ML19339C978
| ML19339C978 | |
| Person / Time | |
|---|---|
| Site: | Pilgrim |
| Issue date: | 02/02/1981 |
| From: | Ippolito T Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML19339C979 | List: |
| References | |
| NUDOCS 8102130034 | |
| Download: ML19339C978 (12) | |
Text
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}o, UNITED
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, y,(f(,g NUCLEAR REGUL.'..ORY COMMISSION
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C WASHINGTON, D. C. 20$55
%d BOSTON EDISON COMPANY DOCKET NO. 50-293 PILGRIM llVCLEAR POWER STATION, UNIT NO. 1 AMENur'ENT TO FACILITY OPERATING LICENSE Amendment No. 46 License No. OPR-35 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by the Boston Edison Company (the licensee) dated September 29, 1980 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 operata in confomity 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 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 Part 51 of the Commission's regulations and all applicable requirements have been satisfied.
2.
Accordingly, the license is amended by changes to the Technical Spec-ifications as indicated in the attachment to this license amendment and paragraph 3.B of Facility Operating License No. OPR-35 is hereby amended to read as follows:
3.S Technical Soecifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 46, are hereby incorporated in the license. The licensee shall operate i.hc facility in accordance with the Technical Specifications.
8102130 O M
. 3.
This license Amendment is effective as of the date of its issuance.
FOR THE NUCLEAR REGULATORY COMMISSION Oc. '
W Thomas'A!w[polito, Chief Ip Operating Reactors Branch 42 Division of Licensing
Attachment:
Changes to the Technical Specifications Date of Issuance:
February 2,1981 l
l I.
r ATTACHMENT TO LICENSE AMEN 0 MENT NO. 46 FACILITY OPERATING LICENSE NO. OPR-35 DOCKET NO. 50-293 Revise Appendix A as follows:
Remove the following pages and insert identically numbered pages:
208 208a 209 210 210a 212 213 21 6 21 7 W
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6.0 ADMINISTRATIVE CONTROLS _
(
6.1 RESPONSIBILITY The' Nuclear Operations Manager shall be accountable for overall facility operation. In his absence the Deputy Nuclear Operations Manager or an alternate designated in writing by the Nuclear Operations Manager shall assume this responsibility.
6.2 0FCAVI2ATION A.
OFFSITE Ihe Company organization for station management and technical
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support shall be as shown on figure 6.2.1.
B.
FACILITY The Facility organization shall be sa shown on Figure 6.2.2 and:
1.
Each on duty shif t shall be composed of at least the minimum shift crew composition shown in Table 6.2.1.
2.
At least one Licensed Operator shall be in the control room when fuel is in the reactor.
3.
f.c least two Licensed Operators shall be present in the control room during reactor startup, scheduled reactor shutdown and during recovery from reactor trips.
4.
An individual qualified in radiation protection procedures shall be on site when fuel is in the reactor.
5.
ALL CORE ALTERATIONS performed while fuel is in the reactor vessel after the initial fu41 loading shall be directly supervised by either a licensed Senior Reactor Operator or Senior Reactor Operator Limited to Fuel Handling who has no other concurrent responsilbilities during this operation.
6.
The organization of the administration of the Pilgria I Fire Prevention and Protection Program shall be sa shown on Figure 6.2.3.
A Fire 3rigade of 5 memb'ers including the Fire Chief shall be maintaior.d on site at all times. This excludes 3 members of the shif t crew necessary for safe shutdown and any personnel
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required for other essential functions during a fire emergency.
6.3 FACILITY STAFT OUALITICATIONS Ihe qualifications with regard to educational and experience backgrounds of the facility staff at the time of appointment to the active position shall meet the recluirements as described in the American National Standards Institure N18.1-1971, " Selection and Training of Personnel for Nuclear Power Plants." In addition, the individual performing the function of Radiation Protection Manager shall neat or exceed the qualifications of Regulatory
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Guide 1.8, September,1975.
208 Amendment No. 46
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a 6.4 TRAINING A retraining and replacem:nt training program for the facility staff shall A.
l be saintained under the direction of the Nuclear Operations P.anager.,
A retraining progras for the licensed operators shall be maintained tader B.
the direction of the Senior Nuclear Training Specialist and shall meet or exceed the requirements and recommendations of Section 5.5 of ANSI N18.1-1971 and Appendix A of 10 CFR Part 55.
A training program for the Fire Brigade shall be mai.tained under t' e r
C.
direction of the Fire Protection and Prevencien Officer and shall zoet or exceed the requiraments of Section 27 of the NFPA Code 1975. Training sessions vill be held quarterly.
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208a Amendment No. /7, 46
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Conani t t ce (nn e i t M Figure 6.2.I llouton Ihlluon Company -- Organization for Operation Of Pilgrlin 1
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Amencinient. No. 71,30,46
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- NRC REACTOR OPERATOR LICENSE Fil4RIN 1 STATION ORGA1883ATION SRO - NRC Si;WIOR REACTOR OPEAATOR LICENSE FIGURE 4.2.2 210 Amendment No. 46
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> N FIGURE 6.2.3 ADMINISTRATION OF THE PII4 RIM NUC1. EAR PLANT FIRE PREVE TION AND PROTECTION PROGRM NUCLEAR OPERATIONS MANK,ER DEPUTY MANAGERS PIIERIM STATION FIRE PREVENTION AND PROTECTION OFFICER FIRE CHIEF (WATCH ENGINEER)
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210a Amendment No. 29, 46
6.5 REVIW AND AUDIT O,PERATIONS REVIEW CCMMITTEE (ORC) 1.
FUNCTION The ORC shall function to advise the Nuclear Operations Manager on all matters related to nuclear safety.
2.
CCMPOSITION The ORC shall be composed of the:
Chairman:
Deputy Nuclear Operations Managers Member:
Management Services Group Leader Me:nber:
Chief Operating Engineer Member:
Chief Trthnical Engineer Member:
Chief Maintenance Engineer Member:
Chief Radiological Engineer 3.
ALTULNA*T.S Alternate members shall be appointed in writing by the ORC Chairman to serve on a temporary basis; however, no more than two alternates shall participate in an ORC quorum at any one time.
4.
MEETING FREQUENCY The ORC shall meet at least once per calendar month and as convened by the ORC Chairman.
3.
QUORUM A quorum of the ORC shall consist of the Chairman and three members including alternates.
6.
RESPONSIBILITIES The ORC shall be responsible for:
Review of 1) all procedures required by Specification 6.8 2.
and changes thereto, 2) any other proposed procedures or changes thereto that affect nuclear safety.
Review of all proposed tests and experiments that affect nuclear b.
safety.
Review of all proposed changes to the Technical Specifications.
c.
d.
Review of all proposed changes or modifications to plant systems or equipment that affect nuclear safety.
(
Investigation of all violations of the Technic.:1 Specifications anc e.
shall prepare and forward a report covering evaluution and recom-mandation to prevent recurrence to the Nuclear Operations Manager and to the NSRAC Chairman.
Amendmant No. 46 212
.o I.
f.
Review of facility operations to detect potential safety hazards.
g.
Performance of special reviews and investigations and reports thereon as requested by the NSRAC Chairnan.
h.
Review of the Station Security Plan and implementing procedures and changes to the plan and procedures.
1.
Review of the Smergency Plan and 1_plet=enting procetures and changes to the plan and procedures.
7.
AUTHORITY The ORC shall:
a.
Inform the Nuclear Operations Manager in writing their approval or disapproval of ite=s considered under 6.5.A.6(a) through (d) above.
b.
Render deter =1 nations in writing with regard to whether or not each item considered under 6.5.A.6(a) through (e) above constitutes an unreviewed safety question.
c.
Provide imediate written notification to the Nuclear Operations Manager and the Nuclear Safety Raview and Audit Cemittee of disagreement between the ORC members and the ORC Chairman.
The Nuclear Operations Manager shall have responsibility for resrlution for such disagree =ents pursuant to 6.1 above.
8.
RICORDS The CRC shall maintain written minutes of each meeting and copies shall be provided to the Nuclear Operations Manager and NSRAC Chairman.
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3.
NUC'ZAR SATITY RIVIIW AND AUDIT C0!Cu..:.:. (NSRAC) l 1.
FUNC ION The NSRAC shall function to provide independent review and audit of l
designated activities in the areas of:
l l
1.
nuclear pcuer plant operations; 2.
nuclear engineering; 3.
chemistry and radiochemistry; 4.
metallurgy; 5.
inscr.nnestation and centrol; 6.
radiological safety;.
7.
mechanical and electrical engineering; 8.
quality assurance practices 9.
fire protection 2.
COMPOSITION The ::SRAC Chairst.n and other members shall be appointed by the Vice
?rasident - Nucle.ar, or such other person as he shall designate.
NSRAC members shall collectively possess experience and competence required to review and audit the designated areas noted in 6.5 4.1.
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Amendment No. 23, 46
b.
Reports of reviews encompassed by Section 6.5.3.7 e, f, g and h above, shal; be prepared, approved and forwarded to the Vice President-Nuclear, with a copy to che Nuclear Operations Manager within 21 days following the cor.;,letion of the review.
c.
Audit reports encompassed by Section 6.5.3.8 above shall be forwarded to the Vice President-Nuclear and to the management positions responsible for the areas audited within 30 days after completion of the audit.
6.6 RI?CRTA3LI OCCURRE'ICI ACTION _
ne following actions shall be taken in the event of a reportable occurrence:
A.
The Commission shall be notified and/or a report submitted pursuant to the requirements of Specification 6.9.
B.
Each Reportable Occurrence Report submitted to the Commission shall be reviewed by the ORC and submitted to the NSRAC Chairman and the Nuclear Operations Manager.
1 6.7 S A: :.. : IIMIT VIOLA
- ION The following actions shall be taken in the event a Safety Limit is violated:
A.
he provisions of 10 CFR 50.36(c) (1) (1) shall be complied with i=ediately.
B.
The Safety L1=it Violation shall be reported to the Commission, the Nuclear Operations Manager and to the NSRAC Chair =an i==ediately.
C.
A Safety Limit violation Report shall be prepared. The report shall be reviewed by the CRC. This report shall describe (1) applicable i
circumstances preceding the violation, (2) effects of the violation upon facility components, systems or structures, and (3) corrective action taken to prevent recurrence.
D.
The Safety Limit Violation Report shall be submitted to the Commission, the NSRAC Chairman and the Nuclear Operations Manager within 14 days of the violation.
6.S PRCCI:CRIS A.
IJritten procedures and adMMetrative policies shall be established, i=ple=ented and =aintained that meet or exceed the requirements and reco=endations of Sections 5.1 and 5.3 of ANSI N18.7 - 1972 and I
Appendix "A" of USNRC Regulatory Guide 1.33, except as provided in 6.3.3 and 6.8.C below.
216 Amendment No. 30, 46
B.
Each procedure and administratf.ve policy of 6.8.1 above, and changes thereto, stall be reviewed by the ORC and approved by the ORC Chairman prior to implementation and periodically forth in station procedures.
as set C.
Te=porary changes to proced.2res of 6.8.A above may be made provided:
, 1.
The intent of the original procedure is not altered.
2.
The change is approved by two members of the plant msnagement staff, at least cne of whom holds a Senior Reactor Operator's license on the unit affected.
3.
The change is documented, reviewed subsequently by the ORC, and ap-proved by the ORC Chair =an within 7 days of implementation.
D.
~4rit:en procedures to implement the Fire Protection Program shall be established, implemented and sa h tained.
6.9 REPOR C G REQUIR. NS In addition to the applicable reporting requirements of Title 10, code of Federal Regulations, the following identified reports shall be submitted to the Director of the appropriate Regional Office of Inspection and Enforce =ent unless otherwise noted.
A.
Routine Reports 1.
Startup Resort. A summary report of plant startup and power escalation casting shall be submitted following (1) receipt of an operating license, (2) amend =ent to the license involving a planned increase in power level, (3) installation of fuel that has a different das?-gu or has been manuf actured by a different fuel supplier, and (i)
=odifications that may have significantly altered the nuclear, thermal, or hydraulic performance of the plant.
The report shall address each of the tests identified in the FSAR and siall in general include a description of the measured values of the operating conditions or character-1stics obtained durir.3 the test program and a comparison of these values with design predictions and specifications.
Any corrective actions that were required to obtain satisfactory operation shmil also be described. Any additional specific details required in license conditions based on other commitments shall be included in this report.
Startup reports shall be submitted within (1) 90 days following completion of the startup test program, (2) 90 days following resumption or commencement of commercial power operation, or (3) 9 months following initial criticality, whichever is earliest. If the Startup Report does not cover all three events (i.e., initial criticality, completion of startup test program, and resu=ption or commencement of comnercial power operation), supple =entary reports shall be submitted at least every three months until all three events have been completed.
l Amendment No. U, M, 46 L.
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