ML20141K416

Amend 191 to License DPR-61,changing Administrative Controls Section of TSs as Needed to Implement Revised Mgt Responsibilities & Titles That Reflect Permanently Shut Down Status of Plant

ML20141K416
Person / Time
Site:	Haddam Neck File:Connecticut Yankee Atomic Power Co icon.png
Issue date:	05/22/1997
From:	Mendonca M NRC (Affiliation Not Assigned)
To:
Shared Package
ML20141K409	List: ML20141K407 ML20141K416 ML20141K420
References
NUDOCS 9705290089
Download: ML20141K416 (13)

Text

}

t UNITED STATES

, g j NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20086-0001

...../ ,

l CONNECTICUT YANKEE ATOMIC POWER COMPANY I DOCKET NO. 50-213  !

HADDAM NECK PLANT AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 191 License No. DPR-61

1. The Nuclear Regulatory Comission (the Comission) has found that-l A. The application for amendment by Connecticut Yankee Atomic Power Company (the licensee) dated December 24, 1996, with the addendum of -1 January 31, 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; l

B. The facility will operate in conformity with the application, the I provisions of the Act, and the rules and regulations of the {

Comission; l 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 Comission's regulations; D. The issuance of this amendment will not be inimical to the comon f 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 Comission's regulations and all applicable requirements have been satisfied.

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. OPR-61 is hereby amended to read as follows:

(2) Technical Soecifications The Technical Specifications contained in Appendix A, as revised through Amendment No.191, are hereby incorporated in the license.

The licensee shall operate the facility in accordance with the Technical Specifications.

9705290089 970522 i PDR ADOCK 05000213 P PDR

_ _ . _ . . _ _ _ . _ _ _ _ _ _ ~ - _ _ _ _ _ . . _ __ _ - _ _

l l

1

- 2 -

i 3. This license amendment is effective as of the date of issuance, to be i implemented within 60 days of issuance.

FOR THE NUCLEAR REGULATORY COMMISSION

& m l

Marvin M. Mendonca, Acting Director Non-Power Reactors ard Decommissioning l Project Directorate

' Division of Reactor Project Management Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical Specifications

! Date of Issuance: May 22, 1997 l

i l

l l

l

l l

l I

l ATTACHMENT T0 LICENSE AMENDMENT NO, 191 FACILITY OPERATING LICENSE NO. OPR-61 DOCKET NO. 50-213 I I I

Replace the following pages of the Appendix A, Technical Specifications, with the attached pages. The revised pages are identified by amendment number and i contain vertical lines indicating the areas of change. j

Remove Insert 6-1 6-1 6-5 6-5 l

6-6 6-6 6-7 6-7 I 6-8 6-8 6-9 6-9 6-10 6-10 6-11 6-11

6-12 6-12 I l 6-20 6-20 I l

I l

I f

6.0 ADMINISTRATIVE CONTROLS 6.1 RESPONSIBILITY 6.1.1 The Executive Vice President and Chief Nuclear Officer shall be responsible for overall facility operation and shall delegate, in writing, the l succession to this responsibility during his absence.

6.2 ORGANIZATION 6.2.1 ONSITE AND OFFSITE ORGANIZATIONS '

Onsite and offsite organizations shall be established for unit operation and corporate management, respectively. The onsite and offsite organizations shall inc'lude the positions for activities affecting the safety of the l 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 descriptions of departmental responsibilities and relationships, and job descriptions for key personnel positions, or in equivalent forms of documentation. These requirements shall be documented in the Quality Assurance Topical Report.

b. The Unit Director shall be responsible for overall unit safe l

, operation and shall have control over those onsite activities l necessary for safe operation and maintenance of the plant.

c. The Executive Vice President and Chief Nuclear Officer, shall have corporate responsibility for overall plant nuclear safety and shall l take any measures needed to ensure acceptable performance of the staff in operating, maintaining, t.nd providing technical support to

the plant to ensure nuclear safety.

I

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

6.2.2 FACILITY STAFF

a. Each on-duty shift shall be composed of at least the minimum shift crew composition shown in Table 6.2-1;

b. At least one licensed Operator shall be in the control room when

! fuel is in the reactor. In addition, while the facility is in MODE 1, 2, 3 or 4, at least one licensed Senior Operator shall be in the control room; j!

HADDAM NECK . 6-1 Amendment No. JJJ, JJJ, JJJ. 191 C410

s ADMINISTRATIVE CONTROLS i

f. Successful completion of the Thames Valley State Technical College associate's degree in Nuclear Engineering Technology program, provided that the individual was enrolled in the program by October 1, 1987.

2. Dedicated STA: Must meet the STA training criteria of NUREG-0737, Item I.A.I.1, and have received specific training in plant design, and response and analysis of the plant for transients and accidents.

6.4 TRAINING A retraining and replacement training program for the facility staff shall be maintained under the direction of the Nuclear Unit Director and shall meet or exceed the requirements and recommendations of Section 5.5 of ANSI N18.1-1971 and 10CFR55.59. The Director-Nuclear Training has the overall responsibility for the implementation of the Training Program.

l 6.5 REVIEW AND AQQ[I 6.5.1 PLANT OPERATIONS REVIEW COMMITTEE (PORC) i FUNCTION 6.5.1.1 The PORC shall function to advise the Unit Director on all matters related to nuclear safety. l COMPOSITION 6.5.1.2 The PORC shall be composed of at least eleven members. Members shall collectively have experience and expertise in the following areas:

Plant Operations Engineering Reactor Engineering Mechanical Maintenance Electrical Maintenance Instrumentation and Controls Health Physics Work Planning and Control Quality Services Security Chemistry The minimum qualifications of PORC members shall be that all members have an academic degree in an engineering or physical science field, or hold a management position, and have a minimum of five years technical experience in their respective field of expertise. The members of PORC shall be appointed in writing by the Unit Director, who is the PORC Chairperson. The alternate ChairpersonsofthePORCshallbedrawnfromthePORCmembersandbeappointedl in writing by the Unit Director.

l HADDAM NECK 6-5 Amendment No. JJJ,JJJ JJJ JJJ.

04:s 77),JJJ,191

. I ADNINISTRATIVE CONTROLS ALTERNATES 6.5.1.3 All alternate members shall be appointed in writing by the PORC Chairperson to serve on a temporary basis; however, no more than two alternates shall participate as voting members in PORC activities at any one time.

MEETING FREQUENCY 6.5.1.4 The PORC shall meet at least once per calendar month and as convened by the PORC Chairperson or his/her designated alternate.

OV0 RUM 6.5.1.5 The quorum of the PORC shall consist of the Chairperson or his/her '

designated alternate and four members including alternates. i RESPONSIBILITIES 6.5.1.6 The PORC shall be responsible for:

a. Review of: (1) all procedures required by Specification 6.8 and changes thereto, and 2) any other proposed procedures or changes thereto as determined by the Unit Director to affect nuclear safety; l 3 b. Review of all proposed tests and experiments that affect nuclear

safety; I

c. Review of all proposed changes to the Technical Specifications;

d. Review of all proposed changes or modifications to plant systems j or equipment that affect nuclear safety;

e. Investigation of all violations of the Technical Specifications, j

including the preparation and forwarding of reports covering i

evaluation and recommendations to prevent recurrence, to the Executive Vice President and Chief Nuclear Officer and to the l Chairperson of the Nuclear Safety Assessment Board;

{ f. Review of all REPORTABLE EVENTS;

g. Review of facility operations to detect potential safety hazards; j h. Performance of special reviews, investigations or analyses and reports thereon as requested by the Chairperson of the Nuclear Safety Assessment Board or the Unit Director.

t HADDAM NECK 6-6 Amendment No. JJJ, JJJ JJ), Idi,191

j

ADMINISTRATIVE CONTROLS 4 .

i

i. Not used.

t j j. Not used.

j k. Review of the Fire Protection Program and Implementing Procedures.

AUTHORITY

{ 6.5.1.7 The PORC shall:

! a. Report to and be advisory to the Unit Director on those areas of l j responsibility specified in Section 6.5.1.6(a) through (k);

1 4

b. Render determinations in writing to the Unit Director if any item l  ;

j considered under Specification 6.5.1.6a. through d., above, as l appropriate and as provided by 10CFR50.59 or 10CFR50.92 constitutes i an unreviewed safety question or requires a significant hazards consideration determination.

c. Provide written notification, meeting minutes may be used for this I 4 purpose, to the Executive Vice President and Chief Nuclear Officer l

{ and the Chairperson of the Nuclear Safety Assessment Board of i

! disagreement between the PORC and the Unit Director; however, the Executive Vice President and Chief Nuclear Officer shall have responsibility for resolution of such disagreements pursuant to Specification 6.1.1.

!' RECORDS  !

! 6.5.1.8 The PORC shall maintain written sinutes of each meeting that, at a l l minimum, document the results of all PORC activities performed under the responsibility and authority provisions of these Technical Specifications.

j I A Copy shall be provided to the Chairperson of the Nuclear Safety Assessment

Board.

6.5.2 NUCLEAR SAFETY ASSESSMENT BOARD (NSAB)

FUNCTION 6.5.2.1 The minimum qualifications of NSAB members are as follows:

a. The Chairperson and NSAB members shall have:

1.- An academic degree in an engineering or physical science field, or hold a senior management position, and

2. A minimum of five years technical experience in their respective field of expertise.

HADDAN NECK 6-7 Amendment No. J7), Jpp, Jpp, J7),

uti JpJ Jpp, 191

- . - . .~ . .. -

. ADMINISTRATIVE CONTROLS b.

The NSAB shall have experience in and shall function to provide independent oversight review and audit of designated activities in the areas of:

1. Nuclear power plant operations;

2. Nuclear engineering;

3. Chemistry and radiochemistry;

4. Metallurgy;

5. Instrumentation and control; i

6. Radiological safety;

7. Mechanical and electrical engineering; and

8. Quality assurance practices.

The NSAB serves to advise the Executive Vice President and Chief Nuclear Officer on matters related to nuclear safety and notify the Executive Vice President and Chief Nuclear Officer 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 NSA8 and the organization or function being reviewed.

COMPOSITION 6.5;2.2 in writing, a minimum of seven members to the NSAB and shall desiThe Ex membership, in writing, a Chairperson and a Vice Chairperson. gna shall function6.5.2.1.

Specification to provide independent review and audit in the areas listed inThe membership ALTERNATES 6.5.2.3 All alternate members shall be appointed, in writing, by the Executive Vice President and Chief Nuclear Officer; however, no more than two alternates shall participate as members in NSAB activities at any one time.

tiEETING FREQUENCY 6.5.2.4 The NSAB shall meet at least once per calendar quarter.

000RW 6.5.2.5 The quorum of the NSAB shall consist of a majority of NSAB members including the Chairperson or Vice Chairperson. No more than a minority of the quorum shall have line responsibility for operation of the sama Northeast Utilities' nuclear unit. No ure than two alternates shall be appointed as members at any meeting in fulfillment of the quorum requirements, p NECK 6-8 Amendment No. JJJ. JJJ, JJJ. JJJ 191

ADMINISTRATIVE CONTROLS REVIEW RESPONSIBILITIES l

l 6.5.2.6 The NSAB shall be responsible for the review of:

a. The safety evaluations for changes to procedures, equipment, or systems, and tests or experiments completed under the provisions of 10 CFR 50.59, to verify that such actions did not constitute an unreviewed safety question as defined in 10 CFR 50.59;

b. Proposed changes to procedures, equipment, or systems that involve an unreviewed safety question as defined in 10 CFR 50.59;

c. Proposed tests or experiments that involve an unreviewed safety question as defined in 10 CFR 50.59;

d. Proposed changes to Technical Specifications and the Operating License;

e. Violations of applicable codes, regulations, orders, license requirements, or internal procedures having nuclear safety significance;

f. All Licensee Event Reports required by 10 CFR 50.73;

g. Indications of significant unanticipated deficiencies in any aspect of design or operation of structures, systems, or components that could affect nuclear safety;

h. Significant accidental, unplanned, or uncontrolled radioactive releases, including corrective actions to prevent recurrence;

i. Significant operating abnormalities or deviations from normal and expected performance of equipment that could affect nuclear safety;

j. The performance of the corrective action program; and

k. Audits and audit plans.

Reports or records of these reviews shall be forwarded to the Executive Vice President and Chief Nuclear Officer within 30 days following completion of the review.

AUDIT PROGRAM RESPONSIBILITIES 6,,5.2.7 The NSAB audit program shall be the responsibility of Nuclear Oversight organization. NSAB audits shall be performed at least once per 24 months in

accordance with Nuclear Group Procedures and shall encompass

l l a. The conformance of unit operation to provisions contained within the

' Technical Specifications and applicable license conditions; MADDAM NECK 6-9 Amendment No. JJJ, JJJ, JJJ,191 0411

l l

ADMINISTRATIVE CONTROLS I l

i l

I

b. The training and qualifications of the unit staff;

c. The implementation of all programs required by: Specification 6.8; l

d. The Fire Protection Program and implementing procedures; j 1

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 Executive Vico President and Chief Nuclear Officer.

RECORDS 6.5.2.8 Written records of reviews and audits shall be maintained. As a minimum these records shall include:

a. Results of the activities conducted under the provisions of Section 6.5.2;

b. Recommended approval or disapproval of items considered under Specifications 6.5.1.6.a through 6.5.1.6.d, and 6.8; and

c. Determination as to whether each item considered under Specification 6.5.1.6.a. 6.5.1.6.b, 6.5.1.6.d, and 6.8 constitute an unreviewed safety question as defined in 10 CFR 50.59, 6.6 REPORTABLE EVENT ACTION 6.6.1 The following actions shall be taken for REPORTABLE EVENTS:

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

b. Each REPORTABLE EVENT shall be reviewed by the PORC and the results of this review shall be submitted to the Chairperson of the NSAB and the Executive Vice President and Chief Nuclear Officer. l 6.7 SAFETY LIMIT VIOLATION 6.7.1 The following actions shall be taken in the event a Safety Limit is g violated: .

a. The unit shall be placed in at least HOT STANDBY within one hour.

HADDAM NECK 6-10 Amendment No. JJJ, JJJ JJJ,191 -

0411

.I 4

ADMINISTRATIVE C0ER0LS

- b. The NRC Operations Center shall be notified by telephone as soon as possible and in all cases within I hour. The Executive Vice President and Chief Nuclear Officer and the Chairperson of the NSAB i shall be notified within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />;

c. A Safety Limit Violation Report shall be prepared. The report shall i 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 i j action taken to prevent recurrence;  ;

d. The Safety Limit Violation Report shall be submitted to the 'I Commission, the Chairperson of the NSAB and the Executive Vice President and Chief Nuclear Officer within 14 days of the violation; i e. Operation will not be resumed until authorized by the Connission. I 6,8 PROCEDURES AND PROGRAMS 6.8.1 Written procedures and/or administrative policies shall be established, .

implemented, and maintained covering the activities referenced below:- -

l 1

HADDAN NECK . 6-11 Amendment No. JJJ. JJJ, JJJ,191 0411 i

7 ADMINISTRATIVE CONTROLS

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

b. The requirements and recoannendations of Sections 5.1 and 5.3 of ANSI N 18.7-1976.

c. Fire Protection Program implementation.

d. Quality controls for effluent monitoring, using the guidance in

- Regulatory Guide 1.21 Rev.1, June 1974.

e. RADIOLOGICAL EFFLUENT MONITORING AND OFFSITE DOSE CALCULATION MANUAL (REMODCM) implementation except for Section I.E, Radiological Environmental Monitoring.

f. PROCESS CONTROL PROGRAM implementation. i 6.8.2 Each procedure of S)ecification 6.8.1, and changes thereto, shall be l reviewed by the PORC and stall be approved by the Unit Director prior to l implementation and reviewed periodically as set forth in each document or in administrative procedures.

l 6.8.3 Temporary changes to procedures of Specification 6.8.1 may be made provided:

l

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 l c. The change is documented, reviewed by the PORC and approved by the j Unit Director within 14 days of implementation. l l 6.8.4 Written procedures shall be established, implemented and maintained covering Section I.E., Radiological Environmental Monitoring, of the REM 00CM.

6.8.5 All procedures and procedure changes required for the Radiological Environmental Monitoring Program of Specification 6.8.4 above shall be reviewed by an individual (other than the author) from the Radiological Assessment Branch or the Production Operation Services Laboratory (POSL) and approved by appropriate supervision.

Temporary changes may be made provided the intent of the original procedure is not altered and the change is documented and reviewed by an individual (other than the author) from the Radiological Assessment Branch or the POSL, within 14 days of implementation.

i l

i HADOAM NECK 6-12 Amendment No. JJJ, IJJ JJJ,191 i

~ , _ _ . _ . . - . . _ _

s ADMINISTRATIVE CONTROLS 6.13 RADIOLOGICAL EFFLUENT MONf10 RING AND OFFSITE DOSE i CALCULATION MANUAL (REM 0DCM) {

Section I, Radiological Effluents Monitoring Manual, shall outline the  !

sampling and analysis programs to determine the concentration of radioactive materials released offsite as well as dose comitments to individuals in those exposure pathways and for those radionuclides released as a result of facility operation. It shall also specify operating guidelines for RADIOACTIVE WASTE TREATMENT SYSTEMS and report content.

Section II, the Offsite Dose Calculation Manual, shall describe the methodology and parameters to be used in the calculation of offsite doses due to radioactive gaseous and liquid effluents and in the calculations of gaseous and liquid effluent monitoring instrumentation Alarm / Trip Setpoints consistent with the applicable LC0's contained in these Technical Specifications.

Changes to the REMODCH:

a. Shall be documented and records of reviews performed shall be retained as required by Specification 6.10.3.m. This documentation shall contain:

1) Sufficient information to support the change together with the appropriate analyses or evaluations justifying the change (s), and

2) A determination that the change will maintain the level of radioactive effluent control required by 10 CFR 20.106, 40 CFR Part 190,10 CFR 50.36a, and Appendix ; to 10CFR Part 50 and not adversely impact the accuracy or reliability of effluent, dose, or setpoint calculations,

b. Shall become effective after review and acceptance by PORC and the approval of the Unit Director. l

c. Shall be submitted to the Comission in the form of a complete, legible copy of the entire REMM or ODCM, as appropriate, as a part of or concurrent with the Annual Radioactive Effluent Report for the period of the report in which any change was made. Each change shall be identified by markings in the margin of the affected pages, clearly indicating the area of the page that was changed, and shall indicate the date (e.g.,

month / year) the change was implemented.

6.14 RADIOACTIVE WASTE TREATMENT Procedures for liquid and gaseous radioactive effluent discharges from the facility shall be prepared, approved, maintained and adhered to for all operations involving offsite releases of radioactive effluents. These procedures shall specify the use of appropriate RADIOACTIVE WASTE TREATMENT SYSTEMS utilizing the guidance provided in the REMODCM.

HADDAM NECK 6-20 Amendment No. JJ), Jp), JJp, ooit J79, 191

-