ML19338D554

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Proposed Revisions to Tech Specs,Pages 3/4 3-51 & 52, B 3/4 3-3,6-5,6-6 Re post-accident Monitoring Instrumentation & Min Shift Crew Composition
ML19338D554
Person / Time
Site: Brunswick  Duke Energy icon.png
Issue date: 09/16/1980
From:
CAROLINA POWER & LIGHT CO.
To:
Shared Package
ML19338D553 List:
References
NUDOCS 8009230439
Download: ML19338D554 (10)
v • d • e


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TABLE 3.3.5.3-1

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' POST-ACCIDENT MONITORING INSTRUMENTATION.-

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MINIMUM NO.

OF OPERABLE ~-

+

INSTRUMENT y.

CHANNELS INSTRUMENT AND INSTRUMENT NUMBER.

T

'i1.: ! Reactor vessel waterLlevel 2

T

'.(B21-LITS-N026A, B;1B21-LR-615;;B21-LI-R604A, B-and B21-LITS-NO37) 12.

.Rea'ctor vessel. pressure ~

2

~

~

(B21-PI-R004A, B; C32-LPR-R608 and.C32-PT ~

N005A, B)_

' ~

i p

2 3 3. - scontainment-pressure

,(CAC-PI-2599; CAC-PT-2599; CAC-PR-1257-1

.i and CAC-PT-1257-1).

4 K

4;.

Cotitainment, pressure 2

.(CAC-TR-1258-1 thru-13,- 22, 233,24 and C91-P602) 5.

Suppressi5n chamber atmosphere temperature 2

(CAC-TR-1258-17 thru 20 and C91-P602)

~

6.'

Suppression chamber l water level 2

-(CAC-LI-2601-3; CAC-LA-2602; CAC-LT-2601;

^

CAC-LT-2602"and CAC-LY-2601-1)

H 7.1

-Suppressica chamber. water temperature 2

.(CAC-TR-1258-14,'21 and C91-P602)

i 8.-

Containment radiation 2

c.

(CAC-AR-1260: CAC-AQll-1260-1, 2, 3; CAC-AR-

- 1261; CAC-AQL-1261--1, 2, 3; CAC-AR-1262 and sCAC-AQll-1262-1, 2,:3) 2 9.-

Containment oxygen

.j

- (CAC-AT-1259-2; CAC-AR-1259;- CAC-AT--1263-2 and -

'i CAC-AR'1263);

~

-Ps 10.) Containment hydrogen 2

- :(CAC--AT-1959-1; CAC-AR-1259; _- CAC-AT-1263-1 and.

p f

[CAC-AR-1263).-

i

,j,

[

111. ISa$5ty relief'alve position indicatis 1/ valve

  • v

,' Primary -; Sonic..(B21 -FY-4157 thru.

37)-

.12.. Safety:;relicfivalve,positionfindication:

.%condary - 1/ valve *

[

f iTemp. (I}21-TR-R614. points 11-11) -

.~

~

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['E f*Witheithhr! indication {5fjavalvejINOPERABLE,operationmay'continueaslong tasythatl. valve'~ 1s other indication is.0PERABLE.

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q TABLE 4.3.5.3 '

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POST-ACCIDENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS-g.

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e

~

CHANNEL CHANNEL f.l.$.l LINSTRUMENT'AND INSTRUMENT NUMBER

' CHECK

- CALIBRATION ^

-e

. Q;.

M R

7:

ol.'

1 Reactor l vessel' water leve' lg l (B21-LITS-N026A,B; B21-LR-R615; - B21-LI-R604A,B and. B21-LITS-NO37)

~

4 s

"M R

w, N

2.

~ Reactor. vessel pressure m

-(B21-PI-R004A,B;1C32-LPR-R608 and C32-PT-N005A,B)-

.M

.R i

3.

I Containment pressure :

' *::(CAC-PI-2599; CAC-PT-2599; CAC'-PR-l'257-l'and CAC-PT-1257-1)-

+

M.

R-

'P

- 4.;

l Containment temperature-.

,(CAC-TR-1258-1 thru 13, 22, 23, 24 and C91-P602)

M

'R

'5..

Suppression chamber atmosphere temperature (CAC-TR-1258-17 thru 20' and C91-P602)

M R

u.

6.-

. Suppression chamber water level 1

(CAC-LI-2601-3; CAC-LR-2602; CAC-LT-2601; CAC-LT-2602 and 'CAC-LY-2601-1)

.y:

M R-u'

'7.

Suppression chamber water temperature (CAC-TR-1258-14, 21 and C91-P602);

M.

R 8.

mContainment radiation-(CAC-AR-1260; CAC-AQH-1260-1,2,3;.CAC-AR-1261; CAC-AQH-1261-1,2,3;

CAC-AR-1262 and CAC-AQH-1262-1,2,3)

M R.

9.

Containment-oxygen concentration (CAC-AT-1259-2; CAC-AR-1259;' CAC-AT-1263-2 and CAC-AR-1263)

M R

1

10. : Containment hydrogen concentration KS (CAC-AT-1259-1; CAC-AR-1259; CAC-AT-1263-1 and. CAC-AR-1263)
.i.

I I$'

11.:l Safety relief. valve position indication (Primary-Sonic)

M-R

(B21-FY-4157.thru 4167)~

u

' 12..- ' Safety. relief valve position indication (Secondary-Temperature)

M R.

(B21-TR-R614 points 1 thru 11)

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INSTRUMENTATION BASES-MONITORING' INSTRUMENTATION (Continued) 3/4.3.5.'2 REMOTE SHUTDOWN MONITORING INSTRUMENTATION The OPERABILITY of_the remote shutdown monitoring instrumentation ensures that sufficient capability is available to pemit shutdown and maintenance of HOT SHUTDOWN of the facility from locations outside of the control room.

This' capability is, required in the event control room habitability is lost and is consistent with General Design Criteria 19 of CFR 50.

3/4.3.5.3 POST-ACCIDENT MONITORING INSTRUMENTATION The OPERABILITY of the post-accident monitoring instrumentation ensures that sufficient information is'available on selected plant parameters to monitor and assess important variables following an accident.

This capability is consistent with the recommendations of Regulatory Guide 1.97 " Instrumentation for Light Water Cooled Nuclear Power Plants

)

to Assess Plant Conditions During and Following an Accident," December 1975 and NUREG-0578, "TMI-2 Lessons Learned Task Force Status Report and Short-Term Recommandations."

3/4.3.5.4 SOURCE RANGE MONITORS i

The source range monitors provide the operator with infomation on the status of the neutron levei in the core at very low power levels during startup. At these power levels reactivity additions should not be made without this flux level information available to the operator.

When the intemediate range monitors are on scale adaquate info'rmation is available withcut the SRM's and they can be retracted.

3/4.3.5.5 CHLORINE DETECTION SYSTEM The OPERABILITY of the chlorine detection systems ensures that an accidential chlorine release will be detected promptly and the necessary protective. actions will be automatically initiated to providel rotection for control room personel.

Upon detection of a high concentration of chlorine the control room emergency _ ventilation system will automatically

-isolate the control room and initiate operation in the recirculation mode-to provide the required protection. The detection systems required by_ this specifications are consistent.with the recommendations of Regulatory Guide 1.95 " Protection of Nuclear Power Plant Control Room Operators against.an accidental Chlorine Release.

BRUNSWICK-UNIT 1-B 3/4 3-3 Amendment.No.

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TABLE'6.2.2-1

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MINIMUM SHIFT CREW COMPOSITION #

Condition of Unit 1 - Unit 2 in CONDITION 1, 2 or 3

' LICENSE.

APPLICABLE OPERATIONAL '..ONDITIONS CATEGORY 1,2,3

~f 4 & 5 S0L**

2 2*

OL**

3 2

Non-Licensed 4

3 Shift Technical Advisor 1

0 Condition of Unit 1 - Unit 2 in CONDITION 4 or 5 LICENSE-APPLICABLE CATEGORY-OPERATIONAL CONDITIONS 1,2,3 4&5 SOL **

2 1*

OL**

2 2

Non-Licensed 3

3

).

Shift Technical-Advisor i

n Condition of Unit 1 - No Fuel in Unit 2 LICENSE APPLICABLE CATEGORY OPERATIONAL CONDITIONS 1,2,3 4&5 SOL 1

1*

OL 2

1

~

Non-Licensed 2

1 J

Shift Technical' Advisor 1

0

  • Does not include.the licensed. Senior Reactor, Operator. or Senior Reactor Operator Limited to Fuel Handling, supervising CORE ALTERATIONS.

1

~, ** Assumes each individual is licensed on both plants.

! Shift crew composition, including an individual qualified in radiation protection procedures, may be less than the minimum requirements for a: period of time not to exceed 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> in order to accomodate unexpected absence-of on duty shift crew members provided imediate action.is taken 'to restore the shift crew composition to within the

? minimum requirements of Table 6.2.2-1.

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. BRUNSWICK-UNIT 1 6-Si

  • Amendment No.

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ADMINISTRA?I"E: CONTROLS-6.3 ' FACILITY STAFF' QUALIFICATIONS'

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6.3.1 Each member of the. unit staff shall meet or exceed the minimum

.gualifications of ANSr N18.1-1971 for comparabic positions, except-for (1)- the 1(Radiation. Protection' Manager) who shall meet ~or exceed the -.

qualifications of Regulatory Guide 1.8, Sept. ember 1975 and-(2).the Shift-Tect.nical: Advisor who shall have a bachelor's degree or equivalent in a.

scientific 1or. engineering' discipline with specific training in plant design, and response and analysis of the plant for transients and. accidents.

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 Supervisor-and-shall meet or execca the requirements and recommendas.fons 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 naintained un' der.-

the direction of the' Plant Fire Chief and shall meet or exccad the requirements'of Section 27 of the NFPA Code-1975.

6.5..

REVIDJ AND AUDIT 6.5.1-PLANT NUCLEAR SAFETY COMMITTEE (PNSC)-

FUNCTION 6.5'1,1 The PNSC.shall function to' advise the General Manager on all matters'related to nuclear safety.

COMPOSITION 6.5.1.2. The PNSC shall be composed of the:

' Chairman:

Plant General Flanager Vice Chairman:

Operations Manager, Maintenance Manager, Technical - Administrative Manager or Director-Nuclear Safety and QA Secretary:

Administrative Supervisor Member:

iMaintenance Supervisor (I6C)

Member:

Maintenance Supervisor-(Mechanical).

Member:-

. Engineering Supervisor -

Member:

-Environmental-and-Radiation Control

~

Supervisor' '

Quality Assurance Supervisor

. Member:

" Member:

Shift Operating Supervisors

, Member:

Training Supervisor ALTERNATES' 6.5.1.3 A111 alternate members :shall be-appointed in 'vriting by the PNSC Chairman to nerve on.a temporary basis; however,.no more than two alternates'shall participato as' voting members in PNSC activities at.any-7 one time.

. BRUNSN. _ICK.- UNIT. ll.

! 6-6 Amendment.No.-

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POST ACCIDENT-MONITORING INSTRUMENTATION:

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-MINIMUM NO.-

s

+

1OF OPERABLE' LINSTRUMENT' 11NSTRUMENT AND INSTRUMENT NUMBER CllANNELS '

- 1. -.

Reactor vessel water -level-2 1(B21-LITS-NO26A,at.B21-LR-615; B21-LI-R604A,B E

~and~321-LITS-NO37)?

2.-

iReactor.. vessel pressur'e) 2 l(B21-PI-R004A, B; C32-LPR-R608'and-C32-PT-N005A, B)-

23.

~ Containment pressure 2

-.(CAC-PI-2599; CAC-PT-2599; CAC-PR-1257-1 and CAC-PT-1257-1)-

' 4. -

Contaihment pressure 2

(CAC-TR-1258-1 thru 13, 22, 23, 24 and C91-P602)

5. -

Suppression chamber' atmosphere temperature 2-i (CAC-TR-1258-17'thru 20 and C91-P602) 6.

~ Suppression chamber water level 2

(CAC-LI-2601-3; CAC-LA-2602;.CAC-LT-2601; CAC-LT-:2602.and CAC-LY-2601-1)'

7.

' Suppression' chamber water temperature 2

.(CAC-TR-1258-14, 21 and-C91-P602) y 8.'

Containment: radiation.

2

'(CAC-AR-1260;..CAC-AQll-1260-1, - 2, 3; CAC-AR-

~1261;iCAC-AQ!!-1261-1, 2~'3; CAC-AR-1262 and CAC-AQll-1262-1, 2s'3)J

~

9.' ' Containmentioxygen-2

~ 1

(_ CAC-AT-1259-2; CAC-AR-1259; CAC-AT-1263-2 ~ and y

LCAC-AR-1263)

, 10._ Containment hydrogeni.

2 l(CAC-AT-1959-1;;CAC-AR-1259;TCAC-AT-1263-1 and

'CAC-AR-1263)

~ 11.1 SafetyJrelieffvalve positionfindication:

1/ valve

  • 1 Primary - Sonic ;(B21-FY-.4157 thru ?4167)

V e_?

12.j l Safety. relief Tvalve posit: ion _ indication:

Secondary y : -1/ valve *

~'

. Tempc. (B21-TR-R614l points 1-11)-

?

  • With' either? indication of a. valve. INOPERABLE,; oper.cion may continue ~as long-M,

- asEtha6 valve's other! indication-is. OPERABLE.

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s 1 4 13/4;3-51i

.-Amendment No.-

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i TABLE 4.3.5.3-1 POST-ACCIDENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS e >.

~f CHANNEL' CHANNEL '

. E; l

. CHECK CALIBRATION 3'

INSTRUMENT AND INSTRUMENT NUMBER

$i

~

M

.R:

  • Reactor vessel water level-f
1..

-_ (B21-LITS-N026A,B; B21-LR-R615; B21-LI-R604A,B -and B21-LITS-NO37)

.- -2 ;

M R

' Reactor: vessel pressure

2..

.(B21-PI--R004 A,B; C32-LPR-R608. and' C32-PT-N005A,B)

'M

'R 3.1 Containment pressure i(CAC-PI-2599;. CAC-PT-2599; CAC-PR-1257-1 and CAC-PT-1257-1)

M-R 4.

Containment temperature.

(CAC-TR-1258-1 thru 13, 22, 23, 24 and C91-P602)-

.M R

5.

. Suppression chamber. atmosphere. temperature

'(CAC-TR-1258-17 thru 20 and C91-P602)

N R'

6 6.

Suppression chamber' water' level Y

(CAC-LI-2601-3; CAC-LR-2602; CAC-LT-2601; CAC-LT-2602 andiCAC-LY-2601-1)

.w

.M R

A 7.

Suppression chamber water. temperature' (CAC-TR-1258-14, 21 and C91-P602)

.M R-8.

Contairment' radiation (CAC-AR-1260; CAC-AQH-1260-1,2,3; CAC-AR-1261; CAC-AQH-1261-1,2,3; CAC-AR-1262 and CAC-AQH-1262-1,2,3)'

M R

9.

Containment oxygen. concentration (CAC-AT-1259-2; CAC-AR-1259; CAC-AT-1263-2 and CAC-AR-1263)

M-R lEI 10.

Containment. hydrogen concentration (CAC-AT-1259-1; CAC-AR-1259; CAC-AT-1263-1 and CAC-AR-1263) j.

M R-3-

L11.- Safety' relief valve' position' indication (Primary-Sonic)

E..

. (B21--FY-4157 thru 4167)

M

^R.

12.

Safety relief valve position' indication (Secondary-Temperature)

(B21-TR-R614 points 1 thru 11)

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7 INSTRUENTA101 o

. BASES g

.c I MON ITORI NG INSTRUMENT ATI O'N I (Conti nued )

'3/4.3.5.2 REM 3TE SHUT 00WN MONITORING INSTRUMENTATION l

F b

LThe 0PERABILITY of the remote shutdown monitoring instrumentation '

ensures that ' sufficient capability is available to permit-shutdown and

~

d -

. maintenance of HOT SHUTDOWNLof the facility from locations outside~ of the control room.. This capability is required.in;the event control room

habitability is lost and is consistent with General Design Criterion 19 y

~-

of CFR 50.'

i

- 3/4.3.5.3 POST-ACCIDENT MONITORING INSTRUMENTATION _

[

Y The OPERABILITY of the post-accident monitoring instrumentation

~

ensures that sufficient information is aiailable on selected plant pa-f-

J rameters. to-monitor and. assess -important variables following.an accident.-

This capability is consistent with' the recomendations of-Regulatory Guide 1.97. " Instrumentation for Light Water Cooled Huclear Power Plants

]~

to Assess Plant: Conditions During and Following an Accident," December 1975 and NUREG-0578,. TMI-2 Lessons' Learned Task. Force Status Report and 2-Short-Term Recommendations."

U 3/4;3.5.4 SOURCE: RANGE MONITORS The source range monitors provide-the operator with information on.

i p

the status of:the neutron level in.the core at very low power levels ~-

'during startup.. At these power levels reactivity additions should not j

be'made without this flux -level information available to the~ operator.

cp When the intermediate range moni. tors are on scale adequate information E

~

'is'available without the SRW s3and'they can be retracted.

~

a

' 3/4. 3. 5'. SJ CHLORINE DETECTION SYSTEM.

j r

1

The 0PERABILITY of the chlorine detection systems ensures that an E

~

accidental chlorine release will be detected promptly.and.the necessary L

protective. actions will-be automatically. initiated to provide protection 7

1 ifor! control room personnel, cUpon-detection of.a high concentration ^of -

chlorine the control room emergency ventilation-system will automatically s

m (isolate the controliroom and initiate operation ~ in.the recirculation -

-modeito provide the required _ protection. The. detection systems requi.cd T byjthis specification are ; consistent with the recommendations ~ of

~

rRegulatory:GuideL1'.95." Protection.of Nuclear. Power Plant Control Room iOperators Against an; Accidental Chlorine Release "

}..

~

KBRUNS$.1CK.-!U"IT2

.B 3/4'3-3 Amendment No.

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MIt!IMUM SHIFT CREW COMPOSITIONf h*?); ~

W'

Condition of Unit 1-- Unit 2 in CONDITION 1, 2 or 3 LICENSE ~

APPLICABLE

'CATEGORYz OPERATIONAL CONDITIONS q

~

1, 2, 3 4&5 SOL **-

2 2*-

OL**-

'3 2'

Non-Licens'ed 4

3 Shift Technical Advisor 1

0

-Condition of Unit 1 - Unit-2 in CONDITION 4-or 5 LICENSE 1 APPLICABLE

- CATEGORY OPERATIONAL CONDITIONS 1, 2, 3 4&5 50L**

2 1*

OL**

2 2

Non-Licensed 3

3 l

^

Shift Technical' Advisor 1

0 Condition of Unit 1 - No Fuel in Unit 2 i-LICENSE ~

APPLICABLE CATEGORY OPERATIONAL CONDITIONS p;'

1, 2, 3 4&5 n

90L 1

1*

i f

' OL-'

2~

1 j

Non-Licensed 2

1-J

+ Shift Technical Advisor =

1 0-

~'

Does not include the licen' sed' Senior Reactor Operator or Senior.. Reactor y

Operator Limited to Fuel Handling, supervising CORE ALTERATIONS.

F

'** Assumes each individual:is licensed on both. plants..

f : Shift crew composition, including an individual qualified in radiation l protection procedures,- may-befless than the minimum requirements LforLa period ~of. time not to exceed.2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> in order to accomodate' J

.. unexpected absence ^of on' duty shift crew members provided immediate h

action-is taken to, restore-the' shift crew composition to within the

-r

~

minimum. requirements'of Table 6.2.2-1.-

},..

u TBRUNSNICK-UNIT 2? '

"6-5i

-Amendment No.:

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ADMINISTRATIVE CONTROLS 6.3 FACILITY STAFF QUALIFICATIONS 6.3.1.Each member of the unit staff shall meet or exceed the minimum qualifications of nNTSI N18.1-1971 for comparable positions, except for (1) the (Radiation Protection Manager) who shall meet or exceed the qualifications of Regulatory Guide 1.8, September 1975 and (2) the Shif t 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.

6.4 TRAINING 6.4.l' A retreining and replacement training program for the facility staff shall be maintained under the direction of the Training Supervisor 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 Fire Chief and shall meet or exceed the requirements of Sectien 27 of the NFPA Code-1975.

6.' 5 REVIEW A'ID AUDIT 6.5.1 PLANT NUCLEAR SAFETY COMMITTEE (PNSC)

FUNCTION 6.5.1.1 The PNSC shall function to advise the General Manager on all matters related to nuclear safety.

COMPOSITION 6.5.1.2 The PNSC shall be composed of the:

Chairman:

Plant General Manager Vice Chairman:

Operations Manager, Maintenance Manager, Technical - Administrative Manager or Director-Nuclear Safety and QA Secretary:

Administrative Supervisor Member:

Maintenance Supervisor (I&C)

Member:

Maintenance Supervisor (Mechanical)-

Member:

Engineering Supervisor Member:

Environmental and Radiation Control Supervisor Member:

Quality Assurance Supervisor Member:

Shift Operating Supervisors Member:

Training Supervisor ALTERNATES

6. 5.1.'3 All alternate members shall be appointed in writing by the PNSC Chairman to serve on a temporary basin; however, no more than two alternates shall participate as voting raembers in :'NSC activities at any one time.

BRUNSWICK - UNIT 2.

6-6

. Amendment No.

_

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