ML19350C107

Amend 37 to License NPF-3,adding Tech Specs Incorporating Certain TMI Lessons Learned Category a Requirements

ML19350C107
Person / Time
Site:	Davis Besse
Issue date:	03/24/1981
From:	Stolz J Office of Nuclear Reactor Regulation
To:	Cleveland Electric Illuminating Co, Toledo Edison Co
Shared Package
ML19350C108	List: ML19350C107 ML19350C110 ML19350C111
References
TAC 42596, NPF-03-A-037 NUDOCS 8103300485
Download: ML19350C107 (21)

Text

.

9 4r UNITED STATES y

NUCLEAR REGULATORY COMMISSION j

WASHINGTCN, D. C. 20555 a

'$ *.... /

THE TOLEDO EDISON CCMPANY AND THE CLEVELAND ELECTRIC ILL'JMINATING CCMPANY DOCKET NO. c0-346 DAVIS-BESSE NUCLEAR POWER STATION, UNIT NO. 1 AMENDNENT TO FACILITY OPERATING LICENSE Amendment No. 37 License No NPF-3 1.

The Nuclear Regulatory Comission (the comission) has found that:

A.

The application for amendment by the Toledo Edison Company and The Cleveland Electric Illuminating Company (the licensees) dated Septed er 16, 1980, complies with the standards and require-ments of the Atomic Energy Act of 1954, as amended (the Act) and the Comission's rules and regulations set forth in 10 CFR Chapt'.r I;

B.

The facility will operate in confomity with the application, the provisions of the Act, and the rules and regulations of the Comission; C.

There is reasonable assurance (1) 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 Comission's regulations; D.

The issuance of this amendment will not be inimical to the comon defense and security or to the health and safety of the public; and E.

The issuance of this amendment is in accordance with 10 CPR Part 51 of the Comission's regulations and all applicable requirements have been satisfied.

l l

l l

810 3 3 0 0M

4 i 2.

Accordingly, Facility Operating License !o. 'JF-3 is hereby amended as indicated below and by changes to the Technical Specifications as indicated ir. the attachment to this license amendment:

Revise paragraph 2.C.(2) to read as follows:

Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 37, are hereby incorporated in the license.

The Toledo Edison Company shall operate the facility in accordance with the Technical Specifications.

3.

This license amendment is effective as of the date of its issuance.

4 FOR THE NUCLEAR REGULATORY CCPliISSICN

',. N T[

u a<l 'l.

~ * ' '

J hn F. Stolz, Chief Chepa,tingReactorsBranch#4 Division of Licensing

Attachment:

Changes to the Technical Specifications Date of issuance:

March 24, 1981 l

l

ATTACHMENT TO LICENSE A!!EtiDitENT NO. 37 FACTLITY OPERAT:.*1G LICENSE NO. fiPF-3 u0CKET I40. 50-346 Replace the following pages of the Appendix "A" Technical Specifications with the enclosed pages as indicated. The revised pages are identified by Amendment number and contain vertical lines indicating the area of change. The corresponding overleaf pages are also provided to maintain document completeness.

Paoes 1-8 3/4 3-10 3/4 3-11

{

3/4 3-12 3/4 3-21 3/4 3-22 3/4 3-27 3/4 3-48 3/4 3-50 6-4 6-5 I

E

. TABLE 1.1 OPERATIONAL MODES REACTIVITY

% RATED AVERAGE COOLANT MODE

. CONDITION, K,ff THERMAL POWER

• TEMPERATURE 1.

POWER OPERATION 3_0.99

> 55 280*F 1

2.

STARTUP 1 0.99 j; 5;

> 2E0*F

-3.

HOT STANDBY

< 0.99 0

3,230'F 4

HOT SHUTDOWN

< 0.99 0

280*F > T,,,9 > 200'F 5.

COLD SHUTDOWN

< 0.99 0

j; 203*F-6.

REFUELING **

< 0.95 0

< 141*F r

• Excluding decay heat.

Reactor vessel head unbolted or receved anc fuel:in the vessel.

1 i,

i I

' DAVIS-3 ESSE, UNIT 1

1 7

TABLE 1.2 FREQUENCY NOTATION NOTATION FREQUENCY S

At least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

9 At least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

W At least once per 7 days.

M At least once per 31 days.

Q At least once per 92 days.

SA At least once per 6 months.*

e R

At least once per 18 months.*

S/U Prior to each reactor startup.

N.A.

.Not applicable.

~i-

• In these Technical Specifications, 6 months is defined to be 184 days, and 18 months is defined to be 550 days.

t l

. DAVIS-BESSE, UNIT l-1 8-Amendment No. 37

i I

I INSTRUMENTATION l

3/4.3.2 SAFETY SYSTEl. INSTRUMENTATION j

SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION LIMITING CONDITION FOR OPERATION 3.3.2.1 The Safety Features Actuation System (SFAS) functional units shown in Table 3.3-3 shall be OPERABLE withatheir trip setpoints set consistent with the values shown in the Trip Setpoint column of Table 3.3-4 and with RESPONSE TIMES as shown in Table 3.3-5.

APPLICABILITY: As shown in Table 3.3-3.

ACTION:

a.

With a SFAS functional unit trip setpoint less conservative than the value shown in the Allowable Values column of Table 3.3-4, declare the functional u. tit inoperable and apply the applicable ACTION requirement oi Table 3.3-3, until the func-tional unit is restored to OPERABLE status with the trip setpoint adjusted consistent with the Trip Setpoint value.

b.

With a SFAS functional unit inoperable, take the action shown in Table 3.3-3.

SURVEILLANCE REOUIREMENTS 4.3.2.1.1 Each SFAS functional unit shall be demonstrated OPERABLZ by the performance of the CHANNEL CHECK, CHANNEL CALIBRATION and CHANNEL FUNCTIONAL TEST during the MODES and at the frequencies shewn in Table 4.3-2.

4.3.2.1.2 The logic for the bypasses shall be demonstrated OPERABLE during the at power CHANNEL FUNCTIONAL TEST of functional units affected by bypass ops. ration. The total bypass function shall be demonstrated OPERABLE at least once per 18 months during CHANNEL CALIBRATION testing of each functional unit affected by bypass operation.

4.3.2.1.3 The SAFETY FEATURES RESPONSE TIME of each SFAS function shall be demonstrated to be within the limit at least once per 18 months.

Each test shall include at least one functional unit per function such that all functional units are tested at least once every N times 18 months where N is the total number of redundant functional units in a specific SFAS function as shown in the " Total No. of Units" Column of Table 3.3-3.

DAVIS-BESSE. UNIT 1 3/4 3-9

3 y!

TABLE 3.3-3 T5 Y'

SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION El

$1 MINIMUM TOTAL NG.

UNITS UNITS APPLICABLE FUNC110NAL UNIT OF UNITS TO TRIP OPERABLE MODES ACTION c:

E

{,1 1.

INSTRUMENT STRINGS a.

Containment Radiation -

liigh 4

2 3

1,2,3,4,6****

9#

l b.

Containment Pressure -

liigh 4

2 3

1,2,3 9#

c.

Containment Pressure -

liigh-liigh 4

2 3

1, 2, 3 9#

d.

RCS Pressure - Low 4

2 3

1, 2, 3

• 9#

e.

RCS Pressure - Low-Low 4

2 3

1, 2, 3**

9#

Ag f.

BWST Level - Low 4

2 3

1,2,3 9#

2 OUTPUT LOGIC y

Es a.

Incident Level #1:

Containment Isolation 2

1 2

1,2,3,4,6****

10 l

b.

Incident Level #2:

liigh Pressure Injection and Starting Diesel gr Generators 2

1 2

1, 2, 3, 4 10 g

c.

Incident Level #3:

gt Low Pressure Injection 2

1 2

1, 2, 3, 4 10 g

d.

Incident Level #4:

Containment Spray 2

1 2

1, 2, 3, 4 10 c'

E?

e.

Incident Level #S:

Containment Sump

. t!

Recirculation 2

1 2

1,2,3,4 10

I j.

TABLE 3.3-3, E

5 SAFETY FEATURES ACTilATION SYSTEM INSTRUMENTATION T

HINIHilH M

TOTAL NO.

IlNiiS UNI 15 APPLICAllLE fi FUNCTIONAL UNIT Of UNils TO TRIP OPIRAllLE N0 DES ACTION 5

3.

HANUAL ACTUATION a.

SFAS (except Containment Spray and Emergency Sump 2

2 2

1,2,3,4,6****

11 Recirculation) h.

Containment Spray 2

2 2

1, 2, 3, 4 11 4.

SEI)UENCE LOGIC CilANNELS 4

2***

4 1, 2, 3, 4 98 S.

INTERLOCK CilANNELS w1 a.

Decay lleat Isolation Valve 1

1 1

1.2,3,4,5 127 0

b.

Pressurizer lleaters 2

2 2

3,4,5 139 R

3,+

E.

e

TABLE 3.3-3 (Continuedi i

TABLE NOTATION I

Trio function may be bypassed in this MODE with RCS pressure belcw 1800 :sig. Sycass shall be automatically removed when RCS pressure exceeds 1800 psig.

t Trip fun: tion may be bypassed in this MCCE with RCS pressure below 600 psig. Bypass snall be automatically re oved when RCS pressure exceeds 600 psig.

Cne must be in SFAS Channels el or #3, the other must be in Channels

!2 or #4 This instrumentation must be OPEMBLE during core alterations or movement of irradiated fuel within the containment to meet the require-ments of Tech. Spec. 3.9.4 The crovisions of Specification 3.0.4 are not applicable.

d ACTION STATEMENTS

~

ACTION 9 -

With the nuder of OPEMBLE functional units one less than the Total Number of Units, startup and/or power operation may proceed provided both of the following conditions are satis fied:

a.

The inoperable functional unit is placed in the tripced condition within ene hcur.

b.

The Minimum Units OPERASLE require'ent is met; how-ever, one additional functional unit may be bypassed for up to 2 hcurs for surveillance testing per Specification 4.3.2.1.1.

ACTIC. 10 -

With any com;cnent in the Output Lc3 c inoperable, trip 1

the asscciated components within one hour or be in at least HOT STANCSY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.

l ACTION 11 -

With the number of OPERABLE Units one less than the Total Number of Units, restore the inoperable functional unit to OPERABLE status within A8 hours or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SFUT30WN with-i l

in the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.

l ACTION 12 -

a.

With less than the Mimimum Units OPEMBLE and reactor coolant pressure > 438 psig, both Dectf Heat Isola-tion Valves (DHil and DH12) shall be verified closed.

I b.

With Less than the Minimum Units OPEMBLE and reactor coolant pressure < 438 psig operation may continue; l

however, the functional unit shall'be OPERABLE prior i

to increasing reactor coolant pressure above 438 9sig.

t ACTION 13 -

With less than the Minimuu Units OPEMBLE and reactor coolant pressure <438 psig, operation may continue; however, the func-tional unit shall be OPERA 8LE prior to increasing reactor coolant pressure above 438 psig, or the inoperable functional unit shall. be placed in the tripped state.

DAVIS-BESSE, UNIT 1 3/4 3-12 Amendment No. M 17

[2 TARIf 4.1-2 SAFETY FEATURES ACTUAll0N SYSTIM INSTRilHifHATION SilRVEILLANCE Rff)llIRIHlitiS C

us."

CilANflEL H0 DES IN WillCll CilANHLL CilANi1Et Filfl(.i10NAL SilRVfiti ANCE FUNCTIONAL UNIT CHICE CA1 II;ilAll0N II SI RI f)tlIRIO j~

1.

INSTRUMENT STRINGS Containment Radiatinn - liigh 5

R H

1,2,3,4,6#

l a.

b.

Containment Pressure - liigh S

H 11 ( 2 )

1, 2, 3 Containment Pressure - liigh-fligh 5

R H(2) 1, 2, 3 c.

d.

RCS Pressure - Low S

k t1 1, 2, 3 e.

RCS Pressure - Low-Low S

11 11 1,2,3 f.

BWST Level - Low S

R H

1, 2, 3 2.

OUTPUT LOGIC a.

Incident Level #1: Containment

{

Isolation S

R H

1,2,3,4,6#

l b.

Incident Level 82: liigh Pressure 4

Injection and Starting Diesel Generators S

R H

1, 2, 3, 4 c.

Incident Level #3: Low Pressure Injection S

R H

1, 2, 3, 4 2

d.

Incident Level #4: Containment 5

Spray 5

R H

1, 2, 3, 4 E

e.

Incident Level #S: Containawnt Sump Recirculation S

R H

1, 2, 3, 4 3.

MANUAL. ACTUATION m

a.

SFAS (Except Containment Spray NA NA H(1) 1,2,3,4,6#

l N

and Emergency Sump Recirculation) b.

Containment Spray NA NA M(1) 1, 2, 3 4.

SEQUENCE LOGIC CilANNELS S

NA H

1, 2, 3, 4

3

5 Y

Ma

!l5 4

TABLE 4.3-2 SAFETY FEAlllRES ACTUAil0N SYSTEM INSTRilHENTAll0N SilRVEltLANCE REQUIRENINTS CilANNEL MODES IN WHICil CilANNE L CilANNEL FUNCIIONAL SURVEILLANCE FUNCTIONAL UNIT glj cK_

CAtlHRATION, TEST REQUIRED 5.

INTERLOCK CHANNELS y

a.

Decay Heat Isolation Valve S

R 1,2,3,4,5 b.

Pressurizer Heater S

R 3,4,5

• • See Specifica tion 4.5.2.d.1 TABLE NOTA _TInN_

(1) Mtnual actuation switches shall be tested at least once per 18 months.during shutdown. All other circuitry associated with manual safeguards actuation shall rxelve a CHANNEL FUNCTIONAL r+

g TEST at least once per 31 days.

(2) The CHANNEL FUNCTIONAL TEST shall include exercising the transmitter by applying either vacuum or pressure to the appropriate side of the transmitter. The provisions of Section 3.0.3 are not applicable for the first test of each channel following the first refueling outage.

i The surveillance requirements of Section 4.9.4 apply during core alterations or movement of m

irradiated fuel within the containment.

TABLE 3.3-11 (Continued)

TABLE NOTATION May be bypassed when steam pressure is below 650 psig. Bypass shall be automatically removed when the steam pressure exceeds 650 psig.

1. The provisions of Specification 3.0.4 are not applicable.

ACTION STATEMENTS ACTION 13 - With the number of OPERABLE Channels one less than the Total Number of Channels, startup and/or power operation may proceed until performance of the next required CHANNEL FUNCTIONAL TEST provided the inoperable sec-tion of the channel is placed in the tripped condition within I hour.

ACTION 14 - With the number of OPERABLE Channels one less than the Total Number of Channels, restore the inoperable channel to OPERABLE status within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.

i l

l l

l DAVIS-BESSE. UNIT 1 3/4 3-27 Amendment No. 37

(

L

TABLE 3.3-12 g

STEAM AND FEEDWATER RUPTURE CONTROL SYSTLM g

INstkliRWTATIW1RlliTGFDlRis_

4, y......

TRIP $tTPOINTS_

ALLOWAnLE VALUES m

• FUNCTIONAL UNITS _

y 1.

Steam Line Pressure - Low

> 591.6 psig 1 591.6 psig*

E

> 586.6 psig**

2.

Steam Generator level - Low 1 20" !! 0 1 20" H 0*

kN 2

2 1 18.87 11 0**

2 3.

Steam Generator Feedwater I2)

< 197.6 psid

< 197.6 psida Differential Pressure - High 5199.6 psid"

< 1384.6 amps #

4.

Reactor Coolant Pumps - Loss of High < 1384.6 amps Low [ 106.5 amps E106.5ampsf g

Y U

IIIMeasured above the lower steam generator tubesheet.

IIIWhere differential pressure is steam generator minus feedwater pressure.

• llowable Value for CilANNEL FUNCil0NAL TEST A

" Allowable Value for CilANNEL CAllBRATION I

Allowable Value for CllANNEL FUNCTIONAL TEST and CilANNEL CALIBRATION f+

if 4u

s TABLE 3.3-10 3$

POST-ACCIDENT 110NITORING lilSTRUMENTATION Y$

MINIMUM

!?,

CHANNELS INSTRUMENT, OPERABLE 1.

SG Outlet Stear Pressure 1/ Steam Generator

-4 2.

RC Loop Outlet Temperature 2/ Loop 3.

RC Loop Pressure 2/ Loop l

4.

Pressurizer Level 2

f 5.

SG Startup Range Level 2/ Steam Generator 6.

' Auxiliary Feedwater Status 1/AFW System 7.

Containment Vessel llydrogen 2

y 8.

Containment Vessel Post-Accident Radiation 2

9.

Containment Vessel Isolation Status 1/ Valve 10.

SFAS Status 1/ Channel

11. Safety Features Equipment Status 1/ System

12. RPS Status 1/ Channel

13. SFRCS Status 1/ Channel

14. High Pressure Injection Flow 1/ Channel

E5'fM g

TABLE 3._3-10(Continuedj.

POST-ACCIDEllT MONITORiflG IflSTRUMENTATION c&

H HINIMUM CitANNELS INSTRlMENT

_Ol'ERABLE

15. Low Pre m.- injection (DilR) Flow 1/ Channel

16. HPI System Pump and Valve Status 1/ System

17. LPI System Pump and Valve Status 1/ System

18. Containment Spray Pump and Valve Status 1/ System

~

19. Core Flood Valve Status 1/ System

20. BWST Valve Status 1/ System

21. Contain.nent Emergency Sump Valve Status 1/ Valve

22. Containment Air Recirculation Fan Status 1/ Fan

23. Containment Air Cooling Far : Status 1/ Fan

24. EVS Fan and Damper Status 1/ System f

25. Auxiliary Feedwater Flow Rate 1/ Steam Generator l

26. RC System Subcooling Margin Honitor j

[

27. PORV position Indicator j

o

28. PORV Block Valve Position Indicator j

y

29. Sc.Nty Valve Position Indicator s

1/ Valve

30. BWST Level 3

i et-

TABLE 4.3-10_

POST-ACCIDENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS G

CllANNEL CHANNEL E.

INSTRUMENT CllECK CALIBRATION Q

i y

1.

SG Outlet Steam Pressure M

R E

2.

RC Loop Outlet Temperature M

R 3.

RC Loop Pressure M

R 4.

Pressurizer Level M

R 5.

SG Startup Range Level M

R 6.

Auxiliary Feed.4ater Status M

HA 7.

Containment Vessel Hydrogen M

R 8.

Containment Vessel Post-Accident Radiation M

R 3

9.

Containment Vessel Isolation Status M

NA

10. SFAS Status M

NA

11. Safety Features Equipment Status M

NA

12. RPS Status M

NA

13. SFRCS Status M

NA

14. liigh Pressure Injection Flow M

R

TABLE 4.3-10 (Continued)

POST-ACCIDENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS G

CHANNEL CilANNEL INSTRUMENT CHECK CALIBRATION M

15. Low Pressure Injection (DHR) Flow M

R

16. HP1 System Pump and Valve Status M

NA

17. LPI System Pump and Valle Status M

NA

18. Containment Spr, Pump and Valve Status M

NA

19. Core Flood Valve Status M

NA

20. BWST Valve Status M

NA

21. Containment Emerger.cy Sump Valve Status M

NA

22. Containment Air Recirculation Fan Status M

NA Y8

23. Containment Air Cooling fan Status-M NA i

24. EVS Fan and Damper Status M

NA 25 Auxiliary Fee &ater Flcw Rate il R

26. RC System Subcooling Margin Ibnitor M

R

27. PORV Position Indicator 11 R

g

28. PORV Block Valve Position Indicator R

f

29. Pressurizer Safety Valve Position Indicator M

R 5

30. BWST Level 5

R E

e

i i

es 3:

![g s

r-II I!

a.I x-Mr g

55b.

.s u

sl e

c' g*

de 2:f

E' 5

-s f g!

If X:;

Eg a-l=

3 g

l=

-g

_1 35 ii

!i d_lsg lg l'g e

4 i

8:

i

s s

r ta I!

,I

=j g

s e

e l

l I

I-I y!

?

v:5!

.a 1

n

! =r l

8 iti 3 [!

_id!

i!

n

=

l 1

g:l Is II U

gi

'I t

s

!=

I

a i

-i g:r

l" is 1:

g

-i 5

1 a

a a

a a

a 3

-g g

o e

az DAVIS-BESSE, UNIT 1 6-3 Amendment No.12 I

l

-=n e

- ' ~ '

I TABLE 6.2-1 MINIML'M SHIFT CREW CCMPOSITION#

1 l

LICENSE APPLICABLE MOCES CATEGORY 1, 2, 3 & 4 5&6 50L 1

1*

OL 2

1 Non-Licensed 2

1 Shift Technical Advisor 1

None Required

• 0ces not include the licensed Senior Reactor Operator or Senior Reactor Operator Limited to Fuel Handling supervising CORE ALTERATIONS.

l

1. Shift crew composition may be less than the minimum requirements for j

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 accommcdate unexpectt-d absence of on duty shift crew memoers provided immediate action is taken to restore the shift crew composition to within the minimum requirements of Table 6.2-1.

DAVIS-BESSE, UNIT 1 64 Amendment No. 37 er up n

a

~w

• wh

-r w

+<-e-e

+m+

---

rw e

3 e

-v

-t+-

m

'wt

---e

ACMINISTRATIVE CCNTROLS 6.3 FACILITY STAFF OUALIFICATIONS I

j 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) l the (Radiation Protection Manager) who shall meet or exceed the quali-fications of Regulatory Guide 1.8, September 1975 and (2) the Shift Tech-l nical Advisor who shall have a bachelor's degree or equivalent in a scientific or engineering discipline with specific training in plant 4 design, and response and analysis of the plant for transients and acci-

j den ts.

6.4 TRAINING 6.4.1 A retraining and repircement training program for the facility staff shall be maintained under the direction of the (position title) and shall meet or exceed the requirements and reconnendations 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 Fire Marshall and shall meet or exceed the

!quirements of Section 27 of the NFPA Code-1976.

6.5 REVIEW AND AUDIT 6.5.1 STATION REVIEW SOARD (SRS)

FUNCTION 6.5.1.1 The Station Review Board (SRS) shall function to advise the Station Superintendent on all matters related to nuclear safety.

0 AVIS-BESSE, UNIT 1 6-5 Amendment No.JI 37

ADMINISTRAi!VF CONTROLS COMPOSITION 6.5.1.2 The Station Review Board shall be composed

.f the:

Chairman:

Assistant Station Si rintendent i

Member:

Operations Engineer Me?.ber:

Technical Engineer

&mber:

Maintenance Engineer-Mamber:

Lead Instrument and Centrol Ergineer i

Member:

Nuclear anc Perfomance Engineer Member:

Chemist and Health Physicist Member:.

Reliability Engineer Member:

Station Superintendent i

ALTERNATES 6.5.1.3 All alternate members shall be appointed in writing by the SRB Chaiman to serve on a temporary basis; hcwever, ne mere than tno alternates shall participate as voting members in SRS activities at any one time.

MEETING FREQUENCY 6.5.1.4 The SRS shall meet at least once per calendar month and as convened by the SRS Chaiman or his designated alternate.

CUORUM 6.5.1.5 A quorum of the SRB sha consist of the Chaiman or his designated alternate and four mer..ers including alternates.

RESPONSIBILITIES 6.5.1.6 The Station Review Board shall be responsible for:

Review of 11 all procedures required by Specification 6.8 and a.

changes thereto, 2) any other proposed procedures or changes thereto as dete nined by the Station Superintendent to affect nuclear safety.

b.

Review of all proposed tests and experiments that affect nuclear safety.

DAVIS-BESSE, UNIT 1 6-6 Amendment No. 12