ML20074A095
| ML20074A095 | |
| Person / Time | |
|---|---|
| Site: | Pilgrim |
| Issue date: | 04/26/1983 |
| From: | Vassallo D Office of Nuclear Reactor Regulation |
| To: | Boston Edison Co |
| Shared Package | |
| ML20074A096 | List: |
| References | |
| DPR-35-A-069 NUDOCS 8305120169 | |
| Download: ML20074A095 (13) | |
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UNITED STATES 8
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NUCLEAR REGULATORY COMMISSION c
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WASMNG TON,0. C. 20665
's, BOSTON EDISON COMPANY DOCKET NO. 50-293 PILGRIM NUCLEAR POWER STATION AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 69 License No. DPR-35 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Boston Edison Co'mpany (the licensee) dated October 25, 1982 as revised March 2, 1983 complirs with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and re-gulations set forth in 10 CFR Chapter I; B.
The facility will operate 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 coc?liance,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 3.8 of Facility Operating License No. DPR-35 is hereby j
l amended to read as follows:
B.
Technical Specifications l
The Technical Specifications contained in Appendix A, as revised through Amendment No.69, are hereby incorporated in the license.
The licensee shall operate the facility in accordance with the Technical Specifications.
8305120169 830426 PDR ADOCK 05000293 P
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This license amendment is effective as of the date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
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Domenic B. Vassallo, Chief Operating Reactors Branch #2 Division of Licensing
Attachment:
Changes to the Technical Specifications Date of Issuance:
April 26,1983 I
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ATTACHMENT TO LICENSE AMENDMENT NO. 69 3
FACILITY OPERATING LICENSE NO. DPR-35 00CKET NO. 50-293 1
Replace the following pages of the Appendix "A" Technical Specifications i
with the enclosed pages. The revised pages are identified by Amendment j
number and contain a vertical line indicating the area of change.
- I Remove Insert
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i 208 208 l
208a 208a 209 209 210 210 210a 1
211 fil 212 21 2 213 213
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214 214 215 21 5 I
216 216 i
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1 6.0 ADMINISTRATIVE CONTROLS 6.1 RESPONSIBILITY The Station Manager shall be accountable for overall facility operation.
In his absence the Station Manager shall designate in writing the individual to assume this responsibility.
6.2 ORGANIZATION A.
OFFSITE The Company organization for station management and technical support shall be as shown on Figure 6.2.1.
B.
FACILITY The Facility organization shall be as shown'en Figure 6.2.2 and:
1.
Each on duty shift shall be composed of at least the minimum shif t 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.
At least two Licensed Operators shall ba 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 hlTERATIONS performed while fuel is ir the reactor vessel after the initial fuel 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 responsibilities during this operation.
l S.
A Fire Brigade of 5 members including a Fire Brigade Leader shall be maintained on site at all times. This excludes 3 memoers of the minimum shift crew necessary for safe shutdown and any personnel required for other essential functions during a fire emergency.
6.3 FACILITY STAFF QUALIFICATIONS The qualifications with regard to educational and experience backgrounds of the facility staff at the time of appointment to the active position shall meet the requirements as described in the American National Standards Institute N18.1-1971, " Selection and Training of Personnel for Nuclear Power Plants." In addition, the individual performing the function of Radiation Protection Manage shall meet or exceed the qualifications of Regulatory Guide 1.8, September,1975.
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Amendment No. 76 69 l
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6.4 TRAINING r
A retraining and replacement training program for the facility staff shall be maintained under the direction of the Training Manager. The training programs for the licensed personnel shall meet or exceed the requirements and recomendations of Section 5.5 of ANSI N18.1-1971 and Appendix A of 10 CFR Part 55. The training programs for the Fire Brigade shall meet or exceed the requirements of NFPA Standard No. 27-1975 " Private Fire Brigade". Fire Protection Training sessions will,be held quarterly.
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Amendment No, ff, Ag 69
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Chief Executive Officer I
i Sr. Vice President Nuclear t
bclear Safety Review an edi Cwittu Ope Review l y..,
g i
bsite 5afety &
8 Performance Group Leader (caC) (Onsite)
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l II'* ESId'*E Vice President A lete Operations leuclear Engineerfag eng Quality Assurance j
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Iloclear Operatists e g
Quality Assurance Ileclear Engineering Seppert.
Trelm:.
Statten Manager - PNP 5 g
Manager Mene r Menac,er
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(onsite)
(of fsite)
(offs te)
(of f',itel i L--
8 Wesue) l s
Operations Review Casselitee (onsite)
Plant Staff (onsite)
Boston Edison company - organization fer operation Of Pilgrim I
- Adninistratively respon-sible for Fire Protection
& Station Security Amendnant No. 11. 39, K 69
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figure 6.2.1
F P!LCHIM NUCl. EAR POWER STATION c+
STATION MANAGER g
(ORC)
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FIRE PROTECTION &
SECURITY I
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I CillEF OPERATING ClllEF CillEP STATION CllIEF RAD 10lDCICAL SERVICES TECIINICAL ENGINEER (ORC)
MAINTENANCE (SRO)
ENGINEER (ORC)
, ENGINEER (ORC)
CROUP LEADER ENGINEER (ORC)
WATCil TECilNICAL TECilNICAL TECIINICAl.
TECilNICAL ENGINEER (S)
STAFF STAFF STAFF STAFF (Sito)
. Mechanical
. Radiation Pro-
= llousekeeping
.On-site Engin-
. Electrical tection
- Clerical eering
- Instrumentation
. Chemistry
- Waste llanage-
- Reactor Engin-
& Control ment eering OPERATING SUPERVISOR (S)
ORC
- Member of ORC RO
- NRC Reactor Operator License (RO)
- NRC Senior Reactor operator 1,1 cense
- Reports administratively to offstro Manager Nuclear Operations Support Pilgrim Station Organization NUCLEAR Figure 6.2.2 Pl. ANT OPERATOR
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PILGRIM NUCLEAR POWER STATION MINIMUM OPERATING SHIFT CREW COMPOSITION l
TECHNICAL SPECIFICATION TABLE 6.2-1 STATION CONDITION
- CREW MINIMUM NUMBER ON DUTY OPERATING Licensed Senior Reactor Operator 1
2 Licensed Reactor Operator 4
2 Unlicensed Operator j
1 1
COLD SHUTDOWN Licensed Senior Reactor Operator 1
AND Licensed Reactor Operator 1
REFUELING Unlicensed Operator
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None Required 1
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- Higher grade l'icensed operators may take the place of lower grade licensed or unlicensed persennel.
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- Provides an On-Shift Technical Advisor who has a bachelor's degree or equivalent (1) in a scientific or engineering dicipline with specific training in plant design, and response and analysis of the plant for transients and accidents.
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(1) Or equivalent is defined as an Associate Degree in nuclear or mechanical engineering plus 5 years nuclear experience.
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Amendment No.-
AS 69
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6.5 REVIEW AND AUDIT A.
OPERATIONS REVIEW COMMITTEE (ORC) 1.
FUNCTION The ORC shall function to advise the Station Manager on all matters related to nuclear safety.
2.
COMPOSITION i
The ORC shall be composed of the i
Chaiman:
Station Manager i
Member:
Chief Operating Engineer Member:
Chief Technical Engineer Member:
Chief Maintenance Engineer Member:
Chief Radiological Engineer l
Member:
Onsite Safety & Performance Group Leader The ORC Chaiman may appoint subcommittees. composed of personnel who are not members of ORC to perform staff work necessary to the efficient functioning of ORC.
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ALTERNATES Alternate members shall be appointed in writing by the ORC Chaiman 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 Chaiman.
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5.
QUORUM A quorum of the ORC shall consist of the Chaiman and a majority of members including alternates.
6.
RESPONSIBILITIES The ORC shall be responsible for:
a.
Review of 1) all procedures required by Specification 6.8 and changes thereto, 2) any other proposed procedures or changes thereto that affect nuclear safety.
b.
Review of all proposed tests and experiments that affect nuclear safety.
c.
Review of all proposed changes to the Technical Specifications, d.
Review of all proposed changes or modifications to plant systems or equipment that affect nulcear safety, e.
Investigation of all violations of the Technical Specifications and shall prepare and forward a report covering evaluation and recomendations to prevent recurrence to the Vice President-Nuclear Operations and to the NSRAC Chaiman.
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. Amendment #
69
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 Chairman, h.
Review of the Station Security Plan and implementing procedures and changes to the plan and procedures.
1 1.
Review of the Emergency Plan and implenenting procedures and changes to the plan and procedures.
- j. Review the Station Fire Protection Plan and implementing procedures and changes to the plan and procedures.
k.
Render determinations in writing with regard to whether or not each item considered under 6.5.A.6(a) through (e) above con-stitutes an unreviewed safety question.
1.
Provide immediate written notification to the Vice President -
Nuclear Operations and the Nuclear Safety Review and Audit Connittee, of disagreement between.the ORC members and the ORC Chairman. The Vice President - Nuclear Operations shall have responsibility for resolution for such' disagreements.
7.
AUTHORITY The ORC shall report to and advise the Station Manager on those areas of responsibility specified in Section 6.5.A.6.
8.
RECORDS The ORC shall maintain written minutes of each meeting and copies shall be provided to the Vice President - Nuclear Operations.
B.
NUCLEAR SAFETY REVIEW AND AUDIT COMMITTEE (NSRAC) 1.
FUNCTION The NSRAC shall function' to provide independent review and audit of designated activities in the areas of:
1.
nuclear poner plant operations; 2.
nuclear engineering; 3.
chemistry and radiochemistry; 4.
metallurgy; 5.
instrumentation and control; 6.
radiological safety; 7
mechanical and electrical engineering; 8.
quality assurance practices 9.
fire protection 2.
COMPOSITION The NSRAC Chairman and other members shall be appointed by the l
Senior Vice President - Nuclear, 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.B.1.
Amendment,29, #6 69
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The collective competence of the committee will be maintained as changes to the membership are made. The membership shall consist of a minimum of five persons.
3.
ALTERNATES Alternate members shall be appointed in writing by the Senior Vice President - Nuclear or the Chaiman to serve on a temporary basis; however, no more than two alternates shall participate in a quorum at any one time.
4.
CONSULTANTS Consultants shall be utilized as detemined by the NSRAC Chaiman to provide expert advice to the NSRAC.
l 5.
MEETING FREQUENCY
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The NSRAC shall meet at least once per six months.
6.
QUORUM A quorum of the NSRAC shall consist of the Chaiman and a majority of the NSRAC members including alternates. No more than a minority of the quorum shall have line responsibility for operation of the facility.
7.
REV!!'d The NSRAC shall review:
a.
The safety evaluations for:
(1) Changes to procedures, equipment or systems and (2) Tests or experiments completed under the provision of Section 50.59, 10 CFR to verify that such a'ctions 'did not constitute an unreviewed safety question.
I b.
Proposed changes to procedures, equipment or systems which involve an unreviewed safety question as defined in Section 50.59, 10 CFR.
c.
Proposed tests or experiments which involve an unreviewed safety question as defined in Section 50.59, 10 CFR.
d.
Proposed cbnges in Technical Specifications or operating license.
e.
Violations cf applicable statutes, codes, regulations, orders, Technical Specifications, license requirements, or of internal procedures or instructions having nuclear safety significance.
f.
Significant operating abnomalities or deviations from nomal and expected perfomance of plant equipment that effect nuclear safety.
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Amendment No. 69
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l g.
All events which are required by regulation or' Technical Specifications to be reported to the NRC in writing within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
i h.
Any other matter involving safe operation of the nuclear plant which NSRAC deems appropriate for consideration or which is referred to NSRAC by the onsite operating organization or by other functional organizational units within Boston Edison.
1.
Reports and meeting minutes of the Operations Review Connittee.
i 8.
AUDITS Audits of facility activities shall be performed under the cognizance of the NSRAC. These audits shall enccmpass:
a.
The conformance of facility operatien to provisions contained within the Technical Specifications and applicable license conditions at least once per year.
b.
The training and qualifications of the entire facility staff at least once per year.
c.
The results of all actions required by deficiences occurring in facility equipment, structures, systems or method of operation that affect nuclear safety at least once per six months.
d.
The performance of all activities required by the Quality Assurance Program to meet the criteria of Appendix "B",10 CFR 50, at least once per two years.
e.
The Emergency Plan and implementing procedures at least once per two years,
.)
f.
The Station Security Plan and implementing procedures at least once per two years, g.
Any other area of facility operation considered appropriate by the NSRAC or the Senior Vice President - Nuclear.
h.
The Fire Protection Program and implementing procedures at least l
once per two years.
9.
AUTHORITY The NSRAC shall report to and advise the Senior Vice President -
Nuclear on those areas of responsibility specified in Section 6.5.B.7 and 6.5.B.8.
- 10. RECORDS l
Records of NSRAC activities shall be prepared, approved and distributed as indicated below:
a.
Minutes of each NSRAC meeting shall be prepared, approved and forwarded to the Senior Vice President - Nuclear, NSRAC members, and others the Chairman may designate, within 14 days following each meeting.
Amendment No. 29, 30 69
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b.
Reports of reviews encompassed by Section 6.5.8.7 e, f, g and h.
I above, shall be prepared, approved, and forwarded to the Senior Vice President - Nuclear, with a copy to the Station Manager within j
21 days following the completion of the review.
l Audit reports encompassed by Section 6.5.B.8 above shall be c.
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forwarded to the Senior Vice President - Nuclear and to the j
management positions responsible for the areas audited within 30 days after completion of the audit.
i 6.6 REPORTABLE OCCURRENCE ACTION j
The following actions shall be taken in the event of a reportable occurrence:
A.
The Comission shall be notified and/or a report submitted pursuant to the requirements of Specification 6.9.
l B.
Each Reportable Occurrence Report submitted to the Comission shall be reviewed by the ORC and submitted to the NSRAC Chaiman and the Station Manager, 6.7 SAFETY LIMIT VIOLATION j
The following actions shall be taken in the event a Safety Limit is violated:
A.
Theprovisionsof10CFR50.36(c)(1)(i)shallbecompliedwith imediately.
B.
The Safety Limit Violation shall be reported to the Comission, the Station Manager, and to the NSRAC Chaiman imediately.
1 C.
A Safety Limit Violation Report shall be prepared. The report shall t
be reviewed by the ORC. This report shall describe (1) applicable j
circumstances preceding the violation, (2) effects of the violation upon facility components, systems or structures, and (3) corrective j
action taken to prevent recur,rence.
t D.
The Safety Limit Violation Report shall be submitted to the Comission, i
The NSRAC Chaiman, and the Station Manager within 14 days of the violation.
j 6.8 PROCEDURES A.
Written procedures and administrative policies shall be established, implemented and maintained that meet or exceed the requirements and recomendations of Section 5.1 and 5.3 of ANSI N18.7 - 1972 and Appendix "A" of UNSRC Regulatory Guide 1.33, except as pr%vided in 6.8.8 and 6.8.C below.
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Amendment No.'J0,#6 69
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