station operation.
It shall also specify operating guidelines for radioactive waste treatment systems and report content.
Section II, the Offsite Dose Calculation Manual (ODCM), shall describe the methodology and parameters to be used in the calculation of offsite doses due 1
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.
)
I Changes to the REMODCH:
a.
Shall be documented and records of reviews performed shall be retained as required by Specification 6.10.2m. This documentation shall contain:
1)
Sufficient information to support the change together with the appropriate analyses or evaluations justifying the change (s),
and 2)
A determination that the change will maintain the level of radioactive effluent control required by 10 CFR 20.106, 40 CFR Part 190,10 CFR 50.36a, and Appendix I to 10 CFR Part 50 and not adversely impact the accuracy or reliability of effluent, dose, or setpoint calculations.
b.
Shall become effective after review and acceptance by SORC and the approval of the Senior Vice President and CN0 - Millstone.
l c.
Shall be submitted to the Commission in the form of a complete, legible copy of the entire REM or ODCM, as appropriate, as a part of or concurrent with the Annual Radioactive Effluent Report for the period of the report in which any change was made.
Each change shall be identified by markings in the margin of the affected pages, clearly indicating the area of the page that was changed, and shall indicate the date (e.g., month / year) the change was implemented.
Millstone Unit 2 6-24 Amendment No. JJ7, JJ7, JJJ.177, 206 0286
- 1 p%Kttg g"
d UNITED STATES j
,j NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20565-0001 o,s,...../
NORTHEAST NUCLEAR ENERGY COMPANY. ET AL.
DOCKET NO. 50-423 MILLSTONE NUCLEAR POWER STATION. UNIT N0. 3 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.135 License No. NPF-49 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Northeast Nuclear Energy Company, et al. (the licensee) dated February 3,1997, complies with the i
standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations set forth in 10 CFR Chapter I; B.
The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C.
There is reasonable assurance (i) that the activities authorized by this anendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; l
D.
The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; j
and E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.
w
4 2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. NPF-49 is hereby amended to read as follows:
(2)
Technical Soecifications The Technical Specifications contained in Appendix A, as revised through Amendment No.
135, and the Environmental Protection Plan contained in Appendix B, both of which are attached hereto are hereby incorporated in the license.
The licensee shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
3.
This license amendment is effective as of the date of its issuance, to be implemented within 60 days of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION fY Phillip F. McKee Deputy Director for Licensing Special Projects Office Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance:
April 10,1997 c
. _ =
ATTACHMENT TO LICENSE AMENDMENT NO.135 FACILITY OPERATING LICENSE NO. NPF-49 DOCKET NO. 50-423 Replace the following pages of the Appendix A, Technical Specifications, with the attached pages. The revised pages are identified by amendment number and con'.ain vertical lines indicating the areas of change.
Remove Insert 2
6-1 6-1 6-4 6-4 6-5 6-5 6-6 6-6 6-7 6-7 6-8 6-8 6-9 6-9 6-10 6-10 6-11 6-11 4
6-12 6-12 6-13 6-13 6-14 6-14 6-15 6-15 6-24 6-24 4
4 l
l 4
I:
_i ADNINISTRATIVE CONTROLS 6.1 RESPONSIBILITY 6.1.1 The Senior Vice President and Chief Nuclear Officer (CN0) - Millstone shall be responsible for overall operation of the Millstone Station site while
.the.Vice President - Millstone Unit 3 shall be responsible for overall unit safe operation and the Unit 3 Unit Director shall be responsible for operation of the unit. The Senior Vice President and CN0 - Millstone, Vice President -
Millstone Unit 3 and Unit 3 Unit Director shall each delegate in writing the succession to these responsibilities during their absence.
6.2 ORGANIZATION 6.2.1 0FFSITE AND ONSITE ORGANIZATIONS Onsite and offsite organizations shall be established for unit operation and corporate management, respectively. The onsite and offsite organizations shall include the positions for acti'Jities affecting the safety of the nuclear power plant.
- a. Lines of authority, responsibility, and communication shall be established and defined for the highest management levels through intermediate levels to and including all operating organization positions. These relationships shall be documented and updated, as appropriate, in the form of organization charts, functional descrip-tions of departmental responsibilities and relationships, and job descriptions for key personnel positions, or in equivalent forms of documentation. These requirements shall be documented in the Quality Assurance Topical Report.
- b. The Vice President - Millstone 'Jnit 3 shall be responsible for l
overall unit safe operation and shall have control over those onsite activities necessary for safe operation and maintenance of the plant.
i i
- c. The Senior Vice President and CN0 - Millstone shall have corporate l
responsibility for overall plant nuclear safety and shall take any measures needed to ensure acceptable performance of the staff in operating, maintaining, and providing technical support to the plant to ensure nuclear safety.
- 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; MILLSTONE - UNIT 3 6-1 Amendment No. 77,77,77,135 0471
J anasturRTRAffVr enarrant t 1
6.2.3 INDEPENDENT SAFETY ENGINEERING GROUP fISEG)
FUNCTION j
6.2.3.1 The ISEG shall include, as part of its function, examination of unit l
operating characteristics, NRC issuances, industry advisories, Licensee Event
. Repotts, and other sources of unit design and operating experience information, including units of similar design, which may indicate areas for improving unit safety. The ISEG shall make detailed reconnendations for revised procedures, equipment modifications, maintenance activities, operations activities, or other means of improving unit safety to appropriate j
station / corporation management.
j COMPOSITION 6.2.3.2 The ISEG shall be composed of at least four full-time personnel i
located on site to perform the functions described in 6.2.3.1 for Millstone l
Unit 3.
Each person shall have either:
(1) A bachelor's degree in engineering or related science and at least 2 years of professional level experience in his field, at least 1 year of which j
experience shall be in the nuclear field, or, (2) At least 10 years of professional level experience in his field, at least j
5 years of which experience shall be in the nuclear field.
l A minimum of 50% of these personnel shall have the qualifications specified in (1) above.
j RESPONSIBILITIES 6.2.3.3 The ISEG shall be responsible for maintaining surveillance of unit
.l activities to provide independent verification
- that these activities are 9
{
1rformed correctly and that human errors are reduced as much as practical.
i i
RECORDS l
6.2.3.4 Records of activities performed by the ISEG shall be prepared and
)
i maintained, and quarterly reports of completed safety evaluations will be made j
l to the Vice President-Nuclear Oversight.
l i
{
6.2.4 SHIFT TECHNICAL ADVISOR l
i 6.2.4.1 The Shift Technical Advisor shall provide advisory technical support to I
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 1
or engineering discipline and shall have received specific training in the i
response and analysis of the unit for transients and accidents, and in unit 1
design and layout, including the capabilities of instrumentation and controls in i
the control room.
I e
- Not responsible for sign-off function.
I NILLSTONE - UNIT 3 6-4 Amen 0:nont No. JJ, 77,135 j
0472 l
l
4 ADMINISTRATIVE CONTROLS i
6.3 FACILITY STAFF QUALIFICATIONS a*
6.3.1 Each member of the facility staff shall meet or exceed the minimum qualifications of ANSI N18.1-1971 for comparable positions, except for:
4 i
a.
If the Operations Manager does not hold a senior reactor operator l
license for Millstone Unit No. 3, then the Operations Manager shall have l
held a senior reactor operator license at a pressurized water reactor, i
4 j
. and the Assistant Operations' Manager shall hold a senior reactor
]
operator license for Millstone Unit No. 3.
i b.
The Health Physics Manager shall meet or exceed the qualifications of i
j Regulatory Guide 1.8, Revision 1, May 1977.
~
i 6.4 TRAINING 6.4.1 A retraining and replacement training program for the facility staff shall be maintained under the direction of the Senior Vice President and CN0 -
Millstone and shall meet or exceed the requirements and recomendations of Section 5.5 of ANSI N18.1-1971 and 10 CFR Part 55.59. The Director-Nuclear Training has the overall responsibility for the implementation of the Training Program.
6.4.2 Deleted.
6.5 REVIEW AND AUDIT 6.5.1 PLANT OPERATIONS REVIEW COMMITTEE (PORC)
FilNCTION 6.5.1.1 The PORC shall function to advise the Unit 3 Unit Director on all l
matters related to nuclear safety.
1 COMPOS 1110R 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 i
Reactor Engineering j
Maintenance 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, 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 3 Unit Director. The Chairperson and alternate l
Chairperson of the PORC shall be drawn from the PORC members and be appointed in writing by the Unit 3 Unit Director.
l.
NILLSTONE - UNIT 3 6-5 Amendment No. 77, pp, pp, pp, pp 135 wa 119,111
a ADMINISTRATIVE CONTROLS ALTERNATES l
6.5.1.3 All alternate members shall be appointed in writing by the PORC Chairperson to serve on a temporary basis;bers in MRC activities at any one however no more than two j
alternates shall participate as voting mem time.
MEETING FREQUENCY
'6.5.1.4 The PORC shall meet at least once per calendar month and as convened l
by the PORC Chairperson.
l M
I 6.5.1.5 The quorum of the PORC shall consist of the Chairperson or Vice
]
Chairperson and four members including alternates.
l RESPONSIBILITIES l
6.5.1.6 The PORC shall be responsible for:
Review of:
1 all procedures, except common site procedures, required by(Sp)ecification 6.8 and changes thereto a.
exceptcommonsiteprgramsrequiredbySpecification)6.8andall programs, 2
changes thereto, and 3 any other proposed procedures, programs or i
changes thereto as de er) mined by the Unit 3 Unit Director to affect l nuclear safety.
Procedures and programs required by Specification 6.8 that are designated for review and approval by the Station Qualified Reviewer Program do not require PORC review.
b.
Review of all proposed tests and experiments that affect nuclear safety; c.
Review of all proposed changes to Sections 1.0-5.0 of these Technical Specifications; d.
Review of all proposed changes or modifications to plant systems or equipment that affect nuclear safety; Investigation of all viclations of the Technical Specifications,lua-
)
e.
including the preparation and forwarding of reports covering eva tion and recommendations to prevent recurrence, to the Senior Vice President and CNO - Millstone Vice President - Millstone Unit 3 and totheChairpersonoftheNuclearSafetyAssessmentBoard; j
f.
Review of all REPORTABLE EVENTS-g.
Review of facility operations to detect potential safety hazards; h.
Performance of special reviews, investigations, or analyses and reports thereon as requested by the Chairperson of the Nuclear Safety Assessment Board or the Senior Vice President and CN0 -
Millstone or Vice Presideat - Millstone Unit 3; and j
l 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 safety question, or requires a significant hazards consideration determination.
MILLSTONE - UNIT 3 6-6 Amendment No. 7J. 77, 77, PP, JPJ, 177,135 om
~
l ADMINISTRATIVE CONTROLS 4
.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 3 Uni
- Director written approval or l
disapproval of items considered under Specification 6.5.1.6a.
through d. above; and b.
Provide written notification to the Senior Vice President and CNO - Millstone Vice President - Millstone Unit 3 and the Chairperson of Ihe Nuclear Safety Assessment Board of disagreement between the PORC and the Unit 3 Unit Director; however, the Unit 3 Unit Director shall have responsibility for resolution of such disagreements pursuant to Specification 6.1.1.
RECORDS 6.5.1.8 The PORC shall maintain wr atten minutes of each meeting and copies shall be provided to the Senior Vice President and CNO - Millstone and the l
Chairperson of the Nuclear Safety Assessment Board.
J J A. SITE OPERATIONS REVIEW COMMITTEE (SORC)
FUNCTION 6.5.2.1 The SORC shall function.to advise the Senior Vice President and CN0 - Millstone on all matters related to nuclear safety of the entire i
Millstone Station Site.
COMPOSITION 6.5.2.2 The SORC shall be composed of the:
Chairperson:
Senior Vice President and CNO - Millstone Member:
Director,it DirectorUnit Operations Member:
Unit 2 Un a it 3 Unit Director l
Member:
n Nuclear Services Member:
Jirector, General Services
-Member:
Mana er, d Member of Unit 1 PORC Member:
Desi nate Member:
Desi nated Member of Unit 2 PORC Membes:
Desi nated Member of Unit 3 PORC Memy :
Desi nated Member of Nuclear Oversight l
The Senior Unit Director / Director, Unit Operations in attendance shall j
be the Vice Chairperson.
l MILLSTONE - UNIT 3 6-7 Amendment No. pp, pp, 19f. U p, m1 Hp,135 j
l
i ADMINIsrRATIVE CONTROLS ALTERNATES 6.5.2.3 Alternate members shall be appointed in writing by the 50RC Chairperson to serve on a temporary basis; however, no more than two alternates shall participate in SORC activities at one time.
MEETING FREQUENCY j
6.5.2.4 The 50RC shall meet at least once per 6 months and as convened by 4
the SORC Chairperson.
1 000 RUM 6.5.2.5 A quorum of the 50RC shall consist of the Chairperson or Vic'e i
Chairperson and five members including alternates.
e l
RESPONSIBILITIES
]
6.5.2.6 The SORC shall be responsible for:
j a.
Review of (d) changes thereto, (2)th 1 all common site procedures required by Specifica-tion 6.8 an all common site programs, required by Specification 6.8 and changes
- ereto, procedures, progreas, or changes thereto as(3) any other pro)oseddetermined by i
1 Vice President and CNO - Millstone to affect site nuclear safety.
l i
Common site programs and procedures required by Specification 6.8 1
that are designated for review and approval by the Station Qualified l
Reviewer Program do not require SORC review.
b.
Review of all roposed chan Controls" oft $eseTechnica$estoSection6.0" Administrative Specifications; c.
Performance of special reviews and investigations and reports as requested by the Chairperson of the Nuclear Safety Assessment Board; j
d.
Not used.
j e.
Not used.
l f.
Review of all common site proposed tests and experiments that affect nuclear safety; l
I 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
)
i considered under Specification 6.5.2.6(59 or 10CFR50.92 const-a) through (g) above appropriate and as provided by 10CFR50.
atos an unreviewed safety question or requires a significant hazards consideration determination.
i 1.
Review of the common site Fire Protection Program and implementing procedures.
i i
i
~
i AmendmentNo.pg,pp.PP,JPF,177 j
NILLSTONE - UNIT 3 6-8 119e
)
un
1 ADMINISTRATIVE CONTROLS AUTADRITY 4
i j
6.5.2.7 The 50RC shall:
a.
Reconnend to the Senior Vice President and CN0 - Millstone written l
approval or disapproval in meeting minutes of items considered under Specification 6.5.2.6(a) through (g) above, and i
b.
Provide immediate written notification or meeting minutes to the President and Chief Executive Officar (CE0)'and the Chairperson of the Nuclear Safety Assessment Board of disagreement between the SORC l and the Senior Vice President and CNO - Millstone; however, the l
Senior Vice President and CN0 - Millstone shall have responsibility l
for resolution of such disagreements pursuant to 6.1.1 above.
RECORDS 6.5.2.8 The 50RC shall maintain written minutes of ;ach meeting and copies shall be provided to the Senior Vice President and CN0 - Millstone and l
Chairperson of the Nuclear Safety Assessment Board.
i 6.5.3 NUCLEAR SAFETY ASSESSMENT BOARD (NSAB)
FUNCTION 6.5.3.1 The minimum qualifications of NSAB members are as follows:
a.
The Chairperson and NSAB members shall have:
1)
An academic degree in an engineering or physical science field, or hold a senior management position, and 2)
A minimum of five years technical experience in their respective field of expertise.
b.
The NSAB shall have experience in and shall function to provide independent oversight review and audit of designated activities in' the areas of:
1)
Nuclear power plant operations; 2)
Nuclear engineering; 3)
Chemistry and radiochemistry; 4)
Metallurgy; 5)
Instrumentation and control; 6)
Radiological safety; NILLSTONE - UNIT 3 6-9 Amendment No. JJ, pp, PP, JPJ, 177,135 0472
l i
ADMINISTRATIVE CONTROLS i.
7)
Nechanical and electrical engineering; and l
8)
Quality assurance practices.
j i
The NSAB serves to advise the President and CEO on matters related to nuclear safety and notify the President and CEO within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> of a safety significant i
disagreement between the NSAB and the organization or function being reviewed.
J COMPOSITION
)
6.5.3.2 The President and CEO shall appoint, in writing, a minimum of seven l
members to the NSAB and shall designate from this membership, in writing, a Chairperson and a Vice Chairperson. The membership shall function to provide j
independent review and audit in the areas listed in Specification 6.5.3.1.
ALTERNATES 1
6.5.3.3 All alternate members shall be appointed, in writing, by the President and CE0; however, no more than two alternates shall participate as l
).
members in NSAB activities at any one time.
i MEETING FREQUENCY f
6.5.3.4 The NSAB shall meet at least once per calendar quarter.
OUORUM
{
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 i
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.
l REVIEW RESPONSIBILITIES l
6.5.3.6 The NSAB shall be responsible for the review of:
}
a.
The safety evaluations for changes to procedures, equipment, or systems, and tests or experiments completed under the provisions of 10 CFR 50.59, to verify that such actions did not constitute an i
unreviewed safety question as defined in 10 CFR 50.59; b.
Proposed changes to procedures, equipment, or systems that involve j
an unreviewed safety question as defined in 10 CFR 50.59; 1
i c.
Proposed tests or experiments that involve an unreviewed safety question as defined in 10 CFR 50.59; 1
i i
NILLSTONE - UNIT 3 6-10 Amendment No. 77, 77, 177, 177, 135 0472 1
- h. -.. -
~
ADMINISTRATIVE CONTROLS d.
Proposed changes to Technical Specifications and the Operating License; e.
Violations of applicable codes, regulations, orders, license requirements, or internal procedures having nuclear safety significance; f.
All Licensee Event Reports required by 10 CFR 50.73; g.
Indications of significant unanticipated deficiencias in any aspect of design or operation of structures, systems, or components that could affect nuclear safety; h.
Significant accidental, unplannec, or uncontrolled radioacti.ve releases, including corrective actions to prevent recurrence; i.
Significant operating abnormalities or deviations from normal and expected performance of equipment that could affect nuclear safety; j.
The performance of the corrective action program; and k.
Audits and audit plans.
Reports or records of these reviews shall be forwarded to the President and CEO l
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 Audits and Evaluation Departiaent. NSAB audits shall be performed at least once per i
24 months in accordance with Nuclear Group Procedures and shall encompass:
a.
The conformance of unit operation to provisions contained within the Technical Specifications and applicable license conditions; b.
The training and qualifications of the unit staff; c.
The impit. mentation 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.
f.
Actions taken to correct deficiencies occurring in equipment, structures, systems, components, or method of operation that affect nuclear safety; and g.
Other activities and documents as requested by the President'and CEO.
NILLSTONE - UNIT 3 6-11 Amendment No. JJ, 17, 77, pp.
om 197. J/J,135
l ADNINISTRATIVE CONTROLS i
1 l,
RECORDS 6.5.3.8 Written records of reviews and audits shall be maintained. As a minimum these records shall. include:
l a.
Results of the activities conducted under the provisions of Section 6.5.3; i
' b.
Recommended approval or disapproval of items considered under j
Specifications 6.5.1.6.a through 6.5.1.6.d, and 6.8; and c.
Determination as to whether each item considered under Specification 6.5.1.6.a. 6.5.1.6.b, 6.5.1.6.d, and 6.8 constitute an uiireviewed safety question as defined in 10 CFR 50.59.
1 j
6.5.4 Station Qualified Reviewer Proaran l
Function 6.5.4.1 The Unit 3 Unit Director or Vice President Millstone Unit 3 or Senior Vice President and CNO - Millstone may establish a Station Qualified Reviewer Program whereby required reviews of designated procedures or classes of procedures required by Specifications 6.5.1.6.a and 6.5.2.6.a are performed by Station Qualified Reviewers and approved by designated managers. These reviews are in lieu of reviews by the PORC or SORC. However, procedures which require a 10 CFR 50.59 evaluation must be reviewed by the PORC or 50RC.
Responsibilities 6.5.4.2 The Station Qualified Reviewer Program shall:
a.
Provide for the review of designated procedures, programs, and i
changes thereto by a Qualified Reviewer (s) other than the individual who prepared the procedure, program, or change.
b.
Provide for cross-disciplinary review of procedures, programs, and changes thereto when organizations other than the preparing organization are affected by the procedure, program, or change.
c.
Ensure cross-disciplinary reviews are performed by a Qualified Reviewer (s) in affected disciplines, or by other persons designated by cognizant Managers or Directors as having specific expertise required to assess a particular procedure, program, or change.
Cross-disciplinary reviewers may function as a committee.
d.
Provide for a screening of designated procedures, programs and changes thereto to determine if an evaluation should be performed in accordance with the provisions of 10 CFR.50.59 to verify that an unreviewed safety question does not exist. This screening will be performed by personnel trained and qualified in performing 10 CFR 50.59 evaluations.
NILLSTONE - UNIT 3 6-12 Amendment No. 17,77,77,77,J7f an ng,135
j ADMINISTRATIVE CONTROL 5 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 l
and that the procedure or program was screened by a qualified i
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, i
'or change thereto requires a 10 CFR 50.5g evaluation, that Manager will ensure i
the required evaluation is performed to determine if the new procedure, program, i
or change involves an unreviewed safety question. The new procedura, program, 1
i or change will then be forwarded with the 10 CFR 50.59 evaluation to PORC or j
SORC for review.
6.5.4.4 Personnel recommended to th Station Qualified Reviewers shall be l
designated in writing by the Unit 3 Unit Director or Vice President - Millstone i
Unit 3 or Senior Vice President and CN0 - Millstone for each procedure, program, or class of procedure or program within the scope of the Station Qualified i
Reviewer Program.
6.E.4.5 Temporary procedure changes shall be made in accordan~ce with i
Specification 6.8.3 with the exception that changes to procedures for which reviews are assigned to Qualified Reviewers will oe reviewed and approved as described in Specification 6.5.4.2.
5 Ef&D.tdi 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 Qualification 6.5.4.7 The training and qualification requirements of personnel designated
)
as a Qualified Reviewer in accordance with the Station Qualified Reviewer l
Program shall be in accordance with administrative procedures. Qualified reviewers shall have:
a.
A Bachelors degree in engineering, related science, or technical discipline, and two years of nuclear power plant experience; OR
~ b.
Six years of nuclear power plant experience; OR c.
An equivalent combination of education and experience as approved by a Department Manager.
4 4
NILLSTONE - UNIT 3 6-13 Amendment No. JJ),135 0472
+
l i
ADMINISTRATIVE CONTROLS i
(
i l
6.6 REPORTABLE 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 j
to the requirements of Section 50.73 to 10 CFR Part 50, and i
b.
Each REPORTABLE EVENT shall be reviewed by the PORC and the results of this review shall be submitted to the Chairperson of the NSAB and the Senior Vice President and CN0 - Millstone.
l 6.7 SAFETY LIMIT VIOLATION l
i 6.7.1 The following actions shall be taken in the event a Safety Limit is violated:-
t a.
The Unit shall be placed in at least HOT STANDBY within one hour.
b.
The NRC Operations Center shall be notified by telephone as soon as possible and in all cases within I hour. The Senior Vice President and CNO - Millstone and the chairperson of the NSAB shall be notified within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />; 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 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 Conurfssion, the Chairperson of the NSAB, and the Senior Vice Prr.sident and CNO - Millstone within 14 days of the violation; and j
e.
Operation shall not be resumed until authorized by the Commission.
6.8 PROCEDURES AND PROGRAMS 6.8.1 Written procedures shall be established, implemented, and maintained covering the activities referenced below:
a.
The applicable procedures recommended in' Appendix A of Regulatory Guide 1.33, Revision 2, February 1978; b.
The applicable procedures required to implement the requirements of NUREG-0737 and supplements thereto; c.
Refueling operations; d.
Surveillance activities of safety related equipment; e.
Not used.
MILLSTONE - UNIT 3 6-14 Amendment No. 77, 77, JPF, J7J, om 177,135 I
r-
j I
e ADMINISTRATIVE CONTROLS l
\\
.l f.
Not used.
g.
Fire Protection Program implementation; 4
h.
Quality controls for effluent monitoring, using the guidance in Regulatory Guide 1.21, Rev.1, June 1974; and i.
Radiological Effluent Monitoring and Offsite Dose Calculation Manual (REMODCM) implementation except for Section I.E.
Radiological Environmental Monitoring.
i 6.8.2 a.
The Unit 3 Unit Director or Vice President - Millstone Unit 3 or i
Senior Vice President and CNO - Millstone may designate specific procedures and programs, or classes of procedures and programs to be reviewed in accordance with the Station Qualified Reviewer Program in lieu of review by the PORC or SORC. Thereviewperthel Qualified Reviewer Program shall be in accordance with Specification 6.5.4.
b.
Procedures and programs listed in Specification 6.8.1, and changes thereto, shall be approved by the Unit 3 Unit Director or Senior Vice President and CN0 - Millstone or by cognizant Manager or Directors who are designated as the Approval Authority by the Unit 3UnitDirectororSeniorVicePresidentandCN0-Millstone,l 4
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 3 Unit Director or Senior Vice President and CNO - Millstone, i
or be reviewed and approved in accordance with the Station Qualified Reviewer Program, prior to implementation.
Each procedure of Specification 6.8.1 shall be reviewed periodically as set forth in administrative procedures.
6.8.3 Temporary changes to procedures of Specification 6.8.1 may be made provided:
a.
The intent of the original procedure is not altered; b.
The change is approved by two members of the plant management staff, at least one of whom holds a Senior Operator license on the unit affected; and c.
The change is documented, reviewed by the PORC or SORC or Station l
Qualified Reviewer Program, as appropriate, and approved by the Station Qualified Reviewer Program Department Manager or Unit 3 Unit Director or Senior Vice President and CNO - Millstone within 14 days of implementation.
MILLSTONE - UNIT 3 6-15 Amendment No. JJ, 77, 17), J17,135 0472
~,
ADMINISTRATIVE CONTROLS 6.13 RADIOLOGICAL EFFLUENT MONITORING AND 0FFSITE DOSE CALCULATION MANUAL fREMODCM)
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 operation. It shall also specify operating guidelines for radioactive waste treatment systems and report content.
Section II, the Offsite Dose Calculation Manual (00CM), shall describe the methodology and parameters to be used in the calculation of offsite doses due to radioactive gaseous and liquid effluents and in the calculations of gaseous and liquid effluent monitoring instrumentation alarsVtrip setpoints consistent with the applicable LCOs 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 6.10.30. 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 radioactive effluent control required by 10 CFR 20.106, 40 CFR Part 190, 10 CFR 50.36a, and Appendix I to 10 CFR Part 50 and not adversely impact the accuracy or reliability of effluent, dose, or setpoint calculations.
b.
Shall become effective after review and acceptance by SORC and the approval of the Senior Vice President and CN0 - Millstone.
l Shall be submitted to the Commission in the form of a complete, legible copy of c.
the entire REM or ODCM, as appropriate, as a part of or concurrent with the Annual Radioactive' Effluent Report for the period of the report in which 'any change was made.
Each change shall be identified by markings in the margin of the affected pages, clearly indicating the area of the page that was changed, and shall indicate the date (e.g., month / year) the change was implemented.
6.14 RADIOACTIVE WASTE TREATMENT Procedure: 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 the use of appropriate waste treatment systems utilizing the guidance provided in the REMODCM.
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. Jp, 77, 77, pp,135 0473 l
.