ML20030D615
| ML20030D615 | |
| Person / Time | |
|---|---|
| Site: | FitzPatrick  |
| Issue date: | 08/31/1981 |
| From: | Ippolito T Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20030D616 | List: |
| References | |
| NUDOCS 8109140033 | |
| Download: ML20030D615 (13) | |
Text
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N UNITED $TATES j
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- NUCLEAR REGULATORY COMMI3slON
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POWER AUTHORITY OF THE STATE OF 14EW YORK DOCKET NO. 50-333 JAMES A. FITZPATRICK NUCLEAR POWER PLANT AMENDMENT TO FACILITY OPERATING LICENSE
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Amendment No. 60 License No. OPR-59 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment by Power Authority of the State of New York (the licensee) dated June 15, 1981, 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 Comission; C.
There is reasonable assurance (1) that the activf ties, authorized by this amendment can be conducted without endangering the haalth and safety of tha public, and (11) 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 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.
0109140033 810831 PDR ADOCK 05000333 P
' 2.
Accordingly, Facility Operating License No. DPR-59 is amended by changes to the Technical Specifications as indicated in the attachment, and Paragraph 2.C(2) of Facility Operating License No. DPR-59 is hereby amended to read as follows:
(2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 60., 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 its issuance.
FOR THE NUCLEAR REGULATORY COMMISSION c4
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'homas Ippolito, Chief Operating Reactors Branch #2 Division of Licensing
Attachment:
Changes to the Technical Specifications Date of Issuance: August 31,1981 6
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l ATTACHMENT TO LICENSE AMENDMENT NO. 60-l FACILITY OPERATING LICENSE NO. DPR-59 DOCKET NO. 50-333 l
l Revise Appendix "A" as follows:
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Delete Insert 247 247 251 251 252 252 252a 252a 253 253 259 259 260 260 141 141 Revise Appendix "B" as follows:
Delete Insert 43 43 44 44 9
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'6. 0 ADMINISTRATIVE CONTROLS Administrative Controls are the means by which plant opera-tions are subject to management control.
Measures specified in this section provide for the assignment of responsibilities, plant organization, staffing qualifications and related re-quirements, review and audit mechanisms, procedural controls and reporting requirements.
Each of these measures are neces-sary to ensure safe and efficient facility operation.
6.1 RESPONSIBILITY The Resident Manager is responsible for safe operation of the plant.
During periods when the Resident Manager is un-available, the Superintendent of Power will assume his respon-sibilities.
In the event.both are unavailable, the Resident Manager may delegate this responsibility to other qualified supervisory personnel.
The Resident Manager reports directly to the Sr. Vice President-Nuclear Generation,-as shown-in-Fig. 6.1-1.
6.2 PLANT STAFF ORGANIZATION The plant se.aff organization is shown graphically in Fi.g.
6.2-1 and functions as follows':
1.
A licensed senior reactor operator shall be on site at all times when there is fuel in the reactor.
2.
In addition to item l above, a licensed reactor operator shall be in the control room at all times when there is fuel in the reactor.
3.
In(addition to items 1 & 2 above, a licensed reactor operator shall be readily available on site whenever the reactor is in other than cold condition.
4.
Two licensed.. reactor-.oper.? tore--shall-be -in the-con -- --
trol room during start-ups and scheduled' shutdowns.----.
5.
A licensed senior reactor operator shall be respon-sible for all movement of new and irradiated fuel within the site boundary.
A licensed reactor ope will be required to manipulate or directly superv,rator ise the manipulation of the controls of all fuel moving equipment, except the reactor build 4.ng crane.
All fuel movements by thu reactor building crane, except new fuel movements from receipt through dry storage, shall be under the direct supervision of a licensed reactor opera tor.
All fuel morements witnin the core shall be direct}a) menitored by a member of the reactor y
analyst group. t Amendm'en t No.
, 60 247 SEE NEXT PAGE FOR FOOTNOTE n--
P f.
Radiological cafoty 9
Mechanical engineering h.
Electrical engineering i.
Administrative controls and quality assurance practices j.
Environment k.
Civil / Structural Engineering 1.
Nuclear Licensing
.n.
Emergency Planning Other appropriate fields associated with the unique n.
characteristics of a nuclear power plant-MEMBERSHIP 6.5.2.2 The SRC shall be composed of the following voting members:
Chairman:
Director-Nuclear Design and. Analysis Vice-Chairman ~:
Vice President-Quality ~ Assurance l
Member:
Manager-Nuclear Technical Support Member:
Manager-Radiological Health and Safety l
Member:
Senior Vice President-Nuclear Generation Merber:
Director-Electricai Design and Analysis Member:
Director of Enviionmental Progrrms Member:
Dire'ctor-Civil / Structural Design and Analysis Member:
Dire : tor-Meehanical Design and Analysis Member:
Cenior Inservice Inspection Engineer-4 Nuclear Technical Support Member:
Manager-Nuclear Licensing Member:
Senior Nuclear Engineer-Design and Analysis Member:
- Manager '.iuclear Operations l
ALTERNATES 6.5.2.3 All alternate members.? hall be appointed in writing by the SRC Chairman; however, no more than two alternates shall participate as voting members in SRC activities at any one time.
CONSULTANTS 6.5.2.4 Consultants shall be utilized as determined by thc SRC Chairman to provide expert advice to the SRC.
MEETING FREQUENCY 6.5.2.5 The SRC shall meet at least once per calendar quarter during the initial year of facility operation following initial fuel loadio. and at least once per six months, thereafter.
Amendment No. 3, 60 251
6.5.2.6 A quorum of SRC choll consiGt of thD C*hairman or Vico-Chairman cnd cix membars, including citor.nctes.
No l
moro then minority of tha quorum chall have a direct line responsibility for the operation of the plant.
Rn'IEW 6.5.2.7 The SRC shall review:
a.
The safety evaluation for 1) changes to procedures, equipment or systems and 2) tests or experiments ccm-pleted under the provision of Section 50.59, 10 CFR, to verify that such actions did not constitute an unreviewed safety question.
b.
proposed changes to procedures, equipme nt or systems which involve an unreviewed safety question as defined in Sectior. 50.59, 10 CFR.
c.
Proposed tests or-experiments which involve' an 'un-reviewed safety question as defined in Section 50.59, 10 CFR.
d.
Preposed changes to Technical Specifications of this Operating License.
Violations cf code, regulations, ord e r s. - -Techr.ica ; ~. -
e.
Specifications, license requirements, or of inter..a1 procedures or ins.tructions having nuclear safety significance.
f.
Significant operating abnormalities or deviations fror normal.and expected performance of plant equipment tha t affect nuclear v.afety.
Com.k.ats requiring 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> written notification.to the Eve g.
ission.
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h.
All recognized indications of an' unanticipated deficiency in some aspect of design or operat. ion of saf ety related s tru ctures, -systems, or-component 37---
i.
Reports and meeting 3 minutes ~of the Plant Operating Review Committee.
AUDIT 6.5.2.8 Audi.ts of facility activities shall be performed ~ under the cognizance of the SRC.
These audits shall encompass:
The conformance of facility operation to provisions a.
contained within the Technical Specifications and applicable license conditions at least once per 12 months.
b.
The performance, training and qualifications of the entire facility staff-at least once pe~r 12 months.
A7endment No. )d, 60 252 w
hJ rcsulGs of 5Jtlcno tekcn to carrcet d0ficiencica i
c.
T occurring in fccility cquipm:nt, ctructurac, cystcm3 cr cathod of cp;raticn that offcet nuclear cofoty at locat cnca por 6 months.
d.
The performance of activities required by the Opera-tional Quality Assurance Program to meet the criteria of Appendix "B", 10 CFR 50, at least once per 24 months.
The Facility Emergency Plan and implementing procedures e.
at least once per 24 months.
1 f.
The Facility Security Plan and implementing procedures at least once per 24 months.
g.
Any other area of f acility operation considered appropriate by the SRC or the President.
h.
The Facility Fire Protection Program and implementing procedures at least once per two years.
i.
An independent fire protection and loss of prevention inspection and audit shall be performed annually utilizing either qualified offsite licensee personnel or an cutside fire protection firm.
j.
An inspection and sudtr af the fire' protection and loss prevention program shall be perf ormed by..an. outside----.---
qualified 'fiEe Eoisultant at intervals no greater.than 3 years.
AUTHORITY 6.5.2.9 The SRC shall report to and ~ advise the President and Chief Operating Officer (to be referred to in the Tech Spec. as the President) on those areas of responsibility specified in Section 6.5.2.7 and 6.5.2.8.
RECORDS I
6.5.2.10 Records will be maintained in accordance with*
-Tho-.foLlowing--sha11-begrepared / approved----- " --
and distributed 4s-indicated-below: - - - - -
Minutes" crf 'evch 1RC 26d.Tng shall be prepared, approved a.
and forwarded to the President within l
14 days after the date of the meeting.
- b., Reports of revieus encompassed by Section 6.5.2.7 _..
above, shall be prepared, approved and forwarded -to the President within 14 days following completion of the review.
c.
Audit reports encompassed by Section 6.5.2.8 above, shall be forwarded to the President and
.l to the managemeat positions responsible for the areas audited within 30 days after completion of the audit.
R.er.dr.ent No.
, 60 252a
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- CHARTER 6.5.2.11 Ccnduct of tha committoo will b3 in cccordcnce with a charter approved by the President setting forth the mechanism for implementation of the committee's responsibilities and authority.
6.6 REPORTABLE OCCURRENCE ACTION (A) In the event of a Reportable Occurrence, the NRC shall be notified and/or a report submicted pursuant.to the requirements of Specification 6.9.
(B) Each Reportable Occurrence requiring 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> notification to the NRC shall be reviewed timely by the PORC and a report submitted by the Resident Manager to the Senior Vice President-Nuclear Generation and_the SRC.
6.7 SAFETY LIMIT VIOLATION (A) If a safety limit is exceeded, the reactor shall be shut down and reactor operation shall only be resumed in accordance with the provisions of 10 CFR 50.36 (c) (1).
(B) An immediate report of each safety limit violation'shall be made to the NRC by the Resident-Manager.'
The Senicr Vice President-Nuclear Generation and Chairman of the SRC -wi-ll-be -- -"
noti fi ed -wi thin -24 hocrs.' "-
(C) The PORC shall prepare a complete investigative report of each safety limit violation and include appropriate analysis and evaluation of: (1) applicable circumstances preceding the occurrence,' (2) systems or structures and -(3) effects of the occurrence upon facility compone corrective action pe' quired to prevent recurrance..The Resident Manager shall forward this report to the Senior Vice President-Nuclear Generation, Chairman of the S$C and the NRC.
6.8 PROCEDURIS (A) Written procedures and adminstrative-pol-icies shall bb~ '
established, implemented and maintained that meet or-
_ requirements-andar+commendstioftFdf*SWetTon S * *'f 5 cit [gxgged ;he ----
r.dministrative Policies and Procedu es" of ANSI ty 18.7-1972 and Appendix A of Regulatory Guide 1.33, November 1972.
In addition, procedures shall be established, implemented and maintained for the Fire Protection Program.
(B) Those procedures affecting nuclear safety shall be reviewed by PORC and approved by the Resident Manager prior to implementation.
(C) Temporary changes to nuclear related procedures may be made provided:
1.
The intent of the original procedure is not altered.
Amen 2ent No. j, 60 d
253
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4 PRESIDENT s, CHIEF OPERATING OFFICER
' SAFE'IV REVIEW O.
COMNITTEE I
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EXECUTIVE V.
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PROCEDURES AND PERFORMANCE t SENIOR VICE PRESIDENT
& CilIEF ENGINEER P
NUCLEAR GENERATION t-
- DIRECTOR OF SAFETY AND F2RE PROTECTION RESIDENT PROCEDURES AND PERFORMANCE MANAGER u
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jThe Senior Vice President Nuclear Generation is responsible for administering the fire protection program.,
- The Director of Safetf and Pire Protection is the of f-site managerent position responsible for assessing the ef fectiveness of the fire protection programs lay conducting reviews and audits.
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a FIGURE 6.1-1 e
MANAGEMENT ORGANIZATION CllART JAMES A. FITZPATRICK NUCLEth POWER PLANT
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FIGURE 6. 2-1 r
occua rens s u o - s r n roit nrAcron oPEnAroit POWER AUTilORITY OF TIIE STATE OF NEW YORK
- w - sa:Actou orcnATo:t JAMES A.
FITZPATRI'CK NUCLEAR POWER PLANT PLANT STAFF ORGANIZATION 1
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3.6 (cont'd)
JAFHPP 4.6 (cont'd) e 4.
Except as specified'in 3.6.C.3 above, the reactor coolant water shall not exceed the following limits eith steaming rates greater than or equal to 100,000 lb/hr and during reactor shutdowns.
Conductivity 5 umho/cm Chloride ion 0.5 ppm 5.
If Specification 3.6.C cannot be met, the reactor shall be placed in a cold condition within 24 hr.
D. Coolant Leakage D.
Coolant Leakage 1.
Any time irradiated f:lel is in Reactor coolant leakage rate inside the primary the reactor vessel and reactor containment shall be established once/ day coolant temperature is above utilizing the Equipment and Floor Drain 212 F, reactor coolant leakage Sump Monitoring Systems.
l into the primary containment from unidentified sources shall not exceed 5 gpm.
In addition, the total reactor coolant system leakage into the primary containment shall not exceed 25 gpm.
2.
The following reactor coalant system leakage detection systems shall be operable during reactor power operation; a.
Drywell sump monitoring system (the capability to measure leakage rate from the equipioent drain sump monitoring and floor drain sump monitoring),
b.
Difwell Continuous Atmosphere (particulate)
Radioactivity Monitoring system, and c.
Drywell Continuous Atmosphere (gaseous)
Radioactivity Monitoring Syqtem.
Amendment No. k?, 60 141 f
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PLANT OPF. RATING REVIEW
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COM.MITTEE l
SUPI:III !TENDENT fl$
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POh*C R
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C RADIOLOGICAT AND I:tJVIItO.'!! T: tai, SERVICES l
SUPI:IIIt!TENDENT l
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FIGURE 5.2-1 POWER AUTilORITY OF Tile STATE OF NEW 'lORK
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JAMES A. FITZPATRICK NUCLEAR POWF.R PLANT P!, ANT ORGANIZATION - RADIOLOGICAL ENVIRONMENTAL l
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PRESIDL.4T AND CHIEF l
OPERATING OFFICER l
SAFETY REVIEW COMMITTEE SENIOR VICE PRESIDENT-EXECUTIVE VICE NUCLEAR GENERATION PRESIDENT AND CHIEF ENGINEER RESIDENT MANAGER MANAGER-RADIOLOGICAL DIRECTOR-ENVIRONMENTAL HEALTH AND SAFETY PROGRANS
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L STAFF STAFF
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Figure 5.2-2 Management Organization-Offsite Radiological Environmental 1
James A.
FitzPatrick Nuclear Power Plant Amendment No. 60 44
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