ML20211L353
| ML20211L353 | |
| Person / Time | |
|---|---|
| Site: | Fort Saint Vrain  |
| Issue date: | 12/05/1986 |
| From: | PUBLIC SERVICE CO. OF COLORADO |
| To: | |
| Shared Package | |
| ML20211L335 | List: |
| References | |
| TAC-56743, NUDOCS 8612150470 | |
| Download: ML20211L353 (10) | |
Text
=
Fort St. Vrain #1 Technical Sp;cifications Amendment Page 7.1-11 h.
Performance of special reviews, investigations, and reports thereon as requested by the Chairman of the Nuclear Factitty Safety Committae.
1.
Review of the Plant Securits Plan and implementing l
procedures.
J.
Review of the plant Radiological Emergency Response Plan and implementing procedures, k.
Review of every unplanned onsite release of radioactive material to the environs, including the preparation of reports concerning evaluation, recommendations, and disposition of the corrective action to prevent recurrence and the forwarding of these reports to the Manager, Nuclear Production and the Nuclear Facti 1ty Safety Committee (NFSC).
6.
Authority The PORC shall:
a.
Function to advise the Manager, Nuclear Production on all matters that affect nuclear safety, b.
Recommend to the Manager, Nuclear Production in writing, approval or disapproval of items considered under 5.4 through 5.d. above.
c.
Render determinations in writing with regard to whether or not each item considered under 5.a through 5.e above constitutes an unreviewed safety
- question, d.
Provide immediate written notification to the Manager, Nuclear Production and the Chairman of NFSC of disagreement between the PORC and the k
[
P
~
Fort St. Vrain #1
+
Technical Sp:cifications Amendment Page 7.1-12 Station Manager; however, the Station Manager shall have responsibility for resolution of such disagreements pursuant to 6.a above.
7.
Records The PORC shall maintain written minutes of each meeting and copies shall be provided to the Manager, Nuclear Production and Chairman of the Fort St. Vrain Nuclear Facility Safety Committee.
- (
Specification AC 7.1.3 - Nuclear Facility Safety Committee s
(NFSC), Administrative Controls The organization, responsibilities, and authority of the NFSC shall be as follows:
1.
Function l
The Nuclear Facility Safety Committee shall collectively l
have the competence required to review problems in the l
following areas:
a) Nuclear Power Plant Operations b) Nuclear Engineering c) Chemistry and Radiochemistry
.s d) Metallurgy s-o l
i y --,
,e
+,
- - +, - - - -
Fort St. Vrain #1 Technical Specifications Amendment Page 7.1-13 e) Instrumentation and Control f) Radiological Safety g) Mechanical and Electrical Engineering h) Quality Assurance Practices
- 1) Other appropriate fields associated with the unique characteristics of the nuclear power plant.
2.
Membership The NFSC shall be composed of the following:
l Chairman (As appointed - See Step 4) l Manager, Nuclear Licensing and Fuels Division Manager, Nuclear Production Division Manager, Nuclear Engineering Division l
Manager, Quality Assurance Division l
Safety and Security Director Consultants, as required and appointed by the Chairman 3.
Alternates l
Alternate members, if required, shall be appointed in l
writing by the Vice President, Nuclear Operations; I
however, no more than two alternate members shall l
participate as voting members in NFSC activities at any l
one time.
Fort St. Vrain #1 Technical Specifications Amendment Page 7.1-14 l
4.
Chairman l
The Chairman and Alternate Chairman of the NFSC shall be l
appointed in writing by the Vice President, Nuclear l
Operations and shall serve as members of the NFSC.
l S.
Consultants Consultants shall be utilized as determined by the Chairman, NFSC, to provide expert advice to the NFSC.
l 6.
Meeting Frequency The NFSC shall meet at least once per calendar quarter during the initial year of facility operation following fuel loading and at least once per six months thereafter.
l 7.
Quorum A
(. rum of the NFSC shall consist of the Chairman or his designated alternate and a majority of the NFSC members including alternates. No more than a minority of the quorum shall have line responsibilities for operation of the facility.
l 8.
Respon:ibilities a.
The Nuclear Facility Safety Committee shall review:
(1) The safety evaluations for safety significant changes to procedures, equipment, or systems
Fort St. Vrain #1
[
Technical Sp cifications Amendment Page 7.1-16 i,
(7) All Reportable Events.
l' (8) Any indication that there may be a deficiency in g
some aspect of design or operation of structures, systems, or components, that affect nuclear safety.
(9) Reports and meeting minutes of the PORC.
l b.
The Nuclear Facility Safety Committee shall approve:
l (1)The control rod withdrawal sequence as required l
by Technical Specification LCO 4.1.3.
l (2) The initial base (reactivity) steady state core l
condition and changes to the base (reactivity) l as required by Technical Specification LCO l
4.1.5.
NFSC permission is required before l
reactor operations may resume if a reactivity l
anomaly of 0.01 Delta K is reached.
l (3) Proposed changes to facility, operating l
procedures and tests or experiments that are l
determined to involve an unreviewed l
environmental question.
l c.
Audits of facility activities shall be performed under the cognizance of the Nuclear Facility Safety Committee. These audits shall encompass:
-(1) The conformance of facility operation to all provisions contained within the Technical Specifications and applicable Itcense conditions at least once per year.
(2) The performance, training, and qualifications, of the facility staff at least once per year.
(3) The results of actions taken to correct deficiencies occurring in facility equipment, structures, systems, or method of operation that affect nuclear safety at least once per six months.
,~.,
3 7-,
Fort St. Vrain #1 Technical Specifications Amendment Page 7.1-18 c
personnel or an outside fire protection firm; (b) a biennial audit of the fire protection program and implementing procedures; (c) a triennial fire protection and loss l
prevention inspection and audit utilizing an l
outside qualified fire consultant.
l (9) The Offsite Dose Calculation Manual and Process Control Program and implementing procedures at least once per 24 months.
(10) The Radiological Environmental Monitoring Program and the results thereof at least once per 12 months.
(11) The performance of activities required by the Quality Assurance Program to meet the provisions of Regulatory Guide 1.21 Revision 1, June 1974 and Regulatory Guide 4.1, Revision 1 April 1975, at least once per 12 months.
l 9.
Authority The NFSC shall report to and advise the Vice President, l
Nuclear Operations on those areas of responsibility I
specified in 8.a. 8.b and 8.c above.
l
- 10. Records Records of NFSC activities shall be prepared, approved, and distributed as indicated belcw:
a.
Minutes of each NFSC meeting shall be prepared, approved, an'd forwarded to the Vice President, 1
Nuclear Operations, within 30 days following each rreeting.
Fort St. Vrain #1 Technical Specifications Amendment 4
Page 7.1-19 l
b.
Reports of reviews encompassed by Section 8.a.
above shall be forwarded to the Vice President, l
Nuclear Operations, within 30 days following completion of the review.
l c.
Audit reports encompassed by Section 8.c, above l
shall be forwarded to the Vice President, Nuclear l
Operations, and to the management positions responsible for the areas audited within 30 days after completion of the audit.
Fort St. Vrain #1 Technical Specifications knendment Page 7.4-2 7.
Offsite Dose Calculation Manual (00CM) implementation.
8.
Quality Assurance Program for effluent and environmental monitoring using the guidance in Regulatory Guide 1.21, Revision 1, June, 1974 and Regulatory Guide 4.1, Revision 1
- April, 1975.
b.
Procedures and administrative policies of a) above, and changes thereto, shall be reviewed by the PORC and approved by the appropriate Manager prior to implementation and reviewed periodically as sat forth in Administrative Procedures.
Security Plan procedures, and changes thereto, shall be reviewed by the Plant Operations Review Committee and approved by the designated Plant Security Officer prior to implementation.
t 1
i c.
Temporary changes to procedures of a) above may be made provided:
1.
The intent of the original procedure is not altered.
l
4 e
ATTACHMENT 3 SIGNIFICANT HAZARDS CONSIDERATION
SIGNIFICANT HAZARDS CONSIDERATION i
i I. Evaluation The proposed changes involving the Fort St. Vrain (FSV) Security Committee and the Nuclear Facility Safety Committee are administrative in nature.
The Fort St.
Vrain Security Committee, as appointed in 1975, consisted of an inter-disciplinary group from Public Service Company of Colorado Electric Production, Electric Engineering, Nuclear Production and Safety and Security. Over the years since 1975, full authority and responsibility for plant security has been transferred to the Fort St. Vrain Security and Nuclear Organizations. Therefore, all references to and duties of the Security Committee are being deleted from the FSV Technical Specifications.
II. Conclusion Based on the above, operation of Fort St. Vrain in accordance with the proposed changes will not (1) involve a significant increase in the probability or consequences of an accident previously evaluated, (2) create the possibility of a new or different kind of accident from any accident previously evaluated, or (3) involve a significant reduction in a margin of safety.
Therefore, this change will not create an undue risk to the health and safety of the public nor does it involve any significant hazards consideration.