ML19351E800
| ML19351E800 | |
| Person / Time | |
|---|---|
| Site: | Haddam Neck File:Connecticut Yankee Atomic Power Co icon.png |
| Issue date: | 12/02/1980 |
| From: | Crutchfield D Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML19351E798 | List: |
| References | |
| NUDOCS 8012190321 | |
| Download: ML19351E800 (22) | |
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k UNITED STATES O ;. *i. W. IS NUCLEAR REGUL'4 TORY COMMISSION
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WASm NGTON. D. C. 20555 CONNECTICUT YANKEE ATOMIC POWER COMPANY DOCKET NO. 50-213 HADDAM NECX PLANT AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 36 License No. DPR-61 1.
The Nuclear Regulatory Comission (the Commission) has found that:
A.
The application for amendment by Connecticut Yankee Atomic Power Company (the licensee) dated February 14, 1979, as supported by information submitted by letter dated March 30, 1979, and the appli-cations for a'nendment by the licensee dated September 5.1978, ire-April 28, 1980 and July 16, 1980, comply with the standards and requ ments of the Atcmic Enerjy Act of 1954, as amended. (the Act), and the Comission's rules and regulations set forth in 10 CFR Chapter I; B.
The facility will operate in conformity with the applications, the 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 l
conducted in compliance with the Casuiission's regulations; D.
The issuance of this amendment will not be inimical 4 the common defense and security or to the health and safety of..e public; and E.
The issuance of this amendment is in accordance with 10 CPR Part j
51 of the Comission's regulations and all applicable requirements have been satisfied.
1 8012190 % l
. 2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. DPR-61 is hereby amended to read as follows:
(2) Technical Specifications The Technical Specifications contained in Appendices A and B. as revised through Amendment No.36, are hereby incorporated in the license. The licensse 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 f
Y Dennis M. Crutchfield, Chie Operating Reactors Branch #5 Division of Licensing
Attachment:
l Changes to the Technical Specifications Date of Issuance: December 2,1980 l
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ATTACHMENT TO LICENSE AMENDMENT NO. 36 FACILITY OPERATING LICENSE NO. DPR-61 DOCKET NO. 50-213 P.eplace the following pages of Appendices A and B Technical Specifications with the enclosed pages. The revised pages are identified by the captioned amendment number and contain vertical lines indicating the area of change.
REPOVE PAGES INSER PAGES (Appendix A) 4-20 4-20 4-21 4-21 6-1 6-1 6-2 6-2 j
6-3 6-3 6-5 6-5 6-Sa 6-Sa 6-6 6-6 6-7 6-7 6-9 6-9 6-11 6-11 6-12 6-12 l
6-13 6-13 6-14 6-14 (Appendix B) 5.1-2 5.1-2 5.1-3 5.1-3 5.2-2 5.2-2 4
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Basis:
The Inservice Inspection Program is based upon the ASME Code,Section XI, for Inservice Inspection, dated January 1, 1970, including Addendum I, dated December 31, 1970. Since the Haddam Neck Plant was built prior to the ISI Code, accessibility is not available for complete inspection.
Hence, there will be exceptions to the ISI Code. These exceptions are indicated by the notes in the enclosed pro-gram summary.
The initial Inservice Inspection Program is based on a 3-1/3 year plan commencing with the first refueling of April 1970.
During the 3-1/3 year period, an attempt will be made to accomplish one-third of a normal 10-year inspection interval, as specified in the Code.
CDie Code requires that at least 25 percent of the required examinations be completed by the expiration of one-third of a 10-year inspection interval )
The intent of this short-term inspection is to allow a period for developing experience with the examination techniques, application of newly developed equipment, and to prove accessibility. These experiences may serve to increase or decrease the extent of examinations for subsequent inspection periods or to modify the techniques in order to facilitate such examinations.
In regards to the reactor surveillance capsule program there are only two capsules (Type II) containing specimens of weld metal remaining. Therefore, the first of these vill not be removed until 15 years of operation have elapsed and the second until 25 years have elapsed. This will provide the greatest amount of useful information about irradiation effects on veld metal over the lifetime of the plant.
In addition, removal of the Type I capsule at the 10 year point will confirm the noted trends and will leave three Type I capsules in standby for special purposes.
4-20 Amendment flo.,&; 36
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1.
Rese areas are presently concidered to be inaccessible for $nspecticn.
Rese cate,cr/ requirerants will be Mviewed in the future as renote e
inspecticn techr.clegy is develcped.
2.
Because of the design of the vessel penetratiens and pressure beur.darf welds, no neaningral volratric exaninatiens can be perfered. Visual exa.inatiens will be perfcmed, however, as specified in iten 1.6 of table 4.10.1.
3.
Rese exa=inatiens nay be perfc=ed at or near the end of a neral lo year inspecticn interial and will be scheduled to be perfered tr. der the inspecticn pre 7,... subsequent to the initial 31/3 year pres an.
e 4
We seface i.spection cf the closure head c9dd**g as regaired by the
/C'E Ccde has been deleted. h cladd'.g seface of the Cornecticut Yankee reacter vessel head had not been papared, prier Oc plan cperaticn, to per.it fer a neaningfal s= face exanina:icn cf this area.
5 ne flywheels shall te visually and 100% voluretrically exe.ined at the next refueling (seccnd rePxling). One different flp.t. eel s".all be exa.ined visually and'lCC5 vclestrically at every c:her succeeding afteli.g.
6.
Since nc::le type sup;c-:s exist, all of the nc::'.es with supports shall be exanined in acccrdance with ca:escry D.
The removal plan for the remaining capsules in the Connecticut Yankee 7.
reactor vessel is scheduled as follows:
2 Capsule Capsula Removal Time Predicted Exposure (E > 1MEV) N/CM Reactor Vessel ID Type Ident.
Years
- Capsule
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19 I
H 10 1.3x1019 1.Ox10 19 19 1.6x10 15 2.0x10 II D
19 2.6x1019 II E
25 3.3x10 I
B Standby f
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C Standby I
G Standbv l
S.
Be 31/3 year inspecticn interval shall not be exec edad by mere than ene year for inservice inspecticn periods to be cencura nt with plant outages.
Removal time is in approximate calendar years from the date of initial criticality (July 24, 1967) and intended to coincide with the rearest l
refueling outage to that time.
I 4-21 Amendment No. 36
6.0 AOMINISTRATIVE CONTROLS 6.1 RESPONSIBILITY 6.1.1 The Station Superintendent shall be responsible for overall l
facility operation and shall delegate in writing the succession to this responsibility during his absence.
6.2 ORGANIZATION OFFSITE 6.2.1 The offsite organization for facility management and technical support shall be as shown on Figure 6.2.1.
FACILITY STAFF 6.2.2 The Facility organization shall be as shown on Figure 6.2-2 and:
a.
Each on duty shift shall be composed of at least the minimum shift crew composition shown in Table 6.2-1.
b.
At least one licensed Operator shall be in the control room when fuel is in the reactor, c.
At least two licensed Operators shall be present in the control room during reactor start-up, scheduled
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reactor shutdown and during recovery from reactor trips.
d.
An individual qualified in radiation protection procedures shall be on site when fuel is in the reactor.
I e.
ALL CORE ALTERATIONS shall be directly suoervised 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 f.
A fire brigade of three (3) members shall be maintained on site at all times. This excludes two (2) members of the minimum shift complement necessary for safe shutdown of the plant and any personnel required for other essential functions during a fire emergency. This specification shall be effective March 1,1978.
l 6-1 Amendment No. Jp; 36
CONNECTICUT YAllMEE AT0 HIC POWER COMPANY
. _OFFSITE ORGAll!ZATI0ff i
CYAPC President NUSCO Pres.ident and Chief Operating Officer CYAPC Vice President l
i NUSCO Senior Vice President
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Operations
- l Nuclear Review Board
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ADMINISTRATIVE CONTROLS 6.3 FACILITY STAFF QUALIFICATIONS 6.3.1 Each member of the facility staff shall meet or exceed the minimum qualifications of ANS1 N18.1-1971 for comparable positions.
6.3.1.1The position of Health Physics Supervisor shall meet the following minimum qualifications:
a.
Academic degree in an engineering or science field or equivalent as per Section 6.3.1.1.c.
b.
Minimum of five years professional technical experience in the area of radiological safety, three years of which shall be in applied radiation work in a nuclear facility dealing with problems similar to those encountered in a nuclear power reactor.
c.
Technical experience in the area of radiological safety beyond the five year minimum may be substituted on a one-for-one basis towards the academic degree requirement (four years of technical experience being equivalent to a four year academic degree).
I d.
Academic and technical experience must total a minimum of nine years.
6.4 TRAINING 6.4.1 A retraining and replacement training program for the facility staff shall be maintained under the direction of the Training Coordinator assigned program responsibility and shall be in accordance with Section 5.5 of ANSI N18.1-1971 and Appendix "A" of 10 CFR Part 55.
6.4.2 A fire brigade training program shall be maintained under the direction of the training department and shall meet or exceed the intent of Section 27 of the NFPA Code 1976 ( cept that drills / training shall be conducted at least quarterly. The effective date of this specification is March 1, 1975.
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l 6.5 REVIEW AND AUDIT 6.5.1 PLANT OPERATIONS REVIEW COMMITTEE (PORC)
FUNCTION 6.5.1.lThe PORC shall function to advise the Station Superintendent on all matters related to nuclear safety.
6-5 Amendment No.,34', 36 i
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COMPOSITION 6.5.1.2 The PORC shall be composed of the:
Chairman:
Station Superintendent Member:
Unit Superintendent Member:
Station Services Superintendent Member:
Engineering Supervisor Member:
Operations Supervisor Member:
Maintenance Supervisor Member:
Instrument and Control Supervisor Member:
Reactor Engineer Member:
Chemistry Supervisor Member:
Health Physics Supervisor Men.ber:
Quality Assurance Supervisor Member:
Security Supervisor t
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6-5a
ADMINISTRATIVE CONTROLS ALTERNATES 6.5.1.3 Alternate members shall be appointed in writing by the PORC Chairman to serve on a temporary basis;,however, no more than two alternates shall participate in PORC activities at any one time.
MEETING FREQUENCY 6.5.1.4. The PORC shall meet at least once per calendir month and as convened by the PORC. Chairman.
QUORUM 6.5.1.5 A quorum of the PORC shall consist of the Chairman and four members including alternates.
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RESPONSIBILITIES 6.5.1.6 The ~PORC shall be responsible for:
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a.
Review of 1) all procedures required by Sp.ecification 6.8 and changes threto, 2) any other proposed procedures or changes thereto as determined by the Station Superintendent to 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 chan'ges or modifications to plant systems or equipment that affect nuclear safety.
e.
Investigation of all violations of the Technical Specifications and shall prepare and forward a report covering evaluation and recommendations to prevent recurrence to the System Superintendent Nuclear Operations and to the Chairman of the Nuclear Review Board.
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f.
Review c,f facility operations to detect potential safety hazards, g.
Performance of special reviews and investigations and reports thereon as requested by the Chairman of the Nuclear Review Board.
Amendment No.g 36 l
ADMINISTRATIVE CONTROLS RESPONSIBILITIES (Continued) h.
Review of the Plant Security Plan and implementing procedures and shall submit reconnended changes to the Chairman of the Nuclear Review Board.
i.
Review of the Emergency Plan and implementing procedures and shall submit recommended changes to the Chairman of the Nuclear Review Board.
j.
Render determinations in writing with regard to'whether or not each item considered under 6.5.1.6(a) through (e) above constitutes an unreviewed safety question.
AUTHORITY 6.5.1.7 The PORC shall:
a.
Report to and be advisory to the Station Superintendent on those l
areas of responsibility specified in Section 6.5.1.6 and 6.5.1.8.
b.
See 6.5.1.6.j above.
Provide timely written rotification, meeting minutes may be used c.
l for this purpose, to the System Superintendent Nuclear Operations l
l and the Chairman of the Nuclear Review Board of disagreement be-tween the PORC and the Station Superintendent however, the Station g
Superintendent shall have responsibility for resolution of such disagreements pursuant to 6.1.1 above.
l RECORDS l
6.5.1.8 The PORC shall maintain written minutes of each meeting and copies shall be provided to the System Superintendent Nuclear Operations i
and Chairman of the Nuclear Review Board.
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6-7 Amendment No. 36
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ADMINISTRATIVE CONTROLS COMPOSITION 6.5.2.2 The Chairman, members, and alternate members of the NRB shall be appointed in writing by the Vice President of Nuclear Engineering and Operations, and shall have an academic degree in engin ering i,
or physical science field; and in addition, shall have a minimum j
of five years technical experience, of which a minimum of three years shall be in their respective field of expertise.
ALTERNATES 6.5.2.3 No more than two alternates shall participate as voting members l
in NRB activities at any one time.
CONSULTANTS 6.5.2.4 Consultants shall be utilized as determined by the NRB Chairman to provide expert advice to the NR3.
MEETING FREQUENCY 6.5.2.5 The NRB shall meet at least once per six months.
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QUORUM 6.5.2.6 The minimum quorum of the NRB necessary for the performance of the l
NRB review and audit functions of these Technical Specifications
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shall consist of the Chairman or his designated alternate and at least four (4) NR3 members including alternates. No more than a ricority of the quorum shall have line responsibility for operation j
of the facility.
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6-9 Amendnent No.,267 36 l
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ADMISTRATIVE CONTROLS AUDITS 6.5.2.8 Audits of facility activities shall be perfnrmed under the cognizance of the.NRB. These audits shall encompass:
a.
The conformance of facility operation to all provisions contained within the Technical Specifications and applicable license conditions at least once per year.
b.
The performance, training and qualifications of the entire facility staff at least once per year.
c.
The results of all 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.
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 Facility Emergency Plan and implementing procedures at least once per two years.
f.
The Facility Security Plan and implementing procedures at least once per two years.
g.
Any other area of facility operation considered appropriate by the NRB or the Senior Vice President-Nuclear Engineering and
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Opeiations.
h.
The Facility Fire Protection Program and implementing procedures at least once per two years.
- i. An inspection and audit of the Fire Protection and loss prevention program shall be performed annually by an outside firm experienced in fire protection and ldss prevention.
AUTHORITY 6.5.2.9 The NRB sha's report to and advise the Senior Vice President-Nuclear l
Engineering and Operations on those areas of responsibility specified in Section 6.5.2.7 and 6.5.2.8.
Meeting minutes may be used for this purpose.
6-11 Amendment No.Jg 36
ADMINTSTRATIVE CONTROLS RECORDS 6.5.2.10 Records of NRB activities shall be prepared, approved and distributed as indicated below:
a.
Minutes of each NRB meeting shall be prepared, approved and forwarded to the Senior Vice President-Nuclear Engineering and j
Operations within 14 days following each meeting.
b.
Reports of reviews encompassed by Section 6.5.2.7.e, f, g, and h above, shall be prepared, approved and forwarded to the Senior Vice president-Nuclear Engineering and Operations within 14 days following completion of the review. Meeting minutes may be used for this purpose.
c.
Audit reports encompassed by Section 6.5.2.8 above, shall be forwarded to the Senior Vice President-Nuclear Engineering and Operations and to the management positions responsible for the areas audited within 30 days after completion of the audit.
Meeting minutes may be used for this purpose.
QUALIFICATIONS 6.5.2.11 Minimum qualifications of NRB members are as follows:
a.
Academic degree in an engineering or physical science field or equivalent as per Section 6.5.2.ll.c.
b.
Minimum of five years technical experience, of which a minimum of three years is in one or more of the areas specified in Section 6.5.2.1.
c.
Technical experience in the areas specified in Section 6.5.2.1 beyond the three year minimum may be substituted on a one for one basis towards the academic degree requirement.
(Four years of technical experience being equivalent to a four year academic degree.)
d.
Total academic and technical experience must total a minimum of nine years.
6.6 REPORTABLE OCCURRENCE ACTION 6.6.1 The following actions shall be taken for all events which are required by regulations of Technical Specifications to be re-ported 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 />.
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 Comission shall be reviewed by the PORC and submitted to the NRB and the S ystem Superintendent Nuclear Operations.
6-12 Amendment No. g 36
ADMINISTRATIVE CONTROLS 6.7 SAFETY LIMIT VIOLATION 6.7.1 The f.110 wing actions shall be taken in the event a Safety Limit 11 vi11ated:
a.
The provisions of 10 CFR 50.36 (c) (1) (1) shall be complied with immediately.
b.
The safety Limit violation shall be reported to the Commission.
l the System Superintendent Nuclear Operations and to the NRB witnin 4
one hour.
c.
.A Safety Limit Violation Report shall be prepared.
The report shall be reviewed by the PORC. 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, the NRB and the System Superintendent-Nuclear Oper-l ations within 14 days of the violation.
6.8 PROCEDURES 6.8.1 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 N18.7-1976 l
and Appendix "A" of USAEC Regulatory Guide 1.33 except as provided in 6.8.2 and 6.8.3 below.
Procedures shall be established and maintained for implementation of the Facility Fire Protection Program.
6.8.2 Each procedure and administrative policy of 6.8.1 above, and changes thereto, shall be reviewed by the PORC and approved by the Station Superintendent prior to implementation and periodically l
as set forth in each document.
l 6-13 l
Amendment No. A 36
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ADf11tilStRATIVE C0!!TROLS 6.8.3 Temporary changes to procedures of 6.8.1 above may be made provided:
- a..The intent of the original procedure is not altered.
b.
The change is approved by two members,of the plant management staff, at least one of whom holds a Senior Reactor Operator's i
License on the unit affected.
c.
The change is documented, reviewed by the PORCand approved by the Station Superintendent within 14 days of implementation.
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l Amendment No. JC 36 6-14
The Environmental Review Board shall be constituted as follows:
5.1.5.1 Membership The ERB shall consist of a minimum of five persons (with alternates) none of whom shall be directly employed by the Connecticut Yankee Atomic Power Company. As a group they will collectively provide expertise in the environmental disciplines and engineering. The collective competence of this group will be maintained as changes to membe,rship are made.
The members and alternates shall be appointed by the NUSCO Senior Vice President Nuclear Engineering and Operations.
l The ERB will obtain advice and counsel of scientific and techni-cal personnel employed by the Company or other organizations whenever necessary to carry out its responsibilities.
5.1.5.2 Meeting Frequency The ERB shall meet at least semiannually on call by the chair-man or as requested by individual members.
5.1.5.3 Quorum A quorum will consist of the majority of the designated board members or their alternates. The majority shall include the chairman or the vice-chairman or their designated alternate.
5.1.5.4 Authority The ERB shall be advisory to the NUSCO Senior Vice President l
Nuclear Engineering and Operations, the Station Superintendent, the NUSCO System Superintendent Nuclear Operations and the NUSCO Assistant Vice President Nuclear and Environmental Engineering l
as indicated in Figure 5.2-1.
5.1.5.5 Records j
5.1.5.5.1 Minutes shall be recorded for all ERB meetings. M.eetings shall be numbered in sequence and distribution shall be to the NUSCO Senior Vice President Nuclear En ineering and Operations, the l
Station Superintendent, the NUSC System Superintendenc Nuclear Operations, the NUCCO Assistarit Vice President Nuclear and l
Environmental Engt.u ering and the Chairman of the Nuclear Review Board.
5.1-2 Amendment No. / 36 I
5.1.5.5.2 Reports of all audits including recommendations of the Board shall be made in writing to the NUSCO Senior Vice President Nuclear Engineering and Operations, the NUSCO System Superinten-dent Nuclear Operations and the NUSCO Assistant Vice President Nuclear and Environmental Engineering with copies to the ' Station Superintendent.
5.1.5.5.3..
The findings of all reviews of Environmental Technical Specifi-cation violations and recommendations to prevent recurrence shall be reported in writing to the NUSCO Senior Vice President Nuclear Engineering and Operations, the NUSCO System Superintendent Nuclear Operations, the NUSCO Assistant Vice President Nuclear l
and Environmental Engineering and the Station Superintendent.
5.1.5.6 Procedures Written administrative procedures for Board operation shall be-prepared and maintained.
5.1.6 The Plant Operations Review Committee (PORC) shall be constituted as specified in Section 5.2, and shall assume the same scope of responsibility in onsite environmental matters which it holds in other operational matters. The PORC shall make recommendations to the Station Superintendent.
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._ 5.2-2 Amendment No. Jr, 36 1