ML20155B375
| ML20155B375 | |
| Person / Time | |
|---|---|
| Site: | Pilgrim |
| Issue date: | 09/26/1988 |
| From: | Wessman R Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20155B380 | List: |
| References | |
| NUDOCS 8810060286 | |
| Download: ML20155B375 (14) | |
Text
e
/p* ** coq'o, UNITED STATES
!j
, i NUCLEAR REGULATORY COMMISSION
- .. g( J,
p WASHINGTON, D. C. 20S*5 o, % \\v# f.,
~
t
/
p BOSTON EDIS0N COMPANY
, DOCKET NO. 50-293 PILGRIM NUCl. EAR POWER STATION AMENMENT TO FACll:TY OPERATING LICENSE Amendment No.122 License No. DPR-35 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment by Boston Edison Company (the licensee) dated August 6,1988 complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act),
and the Corsaission's rules and regulations 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 Comission; 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 amendme..t 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 Commission's regulations and all applicable requirement's have been satisfied.
2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and Paragraph 3.B of Facility Operating License No. DPR-35 is hereby amended to read as follows:
kk00bODG6000926 p
\\DOCM 05000073 PNU
M.
2 (2) Technical Specifications
' The Technical Specifications contained in Appendix A, as revised through Amendment No. 122
, are hereby incorporated in the license.
The licensee shall operate the facility in accordance with the Technical Specifications, t-3.
This license amendment is effective as of the date of issuance and shall be implemerted within 30 days.
FOR THE NUCLEAR REGULATORY COMMISSION Y D.
ah Richard H. Wessman, Director Project Directorate I-3 Division of Reactor Projects 1/11
Attachment:
Changes to the Technical Specifications Date of Issuar.ce:
Septenber 26, 1988 b
4 l
l 5
[
I i.
i t
i
. - -. ~ -
ATTACHMENT TO LICENSE AMENDMENT NO. 122 FACILITY OPERATING LICENSE NO. DPR-35
, DOCKET NO. 50-293 Replace the following pages of the Appendix A Technical Specifications with thr enclosed pages.
The revised pages are identified by amendment number and contain vertical lines indicating the areas of change.
Remove Pages Insert Pages iii iii 208 208 208 a 208 a Fig.6.2-1(pg.209)
Fig. 6.2-1 (pg. 209)
Fig. 6.2-2 (pg. 210)
Fig. 6.2-2 (pg. 210) 212 212 213 213
?)6 216 217 217 226 226 227 727 i
s l
l
+-------------,m--r r--
2-
,,--3--,-
+- -- - -
,--r----+-w-------
-=- - - - - -
Page No.
4.0 HISCELLANEOUS RADIOACTIVE MATERIALS SOURCES 206k 4.1 Sealed Source Contamination 206k 4.2 Surveillance Requirements 106k 4.3 Reports 2061 4.4 Records Retention 2061 5.0 HAJOR DESIGN FEATURES 206m 5.1 Site Features 206m 5.2 Reactor 206m 5.3 Reactor Vessel 206m 5.4 Containment 206m 5.5 Fuel Storage 207 5.6 Seismic Design 207 6.0 ADMINISTRATIVE CONTROLS 208 6.1 Responsibility 208 6.2 Organization 208 6.3 Facility Staff Qualifications 208a l
6.4 Training 208a 6.5 Review and Audit 212 6.6 Reportable Event Action 216 6.7 Safety Limit Violation 217 6.8 Procedures 217 6.9 Reporting Requirements 218 6.10 Record Retention 224 6.11 Radiation Protection Program 226 6.12 (Deleted) 6.13 High Radiation Area 226 6.14 Fire Protection Program 227 Ooerational Obiectives Surveillance 7.0 RADIOLOGICAL ENVIRONMENTAL HONITORING PROGRAM 8.0 229 7.1 Monitoring Program 8.1 229 7.2 Dose - Liquids 8.2 232 7.3 Dose - Noble Gases 8.3 233 7.4 Dose - Iodine-131, Iodine-133, 8.4 234 Radioactive Material in Particulate Form, and Tritium 7.5 Total Dose 8.5 234 Amendment No. L5, 45, 88, 89, 95,122 111 1
6.0 ADMINISTRATIVE CONTROLS 6.1 RESPONSIBILITY The Station Director shall be accountable for overall facility operation.
In his absence, the Station Director 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.
l B.
FACILITY The Facility organization shall be as shown on Figure 6.2-2 and:
l 1.
Each on duty shift shall be composed of at least the minimum shift crew composition shown in Table 6.2-1.
l 2.
When the unit is in an operational mode other than cold shutdown or refueling, a person holding a Senior Reactor Operator License shall be present in the control room at all times.
In addition to this Senior Operator, a Licensed Operator or Senior Operator shall be present at the controls when fuel is in the vessel.
3.
At least two Licensed Operators shall be present in the control room durin2 reactor startup, scheduled reactor, shutdown and during recovery frca reactor trips.
4.
An individual qualified in radiation protection procedures shall be on site when fuel is in the reactor.
3.
ALL CORE ALTERATIONS performed while fuel is in 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.
6.
A Fire Brigade of 5 members including a Fire Brigade Leader shall be maintained on site at all times.
This excludes 3 members of the minimum shift crew rGeessary for safe shutdown and any personnel required for'other essential functions during a fire emergency.
C.
CHANGES TO THE ORGANIZATION Changes may be made to the organization without prior license amendment provided that the NRC is notified in writing within 30 days and a revision to Section 6.2 is included in a subsequent license amendment request.
l Amendment No. 69, 80, 88, 122 208
6.0 ADMINISTRATIVE CONTROLS 6.3 FACILITY STAFF OUALIFICATIONS 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 Manager shall meet or exceed the qualifications of Regulatory Guide 1.8, September,1975.
6.4 TRAINING A retraining and replacement training program for the facility staff shall be maintained under the direction of the Nuclear Training Department Manager.
The training programs for the licensed personnel shall meet or exceed the requirements and recommendations of Section 5.5 of ANSI N18.1-1971 and Appendix A of 10CFR 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.
l l
l Amendment No. 41, A6. 69, 88, 122 208a l
t
3 Chief Executive Officer g
5 i
Senior Vice President -
l Nuclear
]
I Nuclear Safety Review and Audi Comrnittee Vice Presidert -
Emergency Preparedness Station Director QuaRy Assurance Nuclear Engineenng Departrnent Managar Departmerd Manager (Offsite)
(Onsite) 09erations Revew Committee l
(Onsite)
Nuclear Nuclear Management Engineering l
l l
l Senrices Depanmem Plant Sopport Plant Manager Planning & Outage NuclearTraining Depanant Manager Department (Orisite)
Depanurg Npanmert Manager (Offsite)
Manager Manager
(
e)
(Offsite)
(Onsite)
(Onsite) t Boston Edison Company Organization for Management and Technical Support of Pilgrim Station 3
Fiaure 6.2-1 e
=.
>3 Station Dkector g
l a
t
[
Operations Review Cor irrittee D
k Planning & Outage Nuclear Training Plant Support Plant Manager Department Manager Department Manaoer Department Manager I
Moddication & Major Operations Traicing
-Gre Protection Division Manager Plant Maintenance
_l Maintenance Section Manager Section Manager Section Manager RadologcalSection Manager i
TechncalSection Manager v
(SRO)
Services Section Manager TNITrainN Mann% & Outage
-Radiation Protection Manager Section Manager r
Sectio M r
Assessment & Support l
Section Manager
-Chief Operating Engneer(SRO)
Facilities Secten Manager huclear Watch Engineers (sRO)
Luuciea, Ope,, ions supe,viso,s (sRO3 Nuclear Plant Roador Operators (RO)
RO-Licensed Reactor Operator
-Chemistry Division Ma ager SRO-Licensed Senor Readct Operator
-Operations Support Division Manager 1 The Radiation Protection Manager has hift Technical Advsors direct access to the Station Dirccior.
g Pilgrim Station Organization Fiaure 6.2-2 o
6.5 REVIEW AND AUDIT A.
OPERATIONS REVIEW COMMITTEE (ORC) 1.
FUNCTION The ORC shall function to advise the Station Director on all l
matters related to safety.
2.
COMPOSITION The ORC shall be composed of the Technical Section Manager, who shall serve as ORC Chairman, and at least six members, who shall be appointed in writing by the Station Director from senior experienced onsite individuals, at the manager level or equivalent, representing each of the following disciplines:
plant operations, plant maintenance, plant technical, reactor engineering, radiation protection, and chemistry.
3.
ALTERNATES Alternates shall be appointed in writing by.the Station Director l
to serve on a temporary basis.
4.
MEETING FRE00ENCY The ORC shall meet at least once per calendar month and as convened by the ORC Chairman.
B 5.
000 RUM A quorum of the ORC shall consist of the Chairman or designated alternate and a trajority of members / designated alternates; however, no more than two alternates shall be allowed to meet quorum requirements.
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 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 nuclear safety.
Amendment No. 46, 69, 88, 122 212
6.5.A.6 RESPONSIBILITIES (Continued) l e.
Review of facility operations to detect potential safety hazards.
f.
Review of the Station Security Plan and implementing procedures and changes to the plan and procedures.
g.
Review of the Emergency Plan and implementing procedures and changes to the plan and procedures, h.
Perfori.ance of special reviews and investigations and reports D ereon as requested by the Nuclear Safety Review and Audit C.cmittee (NSRAC) Chairman, i.
Investigation of all violations of the Technical Specifications and shall prepare and forward a report covering evaluation and recommendations to prevent recurrence to the Station Director, the NSRAC Chairman, and the Senior Vice President - Nuclear, j.
Review the Station Fire Protection Plan and implementing procedures and changes to the plan and procedures.
The ORC Chairman may appoint subcommittees composed of personnel who are not members of ORC to perform staff work necessary to the efficient functioning of ORC.
7 AUTHORITY a.
Recommend in writing to the Station Director the approval l
or disapproval of items considered under 6.5.A.6(a) through (d) above.
b.
Render determinations in writirg with regard to whether or not each item considered under 6.5 A.6(a) through (d) above constitutos an unreviewed safety question.
c.
Provide immediate"vritten notification to the Station Director, the Nuclear Safety Review and Audit Comittn, and the Senior Vice President - Nuclear of dist.greement between the ORC Hembers and the ORC Chairman.
The Station Director shall have responsibility for resolution of such disagreements.
8.
RECORDS The ORC shall maintain written minutes of each meeting and copies shall be forwarded to the Station Director and the NSRAC Chairman.
Amendment No. 29, 46, if, 88,122 213
5.5.B.6 AUDITS (Continued) l
~
c.
The results of all actions required by deficiencies occurring in facility equipment, structures, systems or method of operation e 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 once per two years.
9.
NLTHORITY 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 Records of NSRAC a:tivities 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 otrt:rs the Chairman may designate.
b.
Reports of reviews encompassed by Section 6.5.B.7.e, f, g and h above, shall be prepared, appro/ed and forwarded to the Senior r
Vice President - Nuclear, with a copy te the Station Director within 21 days following the completion of the review.
I c.
Audit reports encompassed by Section 6.5.B.8 tbove shcIl be forwarded to the Senior Vice President - Nucl?ar and to the management positions responsible for the areas audited within 30 days after completion of the audit.
6.6 REPORTABLE EVENT ACIl0B The following actions shall be taken for each reportable event:
A.
The Commission shall be notified and/or a report submitted pursuant to the requiren,ents of either 10 CFR 50.72 or 10 CFR 50.73.
B.
Each Reportable Event Report submitted to the Commission shall be reviewed by the ORC and submitted to the NSRAC Chairman and the Station Director.
Amendment No. A6, 69, 74, 88,104,122 216 r
6.7 SAFETY LIMIT VIOLATION The following actions shall be taken in ti:e event a Safety Limit is violated:
A.
The provisions of 10 CFR 50.36(c) (1) (i) shall be complied with immediately.
B.
The Safety Limit Violation shall be reported to the Commission within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> per 10CFR50.36(c)(6) and 50.72, and to the Station Director l
and the NSRAC Chairman immediately.
C.
A Safety Limit Violation Report shall be prepared.
The report shall be reviewed by the ORC.
This report shall describe (1) applicable 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 within 30 days in accordance with 10CFR50.36(c)(7) and 50.73 and to the NSRAC Chairman and the Station Director.
l 6.8 PROCEDURES A.
Written procedures and administrative policies shall be established, implemented and maintained that meet or exceed the requirements and recommendations of Sections 5.1 and 5.3 of ANSI N18.7 - 1972 and Appendix "A" of USNRC Regulatory Guide 1.33, except as provided in 6.8.8 and 6.8.C below.
B.
Each procedure of 6.8.A above, and changes thereto, shall be reviewed by the ORC and approved by the responsible department manager prior to l
implementation.
These procedures shall be reviewed periodically as set forth in administrative procedures.
EDTE:
ORC review and approval of procedures for vendors / contractors, who have a QA Proqram approved by Boston Edison Company, is not required for work performed at the vendor / contractor facility.
C.
Temporary changes to procedures 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 management staff, at least one of whom holds a Senior Reactor Operator's license on the unit affected.
3.
The change is documented, subsequently reviewed by the ORC within 7 days of implementation, and approved by the responsible department manager.
D.
Written procedures to implement the Fire Protection Program shall be established, implemented and maintained.
Amendment No. 29, 30, 46, 74, 88,122 217
~
6.10.B RECORD RETENTION (Continued) 6.
Records of gaseous and liquid radioactive material released to the environs.
7.
Records of transient or operational cycles for those facility components designed for a limited number of transier.ts or cycles.
8.
Records of training ar.d qualification for current members of the plant staff.
9.
Records of in-service inspections performed pursuant to these Technical Specifications.
10.
Records of Quality Assurance activities required by the QA Hanual.
11.
Records of reviewt performed for changes made to procedures or.
equipment or reviews of tests and experiments pursuant to 10 CFR 50.59.
12.
Records of meetings of the ORC and the NSRAC.
13.
Records for Environmental Qualification.
6.11 86DIATION PROTECTION PROGRAM Procedures for perscnnel radiation protection shall be prepared consistent with the requiraments of 10 CFR Part 20 and shall be approved, maintained and adhered to for t.11 operations involving personnel radiation exposure.
J 6.12 (Deleted) 6.13 RIGH RADIAllQ.N_AR_EA (OFTIONAL) 6.13.1 In lieu of the "control cevico" or "alarm sign 11" required by paragraph 20.203(c)(2) of 10 CFR 20, each high radiation area in which the intensity of radiation is greater than 100 mre:n/hr but less than 1000 mrem /hr shall be barrict.ded and conspicuously coated as a high radiation area and entrance thereto shall Le controlled by requi-ing issuance of a Radiation Work Permit *. Any individual or group of individuals permitted to enter such arcas shall be provided with or accompanied by one or more of the following:
a.
A radiation monitoring device which continuously indicates the radiation dose rate in the area.
Health Physics personnel or personnel escorted by Health Physics personnel shall be exempt from the Rr4P issuance requirements during the performance of this assigned radiation protection duties, provided they comply with approved radiation protection procedures for entry into high radiation areas.
Amendment No. 30, 45, 95, 122 226
6.13.1 HIGH RADIATION _ AREA (Continued) l b.
A radiation monitoring device which continuously integrates the radiation dose rate in the area and alarms when a preset integrated dose is received.
Entry into such areas with this monitoring device may be made after the dose rate level in the area has been established and personnel have been made knowledgeable of them, c.
An individual qualified in radiation protection procedures who is equipped with a radiation dose rate monitoring device.
This individual shall be responsible for providing positive control over the activities within the area and shall perform periodic radiation surveillance at the frequency specified by the Radiation Protection Hanager in the Radiation Work Permit.
l 6.13.2 The requirements of 6.13.1, above, shall also apply to each high radiation area in wnich the intensity of radiation is greater than 1000 meem/hr.
In addition, locked doors shall be provided to prevent U : dh ri:od entry into such areas and the keys shall be maintained under the administrative control of the Nuclear Hatch Engineer on duty and/or the Radiation Protection Manager.
6.14 FIRE PROTECTION PROGRAM The following inspections and audits shall be performed:
1.
An independent fire protection inspection and audit shall be performed annually utilizing either qualified off-site licensee personnel or an outside fire protection firm.
2.
An inspection and audit by an outside qualified fire consultant shall be performed at intervals no greater than 3 years.
Amendment No. 30, 45, 122 227
\\