ML20083Q559
| ML20083Q559 | |
| Person / Time | |
|---|---|
| Site: | Seabrook  |
| Issue date: | 05/19/1995 |
| From: | Mckee P Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20083Q563 | List: |
| References | |
| NUDOCS 9505260047 | |
| Download: ML20083Q559 (9) | |
Text
A Eto ye UNITED STATES s
j NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20666 4001
%...../
NORTH ATLANTIC ENERGY SERVICE CORPORATION. ET Al*
DOCKET NO. 50-443 SEABROOK STATION. UNIT NO. 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 39 License No. NPF-86 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by North Atlantic Energy Service Corporation, et al. (the licensee), dated October 7,1994, 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; i
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 i
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.
- North Atlantic Energy Service Company (NAESCO) is authorized to act as agent for the: North Atlantic Energy Corporation, Canal Electric Company, The Connecticut Light and Power Company, Great Bay Power Corporation, Hudson Light and Power Department, Massachusetts Municipal Wholesale Electric Company, Montaup Electric Company, New England Power Company, New Hampshire Electric Cooperative, Inc., Taunton Municipal Light Plant, and The United Illuminating Company, and has exclusive responsibility and control over the physical construction, operation, and maintenance of the facility.
9505260047 950519 PDR ADOCK 05000443 P
, 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-86 is hereby amended to read as follows:
(2) Technical Soecifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 39, and the Environmental Protection Plan contained in Appendix B are incorporated into Facility License No.
NAESCO 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 t
Phillip F' cKee, Directo Project D rectorate I-3 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance:
May 19, 1995
ATTACHMENT TO LICENSE AMENDHENT NO. 39 FACILITY OPERATING LICENSE NO. NPF-86 DOCKET NO. 50-443 Replace the following pages of Appendix A, Technical Specifications, with the attached pages as indicated. The revised pages are identified by amendment number and contain vertic31 lines indicating the areas of change. Overleaf pages have been provided Remove Insert 6-7 6-7 6-8*
6-8*
6-9*
6-9*
6-10 6-10 6-11' 6-11*
6-12 6-12 4
a, y,-
r a---
ADMINISTRATIVE CONTROLS RESPONSIBILITIES 6.4.1.6 The 50RC shall be responsible for:
a.
Review of:
(1) all proposed procedures required by Specification 6.7 and changes thereto, (2)'all proposed programs required by Specification 6.7 and changes thereto, and (3) any.other proposed procedures or changes thereto as determined by the Station Manager to affect nuclear safety.
Procedures and programs required by S>ecification 6.7 that are designated for review and approval by tie Stetion Qualified Reviewer Program in accordance with Specification 6.4.2 do not require SORC review.
b.
Review of all proposed tests and experiments that affect nuclear safety; l
c.
Review of all proposed changes to Appendix "A" Technical i
Specifications; d.
Review of all proposed changes or modifications to station systems or equipment that affect nuclear safety; e.
Investigation of all violations of the Technical Specifications, including the preparation and forwarding of reports covering evaluation and recommendations to prevent recurrence, to the Executive Director - Nuclear Production and to the Nuclear Safety Audit Review Committee (NSARC);
f.
Review of all REPORTABLE EVENTS; g.
Review of station operations to detect potential hazards to nuclear safety; h.
Performance of special reviews, investigations, or analyses and reports thereon as requested by the Station Manager or the NSARC; i.
Not used; 1
Not used; k.
Review of any accidental, unplanned, or uncontrolled radioactive l'
release including the preparation of reports covering evaluation, j
recommendations, and disposition of the corrective action to prevent recurrence and the forwarding of these reports to the 3
Executive Director - Nuclear Production and'to the NSARC; 1.
Review of changes to the PROCESS CONTROL PROGRAM, OFFSITE DOSE CALCULATION MANUAL, and the Radwaste Treatment System; and m.
Review of the Fire Protection Program and implementing instructions and submittal of recommended Fire Protection Program changes to the NSARC.
SEABROOK - UNIT 1 6-7 Amendment No. 39
l ADMINISTRATIVE CONTROLS l
l 6.4.1.7 The SORC shall:
a.
Recommend in writing to the Station Manager approval or disapproval of items considered under Specification 6.4.1.6a. through d; b.
Render determinations in writing with regard to whether or not each item considered under Specification 6.4.1.6a. through e.
constitutes an unreviewed safety question; and c.
Provide written notification within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> to the Executive Director - Nuclear Production and the NSARC of disagreement between the SORC and the Station Manager however, the Station Manager shall have responsibility for resolution of such disagreements pursuant to Specification 6.1.1.
RECORDS 6.4.1.8 The SORC shall maintain written minutes of each SORC meeting that, at a minimum, document the results of all 50RC activities performed under the responsibility provisions of these Technical Specifications.
Copies shall be l
provided to the Executive Director-Nuclear Production and the NSARC.
6.4.2 STATION OVALIFIED REVIEWER PROGRAM 1
EMNCTION 6.4.2.1 The Station Manager may establish a Station Qualified Reviewer Program whereby required reviews of designated procedures or classes of procedures required by Specification 6.4.1.6.a are performed by Station Qualified 1
Reviewers and approved by designated managers. These reviews are in lieu of reviews by the 50RC.
However, procedures which require a 10 CFR 50.59 evaluation must be reviewed by the 50RC.
l RESPONSIBILITIES 4
6.4.2.2 The Station Qualified Reviewer Program shall:
a.
Provide for the review of designated procedures, programs, and changes thereto by a Qualified Reviewer (s) other than the individual who prepared the procedure, program, or change, b.
Provide for cross-disciplinary review of procedures, programs, and changes thereto when organizations other than the preparing organization are affected by the procedure, program, or change.
c.
Ensure cross-disciplinary reviews are performed by a Qualified Reviewer (s) in affected disciplines, or by other persons designated by cognizant Managers or Directors as having specific expertise required to assess a particular procedure, program or change.
Cross-disciplinary reviewers may function as a committee.
SEABROOK - UNIT 1 6-8 Amendment No. 34
(
L' ADMINISTRATIVE CONTROLS REVIEW 6.4.3.7 The NSARC shall be responsible for the review of:
l~
a.
The safety evaluations for:
(1) changes to procedures, equipment, or systems; and (2) tests or experiments completed under the provision of 10 CFR 50.59, to verify that such actions did not constitute an unreviewed safety question; 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 or this Operating License; e.
Violations of Codes, regulations, orders, Technical Specifications, license requirements, or of internal procedures or instructions having nuclear safety significance; f.
Significant operating abnormalities or deviations from normal and expected performance of station equipment that affect nuclear safety; g.
All REPORTABLE EVENTS; h.
All recognized indications of an unanticipated deficiency in some aspect of design or operation of structures, systems, or components that could affect nuclear safety; and 1.
Reports and meeting minutes of the SORC.
SEABROOK - UNIT 1 6-9 Amendment No. 34
ADMINISTRATIVE CONTROLS AUDITS 6.4.3.8 Audits of station activities shall be performed under the cognizance of the NSARC. The audits shall be performed within the specified time interval with a maximum allowable extension not to exceed 25% of the specified interval provided the combined time interval for any three consecutive intervals shall not exceed 3.25 times the specified interval. These audits shall encompass:
a.
The conformance of station operation to provisions contained within the Technical Specifications and applicable license conditions at least once per 12 months; b.
The performance, training, and qualifications of the entire station staff at least once per 12 months; c.
The results of actions taken to correct deficiencies occurring in station equipment, structures, systems, or method of operation that affect nuclear safety, at least once per 6 months; d.
The performance of activities required by the Operational Quality Assurance Program to meet the criteria of Appendix B,10 CFR Part 50, at least once per 24 months; e.
The fire protection programmatic controls including the implementing procedures at least once per 24 months by qualified licensee QA personnel; f.
The fire protection equipment and program implementation at least once per 12 months utilizing either a qualified offsite licensee fire protection engineer or an outside independent fire protection consultant. An outside independent fire protection consultant shall be used at least every third year; g.
The Radiological Environmental Monitoring Program and the results thereof at least once per 12 months; h.
The 0FFSITE DOSE CALCULATION MANUAL and implementing procedures at least once per 24 months; 1.
The PROCESS CONTROL PROGRAM and implementing procedures for processing and packaging of radioactive wastes at least once per 24 months; I
j.
The performance of activities required by the Quality Assurance Program for effluent and environmental monitoring at least once per 12 months; k.
Not used; i
1.
Not used; and m.
Any other area of station operation considered appropriate by the NSARC or the Senior Vice President.
SEABROOK - UNIT 1 6-10 Amendment No. 39
ADMINISTRATIVE CONTROLS RECORDS 6.4.3.9 Records of NSARC activities shall be prepared and distributed as l
indicated below:
a.
Minutes of each NSARC meeting shall be prepared and forwarded to the Senior Vice President within 30 working days following each l
meeting; b.
Reports of reviews encompassed by Specification 6.4.2.7 shall be included in the minutes where applicable or forwarded under sepa-rate cover to the Senior Vice President within 30 working days l
following completion of the review; and c.
Audit reports encompassed by Specification 6.4.2.8 shall be forwarded to the Senior Vice President and to the management positions responsible for the areas audited within 30 days after completion of the audit by the auditing organization.
6.5 REPORTABLE EVENT ACTION The following actions shall be taken for REPORTABLE EVENTS:
a.
The Commission shall be notified and a report submitted pursuant t,o the requirements of Section 50.73 to 10 CFR Part 50, and b.
Each REPORTABLE EVENT shall be reviewed by the SORC and the results of this review shall be submitted to the NSARC and the Executive Director-Nuclear Production.
6.6 SAFETY LIMIT VIOLATION The following actions shall be taken in the event a Safety Limit is violated:
a.
The NRC Operations Center shall be notified by telephone as soon as possible and in all cases within I hour. The' Executive Director-Nuclear Production and the NSARC shall be notified within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />; b.
A Safety Limit Violation Report shall be prepared. The report shall be reviewed by the SORC. 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; c.
The Safety Limit Violation Report shall be submitted to the Commission, the NSARC, and the Executive Director-Nuclear Production within 14 days of the violation; and d.
Operation of the station shall not be resumed until authorized by the Commission.
SEABROOK - UNIT 1 6-11 Amendment No. 34 i
ADMINISTRATIVE CONTROLS-6.7 PROCEDURES AND PROGRAMS
'6.7.1 Written procedures shall be established, implemented, and maintained
. covering the activities referenced below:
a.
The applicable procedures recommended in Appendix A of Regulatory Guide 1.33, Revision 2, February 1978; b.
The emergency operating procedures required to implement the requirements of NUREG-0737 and Supplement 1 to NUREG-0737 as stated in Gen,eric Letter No. 82-33; c.
Not used; d.
Not used; e.
PROCESS CONTROL PROGRAM implementation; f.
OFFSITE DOSE CALCULATION MANUAL implementation; g.
Quality Assurance Program for effluent and environmental monitoring; h.
Fire Protection Program implementation; and i.
Technical Specification Improvement Program implementation.
t 6.7.2 The Station Manager 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 SORC. The review per the Qualified Reviewer Program shall be in accordance with Specification 6.4.2.
6.7.3 Procedures and programs listed in Specification 6.7.1 and changes l
thereto,shallbeapprovedbytheStationManagerorbycognIzantManageror Directors who are designated as the Approval Authority by the Station Manager, as specified in administrative procedures. The Approval Authority for each t
procedure and program or class of procedure and program shall be specified in i
administrative procedures.
6.7.4 Each procedure of S)ecification 6.7.1, and changes thereto, shall be reviewed by the SORC and s1all be approved by the Station Manager, or be reviewed and approved in accordance with the Station Qualified Reviewer Program, prior to implementation.
Each procedure of Specification 6.7.1 shall be reviewed periodically as set forth in administrative procedures.
6.7.5 Changes to procedures of Specification 6.7.1 may be made prior to SORC review provided:
a.
The inter.t of the original procedure is not altered; j
b.
The change is approved by two members of the plant management staff, at least one of whom holds a Senior Operator license; and i
c.
The change is documented, reviewed by the SORC and approved by the Station Manager, or reviewed and approved in accordance with the Station Qualified Reviewer Program, within 14 days of implementation SEABROOK - UNIT 1 6-12 Amendment No. 39
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