ML20235N644
| ML20235N644 | |
| Person / Time | |
|---|---|
| Site: | Fort Saint Vrain  |
| Issue date: | 07/13/1987 |
| From: | Calvo J Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20235N614 | List: |
| References | |
| TAC-56743, NUDOCS 8707200160 | |
| Download: ML20235N644 (16) | |
Text
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PUBLIC SERVICE COMPANY OF COLORADO DOCKET NO. 50-267 FORT ST. VRAIN NUCLEAR GENERATING STATION AMENDMENT TO FACILITY OPERATING LICENSE bPR-34 e
o l
1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Public Service _ Company of Colorado (the licensee) dated July 22 and December 5, 1986, ccmplies 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 j
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 i
Part 51 of the Commission's regulations and all applicable requirements have been satisfied.
8707200160 B70713 PDR ADOCK 05000267 P
P DR,
__________________a
i 2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.D(2) of Facility Operating License No.
DPR-34 is hereby amended to read as follows:
lr.) Technical Specifications Ths Technical
- Specifications contained in Appendices A and B; i
as revised through' Amendment No. 56', are hereby incorporated in the license. -The licensee shall operate the facility in accordance with the Technical-Specifications.
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3.
This license amendment is effective as of..the date of its issuance.
FOR THE NUCLEAR REGULATORY-COMMISSION J 6{,
Jose A. Calvo, Director Project Directora'e - IV Division of Rne.or Projects - III, IV, V and Special Projects Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance: July 13,1987
-______m._m_
-.._.__________.-.______________.__m.
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ATTACHMENT TO LICENSE AMENDMENT NO. 56 1
TO FACILITY OPERATING LICENSE NO. OPR-34 j
DOCKET NO. 50-267 Replace the following pages of the Appendix A Technical Specifications with the attached pages as indicated.
The revised pages are identified by amendment number and contain vertical lines indicating the areas of l
l change.
l Remove Insert i
I 7.1-7 7.1-7 7.1-8 7.1-8 i
7.1-9 7.1-9 l
I l
7.1-11 7.1-11 7.1-12 7.1-12 7.1-13 7.1-13 7.1-14 7.1-14 7.1-16 7.1-16
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i 7.1-18 7.1-18 7.1-19 7.1-19 7.1-22 7.1-22 7.1-23 7.1-23 l
7.4-2 7.4-2 l
i Fort St. Vrain #1
^
"O Technical Specificaticrs Amendment 96,56 Page 7.1-7
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Authorized ceviations to the working hour guidelines shall be documented and available for Nuclear i
Regulatory Commission review.
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3.
Training a.
A retraining and replacement training program..for the facility staff shall be mairitained under the 1
l direction of the Superintendent of Training and shall meet or exceed the requirements and 1
I recommendations of Section 5.5 of ANSI N16.1-1971 and Appendix "A" of 10CFR Part 55. Compliance with Section 5.5 of ANSI 18.1-1971 shall be achieved no later than six cantns following commencement of commercial cperation, b.
A training program for the Fire Brigade shall be j
l l
maintained under the direction of the Superintendent l
of Training and shall meet o*
exceed tne require ents of Section 27 of the NFPA Code-1975, except for Fire Brigade training / drill sessions j
which shall be held at least once per calendar quarter.
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c.
The Technical Advisors shall have a bachelor degree or equivalent in a scientific or engineering discipline with specific training in plant design
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Fort St. / rain s'.
1 Technical Sj6. 5gations ecifi Amendment #
..Page 7.1-8 I
J and response and analysis of the :lant for 1
transients and accidents. An initial training and
)
1 retraining program for the Technical Advisers shall
.)
be maintained under the direction of the l
l Superintendent of Training. The Technical Advisors shall also receive trajning.in plant design and I
..1 layout,.
including the capabilities of instrumentation and controls in the' Contrcl Room.
1 e
Specification AC 7.1.2 - Plant Operatiens Review' Committee (PCRC), Administrative Controls t
The organization, responsibilities, and authority of the PORC shall te as follows:
j 1.
Membership The Plant Operations Review Committee'sh411 te composed of the follcwing:
Chai rma n : Station Manager Technical / Administrative Services Manager i
Support Services Manager (Radiation Protection Manager)
Superintendent of Operations Superintendent of Maintenance Superintendent of Nuclear Betterment Engineering
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Health Physics Supervisor
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I a
Fort St. Vrain el
^
Technical Specificatscrs Amendment #4, 56 Page 7.1-9 i
Results Engineering Supervisor j
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Results Instrumentation and Controls Supervisors
$hift Supervisor Administration l
Shift Supervisor Training
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l Superintendent of Technical Services Engineering l
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Superintendent of Training 1
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2.
Alternates An alternate chairman. and alternatt members, if
)
i required, shall be appointed in writing by the FORC Chaiman to serve in the absence of a chairman or a m
1 member; however, no more than two alternate members shall participate in PORC activities at any one time.
i i
3.
Meeting Frequency The PORC shall meet at least once per calencar month and I
as ccnvered by the Chairman.
4 Qacrum A quorwr. shall consist of the Chairfr.an or alternate 1
Chairman, and four members including alternates.
I S.
Responsibilities The PORC shall be responsible for:
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Fort St. Vrain 01 Technical Specif Amendment #37,y*;ations Page 7.1-11 h.
Performance of special reviews, investigations, and reports thereon as requested by the Chairman of the.
Nuclear Facility Safety Committee.
I 1.
Review of the Plant Security Plan and implementing I
l procedures.
j.' Review of the plant Radiological Emergency Response Plan and implementing procedures.
k.
Review of eve ry unplanned onsite release of radioactive material'to the environs, including the
. preparation of reports concerning evaluation, "
j recommendations, and disposition of, the corrective action to l
prevent recurrence and the forwarding of these reports to the Manager, Nuclear Froduction and l
the Nuclear Facility Safety Committee (NFSC).
6.
Authority L
The PORC shall:
l
.l a.
Function to advise the Manager, Nuclear Production l
cn all matters that affect nuclear safety.
b.
Recommend to the Manager, Nuclear Production in writing, approval or disapproval of items considered under 5.a 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 j
j J
I T
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._____.________U
1 Fort St. Vrain #1'
-Technical Specifications
' Amendment # M,56 Page 7.1-12 Station Manager; however, the Station Manager shall.
have responsibility for resolution of
'such.
disagreements pursuant to 6.4 above, e
~7.
Records s
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The PORC shall maintain written minutes' of each meeting' and copies shall be provided to the Manager,. Nuclear Production end Chairman of the Fort St. Vrain Nuclear Facility Safety Committee.
$ specification AC 7.1.3 - Nuclear Facility Safety Committee (NFSC), Administrative Controls i
The organization, responsibilities, and authority of the NFSC shall be as follows:
I l
1.
Function 1
l The Nuclear Facility Safety Committee shall collectively l
have the competence required to review problems in thw l
following areas:
a) Nuclear Power Plant Operations
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b) Nuclear Engineering I
c) Chemistry and Radiochemistry I
I d) Metallurgy l
i u_________.__--__-------_----------
Fort St. Vrain #1 l
Technical Spec Amendment #36, g1 cations i
Page 7.1-13 I
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l e) Instrumentation and Control l
I f) Radiological Safety g) Mechanical and Electrical Engineering 1
h) Quklity Assurance Practices I
S.0ther appropriate fields associated with the unique characteristics of the nuclear power plant.
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2.
Membership The NFSC shall be composed of the'following:
'l Chairman (As appointed - See Step 4) l d
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Manager, Nuclear Licensing And Fuels Division Manager, Nuclear Production Division l
Manager, Nuclear Engineering Olvision n
1 Manager, Quality Assurance Division i
i Safety and Security Director l
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; l
however, no more than two alternate members shall
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l participate as voting members in NFSC activities at any l
one time, i
l L---------_-__
Fort St. Vrain 4-1 Technical Specifications
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Amendment 035, 56 Page 7.1-14 1
l 4
Chairman-i The Chairman and Alternate Chairman of the NFSC shall be l
l appointed in writing by the Vice President,. Nuclear i
Operations and shall serve as members of the NF5C.
l 5,
consultants Consultar.ts shall be utilized as determined by the Chairman, NFSC, to provide expert advice to the NFSC.
l 6.
Meetino Frequency.
The NFSC shall reeet at least once per calendar quarter during the initial year of facility operation following fuel loading and at least once per six months thereaf*ar.
4,
l 7
Quorum s
A quorum of the NFSC shall consist of the Chairman or hisd$signatedalternateand a majority of the NFSC members including alternates. No more than'a minority I
of the quorum shall have line responsibilities for operation of the facility.
l 8.
Responsibilities i
1 a.
The ' Nuclear Facility Safety Committee shall review:
i (1) The safety evaluations 'for safety significant changes to procedures. equipment, or systems j
l
)
fort St. Vrain #1 i
Technical Specifications Amendment H2.
56 i
Page 7.1-16 (7) All Reportable Events.
(8) Any indication that there may be a deficiency in some aspect of design or operation of structures, systems, or components, that af fect i
nuclear safety.
j J
(9) Reports and meeting minutcs of the p0RC.
I b.
The Nuclear Facility Safety Committee shall approve:
l (1) The control rod withdrawal sequence as required i
by Technical Specification LCO 4.1.3.
l (2) The initial base (reactivity) steady state core l
l condition and changes to the base (reactivity) l as requirsd by Technical Specification LCO l
4.1.8.
NFSC permission is required before l
reactor operations may resume if a reactivity I
anomaly of 0.01 Delta K is reached.
l (3) Preposed changes to facility, operating l
proceduras and tests or experiments that are l
determired to involve an unreviewed
)
I environmental question.
I c.
Audits of facility activities shall be performed under the cognizance of the Nuclear Facility Sa fety Comittee. These audits shall encompass:
(1) The conformance of facility operation to all provisions contained within the Technical Specifications and applicable license conditions at least once per year.
(2) The ' performance, training, and qualifications, of the f acility staff at ieast once per year.
l, (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.
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Fort St. Vrain #1 Technical 5 specifications Amendment #37, 56 Page 7.1-18 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 prevention inspection and audit utilizing an 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 Moni toring Progrse and the results thereof at least once per 12 months.
(11) The performance of activities required by the Quality As surance 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, i
Nuclear Operations on those areas of responsibility l
Specified in 8.a. 8.b and 8.c above.
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- 10. Recerds Recorcs of NFSC activities shall be prepai 9d, approved, and distributed as indicated below:
a.
Minutes of each NFSC meeting shall be prepared, approved, an'd forwarded to the Vice President, l
Nuclear Operations, within 30 days following each
- meeting, j
i
)
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________J
Fort St. Vrain #1 Technical Specifications i
Amendment #37, 56 i
Page 7.1-19 i
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b.
Reports of reviews encompassed by Section 8.a.
above shall be forwa rded to the Vice President, l
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l Nuclear Operations, within 30 days following I
completion of the review.
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c.
Audit reports encompassed by Section 8.c.
above I
shall be forwarded to the Vice President, Nuclear l
Operations, and to the management positions responsible for the areas audited within 30 days af ter completion of the audit.
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l Fort St. Vrain 6 Technical Specifications' Amendmen2 97, 56 Page 7.4-2 7.
Offsite Oose Calculation Manual (00CM) i implementation.
8.
Quality Assurance Program for effluent and l
environmental motiitoring using the guidance in
]
Regulatory Guide 1.21, Revision 1, June, 1974 I
and Regulatory Guide 4.1, Revision 1
- April, 1975.
b, procedures and administrative policies of a) above, and changes thereto, shall be r2 viewed by the PORC 3
l l
and approved by the appropriate Manager prior to implementation and reviewed periodically as set 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 l
Security Officer prior to implementation.
l t
I c.
Temporary changes to procedures of a) above may be made pr~ idsd 1.
The intent of the original procedure is not i
altered.
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