ML17319B258

Tech Specs Table 3.3-1 Re Condition Setpoint & Tech Specs Table 6.3-6.8.2,facility Staff Qualifications,Administrative Controls & Safety Limit Violations

ML17319B258
Person / Time
Site:	Cook
Issue date:	03/29/1982
From:	INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG
To:
Shared Package
ML17319B257	List: ML17319B256 ML17319B258
References
NUDOCS 8204060058
Download: ML17319B258 (15)

Text

TABLE 3.3-1 Continued DESIGNATION CONDITION AND SETPOINT FUNCTION P-7 P-8

, P-10 Mith 2 of 4 Power Range Neutron Flux Channels

> 11>> of RATED THERMAL POMER or 1 of 2 Turbine Fi.rst Stage Pressure channels

>37 psigo

~

Mith 2 of 4 Power Range Neutron Flux channe1s 51Ã of'ATED THERMAL POMER.

-Mith 3 of 4 Power range neutron flux channels

< 9X of RATED THERMAL POMER.

P-7 prevents or defeats the automatic block of reactor trip on:

Low flow in more than one primary coolant loop, reactor coolant pump under-voltage a'nd under-frequency, turbine trip, pressurizer low pressure, and pressurizer high level.

P-8 prevents or defeats the automatic b'1ock of reactor trip on low coolant flow in a single loop.

P-10 prevents or defeats the manual bIock of:

Power range low setpoint reactor trip. Intermediate range reactor trip, and intermediate range rod stops.

Provides input to, P-T.

O. C.

COOK-UNIT 1

3/4 3-9 82040b0058 820329 PDR ADOCK 05000315 P

PDR

CHAIRMAII~~THE BOARD A

)IEF EXECUTIVE OFFICER AEPSC IHOIANA4 tiIICHIGAtlELECTRIC CO.

.AND OTHER AEP SUBSIDIARIES 0

VICE CH IRMAtl HP INDIAtlA 8 tiIICHIGAH CONSTRUCTION FLECTRIC CptiIPAHY AEPSC EXECUTIVE VICE PRESIDENT

~ CONSTRUCTION VICE PRESIDENT AHD NEW YORK AHD INDIANA4 tiIICHIGAt<

ENGIHEERIHG ELECTRIC CpfiIPAHY AEPSC I l I I t l l l I I t l I 1 l I 1 1 3 i ENGItlEERIHG DIVISIONS Il l I 3 3 l I I I 313 I I I I I I I 1 AEPSC

.'iIAtlAGER QUALITY ASSURANCE AEPSC PLAilTMAtIAGER DONALD C. COOK NUCLEAR PLANT PLANT QUALITY ASSUR AtlC E SUP ER VISOR APti1INIS i RATIVE 8 TECIIttICAL SUPERVISION T 'HICALSUP RVISiptl FUIICTIOHALDIRECTION TEC,".IIICALLIAISO'I AplilltiISTRATIVE figure 6.2-1 Offsice Organization for "-acilicv Management and echnical SUDDoz'r D.C.

COOK UNi.

1 6-2

PLANT MANAGER ADMUIISTRATIVE SUPERVISOR MAINTENANCE SUPERHITENDENT OPERATIONS SUPERINTENDENT SOL TECHNICAL SUPERIITTENDENT CHIEF SECURITY SUPERVISOR STAFF STAFF PROD. SUPV.

OPERATIONS SOL FIRE PROTECTION COORDINATOR OA SUPERVISOR SHIF1'ECURITY SUPERVISOR TRAINING COORDINATOR SHIFT SUPERVISOR SOL ASSISTANI'HIF 1'UPERVISOR SOL NUCLEAR COMPUTER ENGINEERING SUPERVISOR PERFORMANCE SUPERVISING ENGINEER CONTROL AND INSTRUMENT SUPERVISOR PLANT CHEMICAL SUPERVISOR PL NT RADIATION PROTECTION SUPERVISOR ENVIRONMENTAL COORDINATOR l.EGEHDT SOL SENIOR OPERATOR LICENSE OL-OPERATOR LICENSE

~ KEY SUPERVISORY PERSOISIEL

<<~ REPOR'TS ADMINISTRATIVELYTO PLANT MANAGER AND TECHNICALLY TO AEPSC OA MANAGER sa EffECTIVE 7/I/St-HOLDS RO UNTIL THA1'ATE

~ ooo - ADMINISTRATIVE UNIT SUPERVISOR SOL>>

REACTOR OPERATOR OL AUIOLIAR Y EOUIPMENT OPERATOR PERFORMANCE ENGINEER SHIFT TECHNICAL ADVISOR PERFORMANCE ENGINEER INSTRUMENT MAINTENANCE SUPERVISOR TECHNICIANS CHEMICAL SUPERVISOR TECHNICIANS RADIATION PROTECTION SUPERVISOR FIGURE 6.2-2 FACILITY ORGANIZATIONDONALD C. COOK-UNIT No.l

~

. ADNIiVlSTRATIVECONTRO 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'or comparable positions, except for (1) the Radiation Protection Supervisor who shall meet or exceed the quali-fications of Regulatory Guide 1.8, September

1975, and (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.

6.3.2 Until the newly appointed Operations Superintendent obtains a Senior Reactor Operator's License; all of his licensed functions will be performed by a full time assistant who holds a current Senior Reactor Operator's License.

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 and shall meet or exceed the requirements and recommendations of Section 5.5 of ANSI N18.1-1971 and Appendix "A" of 10 CFR Part 55.

6.4.2 A training program for the Fire Brigade shall be maintained under the direction of the Plant Mi nager and shall meet or exceed the require-ments of Section 27 of the NFPA Code-1976.

6.5 REVIEW AND AUDIT 6.5.1 PLANT NUCLEAR SA1.'ETY REVIEW CO>iMITTEE (PNSRC)

FUNCTION 6.5.1.1 The PNSRC shall function to advise the Plant Manager on all, matters related to nuclear safety.

D.

C.

COOK UNIT 1

6-5

0

~

~

r gtIHISTRATIVE COHTROLS COHPOSITIOH 6.5.1.2 The PHSRC shall

~ ~

~

Chairman:

member:

Member:

Hember:

Member:

Member:

Hember:

Member:

h)ember:

'ember:

Member"r Member:

"ALTERNATES be composed of the:

Plant Nanager or designated alternate Assistant Plant Managers Operations Superintendent Technical Supezint endent Haintenance Superintendent Control and Instr'umen4 Supervisor Nuclear/Computer Engineering Supezvisor Fl.ant Chemical Supervisor Performance Supervising Engine r

.. Plant Radiation Protection Supervisor Shift Supervisor Environmental Coordinator 6.5.1.3 All alternate members shall b

appointed in writin by the PHSRC Chairman to serve on a temporary basis;

however, no more than

.,vo alternates shall participate as voting embers in PNSRC activities at any one time.

~ ~

V HEETIHG FREQUEHCY 6.5.1.4 The PHSRC shall meet at,'east once per ca1endar month and as convened by the PHSRC Chairman or his d signated al ornate.

OUORUN 6.5.1.5 A quorum of the PHSRC shall consist of the Chairman or his designated alternate and four embers including alternates.

RESPOHSIB ILITIES 6.5.1.6 b.

The PiISRC sha11 he responsible or:

Review of 1) a11 procedures required by Specification 6.8 and changes

thereto,

2) any other proposed procedures or changes thereto as determined by th P1ant Manager to affec nuclear safety.

Review of a11 proposed tests and experiments that a=feet nuclear safety.

0 C.

COOK - UHIT 1

4 6.7 SAFEST Y LENET VEOLATION 6.7.1 The following actions shall be taken in the event a Safety Limit is violated:

a.

b.

The facility shall be placed in at least HOT STANGSY within ane hour.

1 The Safety Limit violation shall be reported to the Commissfon and to the Chairman of the NSDRC. within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

c.

A Safety Limit Yf'olatfon Report shall be prepared, 'he report shall be reviewed by the PNSRC.

This report shall descrtbe

'I}'applicable. circumstances preceding the violation, (2) effects af the violation upon facility components, systems or structur s, and. (3) corrective action taken to prevent recurrence.

d.

The Safety Limit Violation Report shall be submitted to the

~ Commission, the Chairman of.,the

NSDRC, and the Executive Vice President-Construction'nd Hex York Engineering AEPSC within

'4 days of the violatipp.

~

~

6.8 PROCEDURES 6.8.I Mrf ten procedures shall be eswblished, implemented and main-lined cavering the activfti s referenc d below:

a.

Tne applicable procedures recommended in Appendix "A" of Regulatory Cufde 1.33,

November, 1972.

b.

Refueling operations.

c.

Surveillance and.est ac.fvfties of safety r clat d equi pnent.

d.

Security Plan implementation.

e.

wer ency Plan impl eaentatfan.

Fire Prate tion Program implementation.

l 6.8.2

"=acn procedure and acministratfve policy of 6.8.1

above, changes

thereto, snail be revfe~wed by the PNSRC and approved by Plan>><tanager prior ta impl ementatfon and reviewed periodfcallj forth in adminis.ra;ive proc dures.

and

'l>>h e D. C.

COOK - UNET I 6-1 3 Anendment Na.

22

ATTACHMENT NO.

3 TO AEP:NRC:00659 REVISED TECHNICAL SPECIFICATION PAGES FOR D.C.

COOK UNIT NO.

2

DESIGNATION-TABLE 3.3-1 (Continued)

CONDITION ANO SETPOINT FUNCTION P-7

~ With 2 of 4 Power Range Neutron Flux Channels llew of RATED THERMAL POWER or 1 of 2 Pressure Before

. The First Stage channels

> 66 psia.

P-7 prevents or defeats the automatic block of reactor trip on:

Low flow in more than one primary coolant loop, reactor coolant pump under-voltage and urder-frequency, turbine trip, pressurizer low pressure, and pressurizer high level.

P-8 P-lo With 2 of 4 Power Range Neutron Flux channels

> 51Ã of RATED THERMAL POWER.

With 3 of 4 Power range neutron flux channels 9.o of RATED THEEQL POWER.

P-8 prevents or defeats the automatic block of reactor trip on low coolant flow in a single loop.

P"10 prevents or defeats the manual block of:

Power range low setpoint reacto~

trip, Intermediate range reactor trip, and intermediate range rod stops.

Provides input to P-7.

0.

C.

COOK - UNIT 2 3/4 3-8

CHAIRtlAt THE BOARD, A

HIEF EXECUTIVE OFFICER AEPSC INDIANA4 iYilCHIGAH ELECTRIC CO.

Atl0 OTHER AEP SUSSIDIARIES 0

0 VICE CHAIRMAN VICE PRESIDENT ENGINEERIHG At(0 AHO INDIANAg ig!CH! GAH CONSTRUCTION ELECTRIC COtiIP A tt Y AEPSC EXECUTIVE VICE P RESIDENT

~ COtlSTRU CTION VICE PRESIDENT AHD tlE'N YORK AHD ItlDIANA4 MICHIGAN EHGIHEERING ELECTRIC COMP AtlY AEPSC llllllllllllllll Illc; EilGIHE RIH G DIVISIONS AEP SC MANAGER IIIIIIIIIIIIIIIIIIIII~

. LITY ASSURAHCE AEPSC PLAiVT i'ilANAGER DONALD C. COOK tIUCLEAR PLANT P LAtl7 gUALIT ( ASSURAHCc SUP ERVISOR ADMINISTRATIVE 4 7

CHHICAL SUPERVISION TE H N I C AL SUP =RVI5lO'I FUNCTIONAL DIRECTION Tc"""ICAL LIAI~O'I D.C.

COOK - Ii'.ITT 2 6-2

~ '

ACXIN!ST RAT!VE Figure 6.2-l Cfzsf.te Organization ror Facility.'!anagernent and:ec'nnical Support

PLANT h)ANAGKR ADMNISTRATIVK SUPERVISOR MAINT E NANCE SUPERINTENDENT OPERATIONS SUPERINTENDENT SOL

" TECHNICAL SUPE'RINTKNDEN'T CHIEF SECURITY SUPERVISOR STAFF STAFF PROD. SUPV.

OPERATIONS SOL F IRK PROTECTION COORDINATOR OA SUPERVISOR SHIFT SECURITY SUPERVISOR TRAININO COORDINATOR SHIFT SUPERVISOR SOL ASSISTANT SHIF T SUPERVISOR SOL N CLEAR COMPUTER ENOINEERIND SUPERVISOR PERFORMANCE SUPERVISINO ENOINEER CONTROL AND INSTRUMENT SUPERVISOR PLANT CHEMICAL SUPERVISOR PLANT RADIATION PROTECTION SUPERVISOR ENVIRONME'NTAL COORDINATOR LKGEHOl SOL SENIOR OPERATOR UCKNSE OL OPERATOR UCENSK

~

KEY SUPERVISORY PERSOISIKL e~ REPORTS ADMINISTRATIVELYTO PLANT MANAGER AND TECHNICALLY TO AEPSC OA MANAGER

~o-EFFECTIVE T/I/SE-HOLDS RO UNTIL THAT DATE

~ ooo - ADMINISTRATIVE UNIT SUPERVISOR SOL~

REACTOR OPERATOR OL AUXILIARY EOUIPMEN'T OPERATOR PERFORMANCE ENOINEER SHIFT T EC HRICAL ADVISOR PERFORMANCE ENOINKER INSTRUMENT MAINTEHANCE SUPERVISOR TECHNICIANS CHEMICAL SUPERVISOR RADIATION PROTECTION SUPERVISOR TECIVIICIANS FIGURE 6.2-2 FACILITY ORGANIZATIONDONALD C. COOK-UNIT No.2

l 6.0 ADMINISTRATIVE C OLS 6.3 FACILITY STAFF UALIFICATIONS 6.3.1 Each member of the facility staff shall meet or exceed the minimum quali-fications of ANSI N18.1-1971 for comparable positions, except for (1) the Radiation Protection Supervisor who shall meet or exceed the qualifications of Regulatory Guide 1.8, September

1975, and (2) the Shift Technical Advisor who snail 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.

6.3.2 Until the newly appointed Operations Superintendent obtains a Senior Reactor Operator's License, all of his licensed functions will be performed by a full time assistant who holds a current Senior Reactor Operator's License.

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 and shall meet or exceed the requirements and recommendations of Section 5.5 of ANSI N18.1-1971 and Appendix "A" of 10 CFR Part 55.

6.4.2 A training program for the Fire Brigade shall be maintained under the direction of the Plant Manager and shall meet-or exceed the requirements of Section 27 of the NFPA Code-1976.

6.5 REVIEW AND AUDIT 6.5.1 PLANT NUCLEAR SAFETY REVIEW COMMITTEE PNSRC) 6.5.1.1 The PNSRC shall function to advise the Plant Manager on all matters related to nuclear safety.

COMPOSITION 6.5.1.2 The PNSRC shall be composed of the:

Chairman:

Member:

Member:

Member:

Member:

Member:

Member:

Member:

Member:

Member:

Member:

Member:

Plant Manager or designated alternate Assi'stant Plant Managers-Operations Superintendent Technical Superintendent Maintenance Superintendent Control and Instrument Supervisor Nuclear/Comput'r Engineering Supervisor Plant Chemical Supervisor Performance Supervising Engineer Plant Radiation Protection Supervisor Shift Supervisor Environmental Coordinator D.

C.

COOK UNIT 2 6-5

AGMINISTRATIYE TROLS 6.7 SAFETY LIMIT VIOLATION 6.7.1 The following actions shall be taken in the event a Safety Limit is violated:

a.

The facility shall be placed in at least HOT STANOBY within one hour.

b.

.The. Safety Limit violation shall be reported to the Commission and to the Chairman of the NSDRC within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

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 violation upon facility components, systems or structures, and

~ (3) corrective action taken to prevent recurrence.

d.

The. Safety Limit Violation,Reaort.shall he. submitted to the Coimnissfon,.the.'Chairman of the'SDRC,.and,the Ececutive Vice President&onstruction and New York Engineering AEPSC within l4 days of the violation.

6.8 PROCEOURES 6.8.1 Mritten procedures shall be established, implemented and main-tained covering the activities refer need below:

a.

The applicable procedures recommended in Appendix "A" of Regulatory Guide 1.33,

November, 1972.

b.

Refueling operations.

c.

Surveillance and test activities of safety related equipment.

d.

Security 'Plan implementation.

e.

Emergency Plan implementation.

f.

Fire Protection Program implementation.

6.8.2 Each proc dure of 6;8.1

above, and changes

thereto, shall be reviewed by the PNSRC and approved by the Plant Manage orior zo imole-mentation and reviewed periodically as set forth in adminis rative procedures.

0.

C.

COCK - UNIT 2 6-13

gI