ML17332A630
| ML17332A630 | |
| Person / Time | |
|---|---|
| Site: | Cook  |
| Issue date: | 03/06/1995 |
| From: | Hannon J NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML17332A631 | List: |
| References | |
| NUDOCS 9503150314 | |
| Download: ML17332A630 (35) | |
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UNITED STATES NUCLEAR REGULATORY COMMISSlON WASHINGTON) D C 2055&4001 INDIANA MICHIGAN POWER COMPANY DOCKET NO. 50-315 DONALD C.
COOK NUCLEAR PLANT UNIT NO.
1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 192 License No.
DPR-58 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Indiana Michigan Power Company (the licensee) dated October 7,
- 1994, 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 7 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 requirements have been satisfied.
9503i503i4 95030b PDR ADOCK 050003i5 P
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-58 is hereby amended to read as follows:
Technical S ecifications The Technical Specifications contained in Appendices A and 8, as revised through Amendment No. 192
, are hereby incorporated in the license.
The licensee shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment is effective as of the date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION P~~ a~
John N. Hannon, Director Project Directorate III-I Division of Reactor Projects - III/IV Office of Nuclear Reactor Re'gulation
Attachment:
Changes to the Technical Specifications Date of Issuance:
March 6, 1995
ATTACHMENT TO LICENSE AMENDMENT NO. 192 TO FACILITY OPERATING LICENSE NO.
DPR-58 DOCKET NO. 50-315 Revise Appendix A Technical Specifications by removing the pages identified below and inserting the attached pages.
The revised pages are identified by amendment number and contain vertical lines indicating the area of change.
REMOVE 6-4 6-6 6-7 6-9 6-11 6-12 6-13 INSERT 6-4 6-6 6-7 6-9 6-11 6-12 6-13
ADMINISTRATIVECONTROLS 6
3 FACILITY STAFF UALIFICATIONS 6.3.1 Each member of the facility staff shall meet or exceed the minimum qualifications of ANSI N18.1-1971 for comparable positions, except for (1) the Plant Radiation Protection Manager, who shall meet or exceed qualifications of Regulatory Guide 1.8, September 1975, (2) the Shift Technical Advisor, who shall have a bachelor's degree or equivalent in a scientific or engineering discipline with specific training in plant design, and response and analysis of the plant for transients and accidents
- and, (3) the Operations Superintendent who must hold or have held a Senior Operator License as specified in Section 6.2.2.h.
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 Manager and shall meet or exceed the requirements and recommendations of Section 5 '
of ANSI N18.1-1971 and 10 CFR Part 55.
6.5 REVIEW AND AUDIT 6
5 1
PLANT NUCLEAR SAFETY REVIEW COMMITTEE PNSRC FUNCTION 6.5.1.1 The PNSRC shall function to advise the Site Vice President/Plant:
- Manager, or designee,
'on all matters related to nuclear safety.
COMPOSITION I
6.5.1.2
,The PNSRC shall be-composed of,Assistant Plant Managers, Department Superintendents, or supervisory personnel reportihg directly to the Site Vice President/Plant'Manager, Assistant Plant Managers or Department Superintendents.
The membership shall represent the functional areas of the plant, including, but not limited to Operations, Technical
- Support, Licensing, Maintenance and Radiation Protection.
The PNSRC membership shall consist of at least one individual from each of the areas designated.
All members, including the Chairman and his alternates, the members and their alternates, shall
.be designated by the Site Vice President/Plant Manager.
PNSRC members and alternates shall meet or exceed the minimum qualifications of ANSI N18.1-1971 Section 4.4 for comparable positions.
The nuclear power plant operations individual shall meet the qualifications of Section 4.2.2 of ANSI N18.1-1971 except for the requirement to hold a current-Senior Operator License.
The operations individual must 'hold or have held a Senior Operator License at Cook Nuclear Plant or a similar reactor.
The maintenance individual shall meet the qualifications of Section 4.2.3 of ANSI N18.1-1971.
COOK NUCLEAR PLANT - UNIT 1 6-4 AMENDMENT NO. 49/63 43Rf M4F 192
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DMINISTRATIVE CONTROLS h.
Performance of special reviews, investigaCions of analyses and reports thereon as requested by the Chairman of the NSDRC.
Deleted.
Deleted.
k.
Review of any accidental, unplanned, or uncontrolled radioactive release including the preparation of reports covering evaluations, recommendations, and disposition of the corrective action to prevent recurrence and the forwarding of these reports to the Senior Vice President
- Nuclear Generation and to the NSDRC.
Review of changes to the PROCESS CONTROL PROGRAM, OFFSITE DOSE CALCULATION MANUAL, and radwaste treatment system.
AUTHORITY 6.5.1.7 The PNSRC shall:
a.
Recommend to the Site Vice President/Plant Manager, or designee, writCen approval or disapproval of items considered under 6.5.1.6 (a) through (d) above.
b; e/'
(".
Render determinations in writing with regard to whether or not each item considered under 6.5.1.6 (a) through (c),and (e) above constiCutes an unreviewed safety question.
/'
--,', Provide, written notification within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />'-to the.Senior Vice President
- Nuclear Generation ance the.
NSDRC of disagreement between the PNSRC and the Site Vice President/PlanC Manager;
- however, the Site Vice President/PlanC Manager shall have responsibility for resoluCion of such disagreements pursuant to 6.1.1 above.
I/e
/"
j
/
/ J ECORDS 6.5.1.8 The PNSRC shall maintain written minutes of each meeting and copies shall be provided to the Chairman of Che NSDRC.
6 5 2 NUCLEAR SAFETY AND DESIGN REVIEW COMMITTEE NSDRC
~PONOT ON C
~
6.5.2.1 The NSDRC shall function to provide independent review and audit of designated activities in the areas of:
a, nuclear power plant operations b.
I/
nuclear engineering COOK NUCLEAR PLANT - UNIT 1 6-6 AMENDMENT NO.
192
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ADMINISTRATIVECONTROLS C.
chemistry and radiochemistry d.
e.
h.
metallurgy instrumentation and conCrol radiological safety mechanical and'lectrical engineering quality assurance practices COMPOSITION 6.5.2.2 The NSDRC shall be composed of the following regular members:
1.
2.
3.
4.
5.
6.
7.
8.
9.
10.
11.
-.;12.
13.
Additional President, Senior Vice President
- Nuclear Generation (NSDRC Chairman)
Manager
- Nuclear
- SafeCy, Licensing,
& Fuel Division (NSDRC Secretary)
Site Vice President/Plant Manager - Donald C. Cook Nuclear Plant Vice President
- Indiana Michigan Power Company Executive Vice President
- Engineering
& Construction Vice President
- Transmission and Distribution Services Senior Vice President
- Fossil and Hydro Generation Manager
- Nuclear Engineering Department Vice President
- Civil Engineering Manager
- Nuclear Plant Engineering Support Division Manager
- Nuclear. SupporC Services Department Manager- - Quality 'Assurance Department Mana'ger - Pioduction Support and Administrativq Services Sec'tion members and Vice Chairman may be appointed by the and Chief Operating Officer.
LTERNATES 6.5.2.3 Designated alternate members shall be appointed by the President, and Chief Operating Officer or. such other person as he shall designate.
In addition, temporary alternate members may be appointed by the NSDRC Chairman to serve on an interim basis, as required.
Temporary alternate members are empowered to act on the behalf of the regular or designated alternate members for whom they substitute.
COOK NUCLEAR PLANT - UNIT 1 6-7 AMENDMENT NO.
192
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/
DMINISTRATIVE CONTROLS f.
Significant operating abnormalities or deviations from normal and expected performance of plant equipment that affeet nuclear safety.
g.
All REPORTABLE EVENTS.
h.
Allrecognized indications of an unanticipated deficiency in some aspect of design or operation of safety-related structures,
- systems, or components.
Reports and meeting minutes of the PNSRC.
UDITS 6.5.2.8 Audits of facility activities shall be performed under the cognizance of the NSDRC.
These audits shall encompass:
a.
I
-The conformance of facility operation to provisions contained within the Technical Specifications and applicable license conditions at least once per 12 months.
b.
The performance,
- training, and qualifications of the entire facility staff at least once per 12 months.
C.
The results of actions taken to correct deficiencies occurring in facilityequipment, structures, systems or, method of operation that affect. nuclear safety at least once per 6 months.
d.
The performance of activities required by the Quality Assu'rance Program to meet the criteria of Appendix "B"; 10"CFR 50, at least once per 24 months.
e.
Deleted.
Deleted.
The fire protection programmatic controls including the implementing procedures at least once per 24 months by qualified licensee QA personnel.
h.
The fire protection equipment and program implementation at least once per 12 months using either a qualified offsite licensee fire protection engineer or an outside independent fire protection consultant.
An outside independent fire protection consultant shall be used at least every third year.
The Radiological Environmental Monitoring Program and the results thereof at least once per 12 months.
COOK NUCLEAR PLANT - UNIT 1 6-9 AMENDMENT NO.
192
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ADMINISTRATIVECONTROLS b.
shall be approved by the appropriate department head as previously designated in wriCing by the Site Vice President/Plant
- Manager, or designee.
The Site Vice President/Plant Manager, or
- designee, shall approve Plant Manager Procedures.
Temporary changes t:o procedures which do not change the intent of the approved procedures shall be approved for implementation by two members of t:he plant staff, at least one of whom holds a Senior Operator license, and documented.
Th'e temporary changes shall be approved by Che original approval authority within 14 days of implementation.
For changes to procedures which may involve a change in intent of the approved procedures, the person authorized above to approve the procedure shall approve the change prior to implementation.
r Proposed changes or modifications to plant nuclear safety-related structures, systems and components shall be reviewed as designated by the Site Vice President/Plant Manager, or designee.
Each such modification shall be reviewed (reference T/S 6.5.3.1.e) by a
qualified (reference T/S 6.5.3.1.d) individual/group other than the individual/group which designed the modification, but who may be from the same organization as the individual/group which designed ghe modifications.
Proposed modifications to plant nuclear safety-related sCructures, systems and components shall be approved prior to implementation by the Site Vice President/Plant
- Manager, or designee.
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d.
e.
Individuals who conducted the reviews performed in the accordance with Specification 6.5,3.1a, 6.5.3.1b, and 6.5.3.1c, shall be members of the plant management staff previously designated by the Site Vice President/PlanC Manager and shall meet or exceed the minimum qualifications of ANSI N18.1-1971 Section 4.4 for comparable positions.
Each such review shall include a
determinaCion of whet:her or not additional, cross-disciplinary review is necessary.
If deemed necessary, such review shall be performed by qualified personnel of the appropriate discipline.
<'i
.Each review shall include a determination of whether or not an unreviewed safety question is involved.
Pursuant to 10 CFR 50.59, NRC approval of items involving unreviewed safety questions shall be obtained prior to the approval of the Site Vice President/PlanC
- Manager, or designee, for implementation.
Proposed tests and experiments which affect planC nuclear safety and are not addressed in the Final Safety Analysis Report or Technical Specifications shall be
- prepared, reviewed, and approved.
Each such test or experiment shall be, reviewed bv
~W)>~
qualified'~individuals/groups other " than'he individual/group--'-'
i' which prepared the proposed. test or experiment,to; ass@re cross-J disciplinary'eview as appropriate for the proposed test or I
experiment.
Proposed tests and experiments shall be approved before implemenCation by the Site Vice President/Plant
- Manager, or designee.
)'I "4l DeleCed.
COOK NUCLEAR PLANT - UNIT 1 6-11 AMENDMENT NO. 69, 192
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(continued) g.
'Deleted.
I 6.5.3.2 Records of the above activities shall be provided to the Site Vice President/Plant
- Manager, or designee, PNSRC and/or the NSDRC as necessary for required reviews' I
6 6 REPORTABLE EVENT ACTION 6.6.1 The following actions shall be taken for REPORTABLE EVENTS:
a.
The Commission shall be notified and a report submitted pursuant to the requirements of 10 CFR 50.73, and ge ~ci b.
Each REPORTABLE EVENT shall be reviewed by the
- PNSRC, and the results of this. review shall be submitted to the NSDRC and the Senior Vice President
- Nuclear Generation.
SAFETY LIMITVIOLATION 6.7.1 The following actions shall be taken in the event-a safety limit is violated:
a.
The NRC Operations Center shall be notified by telephone as soon as possible and in all cases within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.
The Chairman of the NSDRC shall be notified within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
b.
c ~
A Safety Limit Violation Report shall be prepared.
The report shall be reviewed by the PNSRC.
This report shall describe (1) applicable circumstances preceding the violation; (2) effects of
. the vioiation upon facility components,,
systems
'pr structures; and'3) corrective actio'n taken to pr.event, recurrence.
The Safety Limit Violation Report'hall be submitted to the Commission, the Chairman of the NSDRC and s the Senior Vice President
- Nuclear Generation within 14 days of the violation.
Operation of the unit shall not be resumed until authorized by
'he Commission.
COOK, NUCLEAR PIANT - UNIT 1 6-12 AMENDMENT NO. M, 454, ~
192
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8 OCD 6.8.1 Written procedures shall be established, implemented and maintained covering the activities referenced below:
a.
The applicable procedures recommended in Appendix "A" of Regulatory Guide 1.33, Rev. 2, February 1978.
b.
Deleted.
c.
Deleted.
d.
PROCESS CONTROL PROGRAM implementation.
e.
OFFSITE DOSE CALClHATION MANUAL implementation.
Quality Assurance Program for effluent and environmental monitoring using the guidance in Regulatory Guide 1.21, Rev. 1, June
- 1974, and Regulatory Guide 4.1, Rev. 1, April 1975.
6.8.2 Each procedure and administrative policy of Specification 6.8.1
- above, and changes
- thereto, including temporary changes, shall be reviewed prior to implementation as set forth in Specification 6.5 above.
6.8.3 A plant program for post-accident:
sampling shall be established, implemented, and maintained which will ensure the capability to obtain and analyze reactor coolant samples, containment atmosphere noble gas samples, and unit vent gaseous effluent samples for iodines and particulates under accident conditions.
The program will include the following:
a.
Training of personnel, b.
Procedures for sampling and analysis, c.
Provisions for maintenance of sampling and analysis equipment.
COOK NUCLEAR HANT - UNIT 1 6-13 AMENDMENT NO. M, 444
+99-, 192
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go" UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTONe D.C. 2055&0001 INDIANA MICHIGAN POWER COMPANY DOCKET NO. 50-316 DONALD C.
COOK NUCLEAR PLANT UNIT NO.
2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.
178 License No.
DPR-74 1.
The Nuclear Regulatory Commission (the Commission) has found that:
The application for amendment by Indiana Michigan Power Company (the licensee) dated October 7,
- 1994, 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;
The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; tC.
D.
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; 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 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:
Technical S ecifications The Technical Specifications contained in Appendices A and B,
as revised through Amendment No. I78
, are hereby incorporated in the license.
The licensee shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment is effective as of the date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION C mac Joh N. Hannon, Di ector Project Directorate III-I Division of Reactor Projects III/IV Office of Nuclear Reactor Regulation
Attachment:
Changes to i,he Technical Specifications Date of Issuance:
Harch 6, 1995
ATTACHMENT TO LICENSE AMENDMENT NO. 178 FACILITY OPERATING LICENSE NO.
DPR-74 DOCKET NO. 50-316 Revise Appendix A Technical Specifications by removing the pages identified below and inserting the attached pages.
The revised pages are identified by amendment number and contain vertical lines indicating the area of change.
REMOVE 6-4 6-6 6-7 6-9 6-11 6-12 6-13 INSERT 6-4 6-6 6-7 6-9 6-11 6-12 6-13
ATTACHMENT 3 TO AEP:NRC'0659X DMINISTRATIVE CONTROLS 6
3 FACILITY STAFF UALIFICATIONS 6.3.1 Each member of the facility staff shall meet or exceed the minimum qualifications of ANSI N18.1-1971 for comparable positions, except for (1) the Plant Radiation Protection Manager, who shall meet or exceed qualifications of Regulatory Guide 1.8, September 1975, (2) the Shift Technical Advisor, who shall have a bachelor's degree or equivalent in a scientific or engineering discipline with specific training in plant design, and response and analysis of the plant for transients and accidents
- and, (3) the Operations Superintendent, who must hold or have held a Senior Operator License as specified in Section 6.2.2.h.
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 Manager and shall meet or exceed the requirements and recommendations of Section 5.5 of ANSI N18.1-1971 and'0 CFR Part 55.
6 5
REVIEW AND AUDIT 6
5 1 PLANT NUCLEAR SAFETY REVIEW COMMITTEE PNSRC FUNCTION
/
6.5.1.1 The PNSRC shall function to advise the Site Vice President/Plant Manager, or designee,,-on all matters related to'uclear, safety.
-I I
COMPOSITION t~
C.-
~--
r 6.5.1.2 The PNSRC shall be composed of Assistant Plant Managers, Department Superintendents, or supervisory personnel reporting directly to the Site Vic'e President:/Plant Manager, Assistant Plant Managers or Department Superintendents.
The membership shall represent the functional areas of the plant, including, but not limited to Operations, Technical
- Support, Licensing, Maintenance and Radiation Protection.
The PNSRC membership shall consist of at least one individual from each of the areas designated.
All members, including the Chairman and his alternates, the members and their alternates, shall'e designated by the Site Vice" President/Plant Manager.
PNSRC members and alternates shall meet or exceed the minimum qualifications of ANSI N18.1-1971 Section 4.4 for comparable positions.,
The nuclear power plant operations individual shall meet the qualifications of Section 4.2.2 of ANSI N18.1-1971 except for the requirement to hold a current Senior Operator License.
The operations individual must hold or have held a Senior Operator License at Cook Nuclear Plant or a similar reactor.
The maintenance individual shall meet the qualifications of Section 4.2.3 of ANSI N18.1-1971.
COOK NUCLEAR PLANT - UNIT 2 6-4 AMENDMENT NO. Q4, ~i~ ~f 178
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ADMINISTRATIVECONTROLS
,h;
'Performance of special
- reviews, investigations of analyses and reports thereon as requested by the Chairman of the NSDRC.
i.
Deleted.
j.
Deleted.
k.
Review of any accidental, unplanned, or uncontrolled radioactive release including the preparation of reports covering evaluations, recommendations, and disposition of the corrective action to prevent recurrence and. the forwarding of these reports to the Senior Vice President
- Nuclear Generation and to the NSDRC.
Review of changes to the PROCESS CONTROL
- PROGRAM, OFFSITE DOSE CALCULATION MANUAL, and radwaste treatment system.
~UTHORITY 6.5.1.7 The PNSRC shall:
a.
Recommend to the Site Vice President/Plant
- Manager, or desginee, written approval or disapproval of items considered under 6.5.1.6 (a) through (d) above.
b.
Render determinations in writing with regard to whether or not each item considered under 6.5.1.6 (a) through (c) and (e) above constitutes an unreviewed safety question.
le'. Provide written notification>withins 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> to the Senior Vice r>J.
~ g presfdent
-Nuclear Generatfon and-.the.
NSDRC of disagreement'etween q
I,"the PNSRC and the Site Vice~fPresideiit/Plant'Mamnager; however.;, the>'y~
Site Vice President'/Plant Manager,j'i or designee,"
shall "have responsibility for resolution of such disagreements pursuant to 6.1.1 Q above.
s PP l
RECORDS 6.5.1.8 The PNSRC shall maintain.written minutes of each meeting and copies shall be provided to the Chairman of the 'NSDRC.
6 '5 2
NUCLEAR SAF ND DES GN EVIEW COMMITTEE NSDRC FUNCTION 6.5.2.1 The NSDRC shall function to provide independent review and audit of designated activities in the areas of:
a.
nuclear power plant operations b.
nuclear engineering COOK NUCLEAR PLANT - UNIT 2 6-6 AMENDMENT NO. M, ASS 178
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DMINISTRATIVE CONTROLS
,c.
chemistry and radiochemistry d.
metallurgy e.
instrumentaCion and control f.
radiological safety g.
mechanical and electrical engineering h.
quality assurance practices COMPOSITION 6.5.2.2 The NSDRC shall be composed of the following regular members:
1.
2.
3.
4, 5.
6.
7.
8.
9.
10.
11.
12,
. '3
'dditional President" Senior Vice President
- Nuclear Generation (NSDRC Chairman)
Manager
- Nuclear SafeCy, Licensing,
& Fuel Division -
(NSDRC Secretary)
Site Vice President/Plant Manager - Donald C. Cook Nuclear Plant Vice President
- Indiana Michigan Power Company Executive Vice President
- Engineering
& Construction Vice President
- Transmission and Distribution Services Senior Vice President
- Fossil and Hydro Generation Manager
- Nuclear Engineering Department Vice President
- Civil Engineering Manager
- Nuclear Plant Engineering Support Division Manager
- Nuclear Support Services Department Manager
- Quality Assurance Department Manager - Production Support and Administrative Services Section members and Vice Chairman may be -'hppointed by the and Chief Operating Officer.
LTERNATE MEMBERS 6.5.2.3 Designated alternate members shall be appointed by the President.
and Chief Operating Officer or such other person as he shall designate.
In addition, temporary alternaCe members may be appointed by the NSDRC Chairman to serve on an interim basis, as requir'ed.
Temporary alternate members are empowered Co act on t'e behalf of the regular or designated alternate members for whom they substitute.
COOK NUCLEAR PLANT - UNIT 2 6-7 AMENDMENT NO.
178
g DMINISTRAT VE CONTRO S
f.
Significant operating abnormalities or deviations from normal and expected performance of plant equipment that affect nuclear safety.
g.
All REPORTABLE EVENTS.
h.
All recognized indications of an unanticipated deficiency in some aspect of design or operation of safety-related structures,
- systems, or components.
C-'.
Reports and meeting minutes of the PNSRC.
UDITS 6.5.2.8 Audits of facility activities shall be performed under the cognizance 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.
The performance,
- training, and qualifications of the entire facility staff at least once per 12 m'onths.
c.
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.
J d.
The performance of activities required by the Quality Assurance Program to meet the criteria of Appendix "B", 10 CFR 50, at least once per 24 months. c, i
f>>
r- ~
XV f.
, Deleted.
go h.
The fire protection programmatic controls including the implementing procedures at least once per 24 months by qualified licensee QA personnel.
/~
The fire protection equipment~and program"implementation at least once per 12 months using either a qualified offsite licensee fire protection engineer or an outside independent fire protection consultant.
An outside independent fire protection consultant shall be used at least every third year.
i.
The Radiological Environmental Monitoring Program and the results thereof at least once per 12 months.
COOK NUCLEAR PLANT - UNIT 2 6-9 AMENDMENT NO. M, 488-178
f 1
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ADMINISTRATIVECONTROLS shall be approved by the appropriate department head as previously designated in writing by the Site Vice PresidenC/Plant
- Manager, or designee.
The Site Vice President/Plant Manager, or designee, shall approve Plant Manager Procedures.
Temporary changes to procedures which do noC change the intenC of the approved procedures shall be approved for implementation by two members of the plant staff, at least one of whom holds a Senior Operator license, and documented.
The temporary changes shall be approved by Che original approval authority within 14 days of implementation.
For changes to procedures which may involve a
change in intent of Che approved procedures, the person authorized above to approve the procedure shall approve the change prior to implementation.
b.
Proposed changes or modifications to plant nuclear safety-related structures, systems and components shall be reviewed as designated by the Site Vice President/Plant
- Manager, or designee.
Each such modification shall be reviewed (reference T/S 6 '.3.1.e) by a
qualified (reference T/S 6.5.3.1.d) individual/group other than the individual/group which designed the modification, but who may be from the same organization as the individual/group which designed the modifications.
Proposed modifications to plant nuclear safeCy-related structures, systems and components shall be approved prior to implemenCation by the Site Vice President/Plant Manager, or designee.
C.
d.
e.
Proposed tests and experiments which affect plant nuclear safety and are not addressed in the Final Safety Analysis Report or Technical Specifications shall be prepared,
- reviewed, and approved.
Each such test or experiment shall be reviewed by qualified individuals/groups other than the individual/group which prepared the proposed test or experiment to assure cross-disciplinary review as appropriate for the proposed test or experiment..-
Proposed tests and experiments shall be
~approved before implementation by the, Site Vice President/Plant
- Manager, or designee.
/X Individuals who conducted
'the reviews performed in accordance wiCh Specification 6.5.3.1a, 6.5.3.1b, and 6.5.3.1c, shall be members of the plant management staff previously designated by the Site Vice President/Plant Manager and shall meet or exceed the minimum qualifications of ANSI N18.1'-1971 Section 4.4 for comparable positions.
Each such review shall include a determination of whether or not addiCional, cross-disciplinary review is necessary.
If deemed necessary, such review shall be performed by qualified personnel of the appropriat'e discipline.
3
, E.
Each review shall include a determination of whether or not an unreviewed safety quesCion is involved.
Pursuant to 10 CFR 50.59, NRC approval of items involving unreviewed safety questions shall be obtained prior to the approval of the Site Vice President/Plant
- Manager, or designee, for implementation.
Deleted.
COOK NUCLEAR PLANT - UNIT 2 6-11 AMENDMENT NO. 44, RSS.
178
NS VECO (continued) g.
Deleted.
6.5.3.2 Records of the above activities shall be provided to the Site Vice Preident/Plant
- Manager, or designee, PNSRC and/or the NSDRC as necessary for required reviews.
6 6
REPORTABLE EVENT ACTION 6.6.1 The following actions shall be taken for REPORTABLE EVENTS:
a.
The Commission shall be notified and a report submitted pursuant to the requirements of 10 CFR 50.73, and b.
Each REPORTABLE EVENT shall be reviewed by the PNSRC, and the results of this review shall be submitted to the NSDRC and the Senior Vice President
- Nuclear Generation.
6 SAFETY LIMIT VIOLATION 6.7.1 The following actions shall be taken in the event a safety limit is violated:
a.
The NRC Operations Center shall be notified by telephone as soon as possible and in all cases within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.
The Chairman of the NSDRC shall be notified within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
b.
C.
d.
A Safety Limit Violation Report shall be prepared.
The report shall be reviewed by the PNSRC.
This report shall desciibe (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.
~
'he Safety Limit Violation Report shall be submitted to the Commission, the Chairman of the NSDRC and the Senior Vice President-Nuclear Generation within 14 days of the violation.
Operation of the unit shall not be resumed until authorized by the Commission.
COOK NUCLEAR PLANT - UNIT 2 6-12 AMENDMENT NO. W, 434
+75; 178
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6 8
OCEDURES OG S
6.8.1 Written procedures shall be established, implemented and maintained covering the activities referenced below:
a.
The applicable procedures recommended in Appendix "A" of Regulatory Guide 1.33, Rev. 2, February 1978.
b.
Deleted.
c.
Deleted.
d.
PROCESS CONTROL PROGRAM implementation.
e.
OFFSITE DOSE CALCULATION MANUAL implementation.
f.
Quality Assurance Program for effluent and environmental monitoring using the guidance in Regulatory Guide 1.21, Rev. 1, June
- 1974, and Regulatory Guide 4,1, Rev.
1, April 1975.
6.8.2 Each procedure and administrative policy of Specification 6.8.1
- above, and changes
- thereto, including temporary changes, shall be reviewed prior to implementation as set forth in Specification 6.5 above.
6.8.3 A plant program for post-accident sampling shall be established, implemented, and maintained which will ensure the capability to obtain and analyze reactor coolant samples, containment atmosphere noble gas
- samples, and unit vent gaseous effluent samples for iodines and particulates under accident conditions.
The program will include the following:
a.
Training of personnel, b.
Procedures for sampling and analysis, c.
Provisions for maintenance of sampling and analysis equipment.
COOK NUCLEAR PIANT - UNIT 2 6-13 AMENDMENT NO. 44, 438 178
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