ML17318A448
| ML17318A448 | |
| Person / Time | |
|---|---|
| Site: | Cook  |
| Issue date: | 11/09/1979 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML17318A447 | List: |
| References | |
| NUDOCS 7911260255 | |
| Download: ML17318A448 (13) | |
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UNITEDSTATES NUCLEAR REGULATORY COIYIMISSION WASHINGTON, D. C. 20555 INDIANA AND MICHIGAN ELECTRIC COMPANY INDIANA AND MICHIGAN POWER COMPANY DOCKET NO. 50-316 DONALD C.
COOK NUCLEAR PLANT UNIT NO.
2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.
14 License No. DPR-74 1.
The Nuclear Regulatory Commission (the ComrIIission) has found that:
A.
The application for amendment by Indiana and Michigan Electric Company and the Indiana and Michigan Power Company (the licensees) dated August 24, 1979 and portions of letters dated December 22, 1978 and February 13, 1979 complies with the standards and require-IIIenis of the Atomic Energy Act of 1954, as amended '.<the Act) and the Commission,'s rules and regulations set fortn 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 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 requi rements have been satisfied.
II
1 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-74 is hereby amended to read as follows:
4 (2)
Technical S ecifications The Technical Specifications contained in Appendices A and 8, as revised through Amendment No.
14, are hereby incorporated in the license.
The licensee shall operate the facility in accordance with the Technical Specifications.
3.
Paragraph 2.H is added to the license to read as follows:
2.H In all places of this license, the reference to the Indiana and Michigan Power Company is deleted and all references to "the licensees" is amended to read "the licensee".
The intent is to recognize the Indiana and Michigan Electric Company as the sole licensee of the Donald C.
Cook Nuclear Pl ant.
4.
This license amendment is effective as of the date of 'the merger of the Indiana and Michigan Power Company and the Indiana and Michigan Electric Company.
FOR THE NUCLEAR REGULATORY COMMISSION
Attachment:
Changes to the Technical Specifications
/
~ /jg~..crE"c A. Schwencer, Chief Operating Reactors Branch Pl Division of Operating Reactors Date of Issuance:
November 9, 1979
ATTACHMENT TO LICENSE AMENDMENT, NO. 14 FACILITY OPERATING LICENSE NO.
DPR-74 DOCKET NO.
50-316 Replace the following pages of the Appendix "A" Technical Specifications with the enclosed pages.
The revised pages are identified by Amendment number of contain vertical lines indicating the area of change.
The correspondino overleaf pages are also provided to maintain document completeness.
~Pe es 6-2 6-9 6-11 6-12 D.
C.
COOK - UNIT 2
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- 6. 0 ADMI N I STRATIVE CONTROLS 6.1 RESPONSIBILITY 6.1.1 The Plant Manager shall be responsible for overall facility opera-tion 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 in 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 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.
e.
All CORE ALTERATIONS 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.
f.
A site Fire Brigade of at least 5 members shall be maintained onsite, at all times.
The Fire Brigade shall not include 3
members of the minimum shift crew necessary for safe shutdown of the unit or any personnel required for other essential functions during a fire emergency.
D.
C.
COOK - UNIT 2 6-1
PRESIDENT AEP, AEPSC, I &
M'ND OTHER AEP SUBSIDIARIES LEGEND:
ADMINISTRATIVE TECHNICAL SUPERVISION
& FUNCTIONAL DIRECTION TECHNICAL LIASON EXECUTIVE VICE PRESIDENT INDIANA& MICHIGAN ELECTRIC COMPANY SENIOR EXECUTIVE VICE PRESIDENT ENGINEERING &
CONSTRUCTION AEPSC VICE PRESIDENT'NDIANA& MICHIGAN ELECTRIC COMPANY E XECUTIVE VICE PRESIDENT ENGINEERING &
CONSTRUCTION AEPSC
~ 'e ASSISTANT TO EXEC. V. P.
VICE PRESIDENT NUCLEAR ENGINEERING i AEPSC OTHER ENGINEERING D IVISIONS AEPSC QUALITY ASSURANCE MANAGER AEPSC AEPSC NSDRC PLANT MANAGER DONALD C. COOK NUCLEAR PLANT PLANT QUALITYASSURANCE SUPERVISOR INDIANAAND MICHIGAN ELECTRIC COMPANY Responsible for Fire Protection Program FIGURE 6.2.1 Offsite Organization for Facility Management and Technical Support D.,C.
COOK - UNIT 2 6-2 Amendment No.
14
ADMINISTRATIVECONTROLS COMPOSITION 6.5.2.2 The NSDRC shall be composed of the:
Chairman:
Member:
Member:
Member:
Member:
Member:
Member:
Member:
Member:
Member:
Member:
Member:
Alternate:
Alternate:
Alternate:
Alternate:
Vice President Nuclear Engineering Senior Executive Vice President, Engineering 5 Construction Executive Vice Pr esident, I8M Electric Company Executive Vice President, Engineering 8 Construction Assistant Vice President, Mechanical Engineering Vice President, Electrical Engineering Assistant Vice Pr esident, Production Chief Design Engineer Assistant Vice President-Civil Engineering Plant Manager, D.C.
Cook P1ant
- Head, Environmental Engineering Division Head, Nuclear Safety 8 Licensing Section Assistant Chief Me'chanical Engineer Assistant Plant Manager, D.C.
Cook Plant Executive Assistant to the Executive Vice President, I8M Assistant Division Head, Nuclear Engineering Division ALTERNATES 6.5.2.3 All alternate members shall be appointed in writing by the NSDRC Chairman to serve on a temporary basis;
- however, no more than two'lternates shall participate as voting members in NSDRC activities at any one time.
CONSULTANTS 6.5.2.4 Consultants shall be utilized as determined by the NSDRC Chairman to provide expert advice to the NSDRC.
MEETING FRE UENCY 6.5.2.5 The NSDRC shall meet at least once per calendar quarter during the initial year of facility operation following fuel loading and at least once per six months thereafter.
D.
C.
COOK - UNIT 2 6-9 Amendment No.
14
ADMINISTRATIVE CONTROLS gUORUM 6.5.2.6 A quorum of NSDRC shall consist of the Chairman or his designated alternate and at least 6
NSDRC members including alternates.
No more than a minority of the quorum shall have line responsibility for operation of the facility.
REVIEW 6.5.2.7 The NSDRC 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 actions did not constitute an unreviewed safety question.
b.
Proposed changes to procedures, equipment or systems which involve an unreviewed safety question as defined in Section 50.59, 10 CFR.
Proposed tests or experiments which involve an unreviewed safety question as defined ln Section 50.59, 10 CFR.
d.
Proposed changes to Technical Specifications or this Operating License.
e.
Violations of codes, regulations,
- orders, Technical Specifications, license requirements, or of internal procedures or instructions having nuclear safety significance.
Significant operating abnormalities or deviations from normal and expected performance of plant equipment that affect nuclear sa fety.
g.
h.
Events 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 Commission.
All recognized indications of an unanticipated deficiency in some aspect. of design or operation of safety related structures,
- systems, or components.
Reports and meetings minutes of the PNSRC.
D.
C.
COOI'. - UNIT 2 6-10
ADMINISTRATIVE'ONTROLS AUDITS 6.5.2.8 Audits of facility activities shall be performed under the coqnizance of the NSDRC.
These audits shall encompass:
a.
The conformance of facility operation to provisions contained within the Technical Specifications and applicable license conditions at least once per 12 months.
b.
C.
d.
The performance, training and qualifications of the entire facility staff at least once per 12 months.
The results of actions taken to correct deficiencies occurring in facility equipment, structures, systems or method of operation that affect nuclear safety at least once per 6 months.
The performance of activities required by the Operational Ouality Assurance Program to meet the criteria of Appendix "B", 10 CFR 50, at least once per 24 months.
e.
The Facility Emergency Plan and implementina procedures-at least once per 24 months.
The Facility Security Plan and implementing procedures at least once 'per 24 months.
Any other area of facility operation considered appropriate by the NSDRC.
h.
The Facility Fire Protection Program and implementing procedures at least once per 24 months.
An independent fire protection and loss prevention inspection and audit shall be performed at least once per 12 months utilizing either qualified offsite licensee personnel or an outside fire protection firm.
An inspection and audit of the fire protection and loss pre-vention program shall be performed by an outside qualified fire consultant at least once per 36 months.
AUTHORITY 6.5.2.9 The NSDRC shall report to and advise the vice Chairman, Engi-neering and Construction,
- AEPSC, on those areas of responsibility specified in Sections 6.5.2.7 and 6.5.2.8.
D.
C.
COOK - UNIT 2 6-11 Amendment No. 14
ADMINISTRATIVE CONTROLS RECORDS 6.5.2.10 Records of NSDRC activities shall be prepared, approved and distributed as indicated below:
a.'inutes of each NSDRC meeting shall be prepared, approved and forwarded to the Vice Chairman, Engineerinq and Construction, AEPSC, within 14 days following each meeting.
b.
C.
Reports of reviews encompassed by Section 6.5.2.7 above, shall be
- prepared, approved and forwarded to the Vice Chairman, Enqi-neering and Construction, AEPSC, within 14 days following completion of the review.
Audit reports encompassed by Section 6.5.2.8
- above, shall be forwarded to the Vice Chairman, Engineering and Construction,
- AEPSC, and to the management positions responsible for the areas audited within 30 days after completion of the audit.
6.6 REPORTABLE OCCURRENCE ACTION 6.6.1 The following actions shall be taken for REPORTABLE OCCURRENCES:
a ~
b.
The Commission shall be notified and/or a report submitted pursuant to the requirements of Specification 6.9.
Each REPORTABLE OCCURRENCE requirinq
'24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> notification to the Commission shall be reviewed by the PNSRC and submitted to the NSDRC and the Chief, Nuclear Engineer.
D.
C.
COOK - UNIT 2 6-12 Amendment No. 14'
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO.
33TO FACILITY OPERATING LICENSE NO.
DPR-58 AND AMENDMENT NO.
14 TO FACILITY OPERATING LICENSE NO.
DPR-74 INDIANA AND MICHIGAN ELECTRIC COMPANY INDIANA AND MICHIGAN POWER COMPANY DONALD C.
COOK NUCLEAR PLANT UNIT NOS.
1 AND 2 DOCKET NOS. 50-315 AND 50-316 Introduction On August 24, 1979, the Indiana and Michigan Electric Corn@any and the Indiana and Michigan Power Company (the licensees) submitted an application for amendment to the Facility Operating Licenses for the Donald C.
Cook Nuclear Plant.
The amendment would recognize the merger of the two companies with the surviving corporation being the Indiana and Michigan Electric Company.
On December 22, 1978 and February 13, 1979, the licensee submitted applications for Unit'os.
1 and 2, respectively, which in part corrected the titles of members of the licensees'rganizations.
Evaluation The staff has reviewed the proposed merger of the licensees as it would effect financial qualifications, technical qualification, and safety of operation of Unit Nos.
1 and 2 of the.D.
C.
Cook Nuclear Plant.
From a financial standpoint, the financial qualifications of the merger companies will be the same as collectively existed prior to the nerger.
From a
technical qualifications standpoint, there are no changes in personnel, operating procedures or practices other than that employees of Indiana and Michigan Power Company will become employees of Indi ana and Michigan Electric Company.
There are no safety considerations involved in the merger, therefore, we find the proposed merger acceptable.
In addition to the merger, the licensees.
brought to our attention certain title changes within their organizations.
We have taken this opportunity to correct the Administrative Controls area of the Technical Specifications.
These changes in titles will have no effect on the con.inued safe operation of the D. C.
Cook Nuclear Plant.
Vell260
E nvi ronmenta1 Cons i de rat i on We have determined that the amendments do not authorize a change in effluent types or total amounts nor an increase in power level and will not result in any significant environmental impact.
Having made this determination, we have further concluded that the amendments involve an action which is insignificant from the standpoint of environmental impact and, pursuant to 10 CFR
$51.5(d)(4), that an environmental impact statement or negative declaration and environ-mental impact appraisal need not be prepared in connection with the issuance of these amendments.
Conclusion Me have concluded, based on the considerations discussed above, that:
(1) because the amendments do not involve a significant increase in the probability or consequences of accidents previously considered and ao -not involve a significant decrease in a safety margin, the amendments do not involve a significant hazards consideration, (2) there is reasonable assurance that the, health and safety of the public will not be endangered by operation in the proposed
- manner, and (3) such activities will be conducted in compliance with the Commission's regulations and the issuance of these amendments will not be inimical to the common defense and security or to the health and safety of the public.
Date:
November,9, 1979
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