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Proposed Tech Specs 1.2,3.3-3,3.3-11,4.3-2,3.3-10,4.3-10, 3.4.11,6.3 - 6.5,6.2-1,3/4.4.4,3/4.4.5,3/4.4.10 & 3.4.4.11 Re Safety Features Actuation Sys Instrumentation.Made in Response to TMI Lessons Learned,Category a Requirements
	ML19338D314
Person / Time
Site:	Davis Besse
Issue date:	09/16/1980
From:	; TOLEDO EDISON CO.
To:	;
Shared Package
ML19338D309	List: ML19338D308; ML19338D311; ML19338D314;
References
	TAC-42596, NUDOCS 8009220313
	Download: ML19338D314 (14)
	v • d • e

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T_ABLE 1.2 FREQUEf4CY fl0 TAT 10fi NOTAT10:1 FREQUEfiCY S At least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

D At least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

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.

R At least once per 18 months.

S/U Prior to each reactor startup.

N.A. flot applicable.

W [n fhes c. 7e~ e L n ica l Syecificats' ens.,

is de (cu e d to be I@'I days, (o w o n +k s !

months is deIns ed to be 55 0 and (8 C. A I, ,

ll 1

DAVIS-BESSE, UNIT 1 1-8 l

8009220 3 i 3 i

sg TABLE 3.3-3

@ SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION

$; MINIMUM r" UNITS APPLICABLE

. TOTAL N0. UNITS c: FUNCTIONAL UNIT OF UNITS TO TRIP OPERABLE MODES ACTION

.5

1. INSTRUMENT STRINGS g

] b ,, ,

a. Containment Radiation - I) 2> 32 s High 4 2 3 All ".CDE5 9#

b. Containment Pressure -

High 4 2 3 1,2,3 9#

c. Containment Pressure -

High-High 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#

f. BWST Level - Low 4 2 3 1, 2, 3 9#

5{

y 2. OUTPUT LOGIC E; a. Incident Level #1:

/>2/s3sbII*33,,

Containment Isolation 2 1 2 Al' ~.UDE5- 10

b. Incident Level #2:

High Pressure Injection and Starting Diesel Generators 2 1 2 1,2,3,4 10

c. Incident Level #3:

Low Pressure Injection 2 1 2 1,2,3,4 10

d. Incident Level #4:

. Containment Spray 2 1 2 1,2,3,4 10

e. Incident Level #5:

Containment Sump Recirculation 2 1 2 1,2,3,4 10

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TABLE 3.3-3

! B -

5 SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION f

% MINIMUM p, TOTAL NO. UNITS UNITS APPLICABLE m FUNCTIONAL UNIT OF UNITS TO TRIP OPERABLE MODES ACTION C

= 3. MANUAL ACTUATION g, y

a. SFAS (except Containment b) >>

Spray and Emergency Sump 2 2 2 au A007.- 11 Reci rcula tion)

b. Containment Spray 2 2 2 1,2,3,4 11

4. SEQUENCE LOGIC CHANNELS 4 2*** 4 1,2,3,4 9#

5. INTERLOCK CHANNELS

a. Decay Heat Isolation Valve 1 1 1 1, 2, 3, 4 5 12#

U b. Pressurizer Heaters 2 2 2 3,4,5 13# I i

Y g -

R 3

o O

)

TABLE 3.3-3 (Continued)

TABLE NOTATION o Trip function may be bypassed in this MODE with RCS pressure below 1800 psig. Bypass shall be aut omatically renoved when RCS pressure exceeds 1800 psig.

- Trip function may be bypassed in this MODE wi*h RCS pressure below 600 psig. Bypass shall be automatically removed when RCS pressure exceeds 600 psig.

- - One must be in SFAS Channels #1 vr #3, the other must be in Channels

2 or #4.

- - - This instrumentation must be OPERABLE during core alterations or movement af irradiated fuel within the containment to meet the requirements of Tech. Spec. 3.9.4.

The provisions of Specification 3.0.4 are not applicable.

ACTION STATEMENTS ACTION 9 - With the number of OPERABLE functional units one less than the Total Number of Units, startup and/or power operation may proceed l provided both of the following conditions are satisfied:

a. The inoperable functional unit is placed in the tripped condition within one hour,

b. The Minimum Units OPERABLE requirement is met; however, one additional functional unit may be bypassed for up to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months for surveillance testing per Specification 4.3.2.1.1.

ACTION 10 - With any component in the Output Logic inoperable, trip the associated components within one hour or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

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 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months !

and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

ACTION 12 - a. With less than the Minimum Units OPERABLE cad reactor coolant pressure 1438 psig, both Decay Heat Isolation Valves (DHil and DH12) shall be verified closed.

b. With less than the Mininum Units OPERABLE and reactor coolant pressure <438 psig operation may continue; however, the functional unit shall be OPERABLE prior to increasing reactor coolant pressure above 438 psig.

ACTION 13 - With less than the Minimum Units OPERABLE and reactor coolant pressure

< 438 psig, operation,may continue; however, the functional unit shall be OPERABLE prior to increasing reactor coolant pressute 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. 28

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/ TABLE 3.3-11 (Continued)

TABLE NOTATION

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

The provisions of Specification 3.0.4 are not applicable.

ACTION STATEMENTS s fet up M YO Y f * *' k ACTION 13 - With the number of OPERABLF Channels one less than the Total Number of Channels, operation may proceed until performance of the next required CHANNEL FUNCTIONAL TEST provided the inoperable section of the channel is placed in the tripped condition within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months .

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

DAVIS-BESSE, UNIT 1 3/4 3-27

[ TABLE 4.3-2 SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION SURVEILLANCE REQUIREMENTS CHANNEL MODES IN WHICli CHANNEL CHANNEL FUNCTIONAL SURVEILLANCE FUNCTIONAL UNIT CHECK CALIBRATION TEST REQUIRED

[ 1. INSTRUMENT STRINGS .

a. Coritainment Radiation - High S R M M ' "*S

b. Containment Pressure - High S R M(2). 1, 2, 3

c. Containment Pressure - High-High S R M(2) 1, 2, 3

d. RCS Pressure - Low S R M 1,2,3

c. RCS Pressure - Low-low 5 R M 1,2,3

f. BWST Level - Low S R M 1, 2, 3

2. OUTPUT LOGIC

a. Incident Level #1: Con ta inmen t 6 %s 3; Y; b M isolation S R M *'F. ",30 3

b. Incident Level #2: High Pressure Y Injection and Starting Diesel S Generators S R M 1,2,3,4

c. Incident Level #3: Low Pressure Injection S R M 1, 2, 3, 4

d. Incident Level #4: Containment Spray S R M 1, 2, 3, 4

e. Incident Level #5: Con tainment '

Sump Recirculation S R M 1, 2, 3, 4

3. MANUAL ACTUATION 4 4 3, V, G#

a. SFAS (Except Containment Spray NA NA M(1) . 'nES and Emergency Sump Recirculation)

b. Containment Spray NA NA M(1) 1, 2, 3 4 SEQUENCE LOGIC CIIANNELS S NA M 1, 2, 3, 4

N s

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9 TABLE 4.3-2 SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION SURVEILLANCE REQUIREMENTS CHANNEL MODES IN WHICH T CHANNEL FUNCTIONAL SURVEILLANCE CHANNEL E CALIBRATION TEST REQUIRED CHECK

$ FUNCTIONAL UNIT T

c: 5. INTERLOCK CHANNELS 5 R

- 1,2,3,4,5

a. Decay Heat Isolation Valve S

] R

- 3,4,5 S

b. Pressurizer Heater

- See Speci fica tion 4.5.2.d.1 TABLE NOTATION M

a 4'

% (1) Manual actuation switches shall be tested at least once per 18 months during shutdown. All other circuitry associated with manual safeguards actuation shall receive a CHANNEL FUNCTIONAL TEST at least once per 31 days.

[2 (2) The CHANNEL FUNCTIONAL TEST shall include exercising the transmitter by applying either vacuum or h pressure to the appropriate side of the transmitter.

Sedi*h Yo 9' 'I ay/y durihf f'N l

0 $ 7%e surveilloe e reyaitem*><fs oI

" core aher aJrons or n, ove m e a t of irr a dia Fe d fa e / wWr in 2 the c o n + a is m en t.

"C.

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T ia n

P c TABLE 3.3-10 (continued)

[j POST-ACCIDENT MONITORING INSTRUMENTATION INSTRUMENT MINIMUM CIIANNELS OPERABLE

25. Auxiliary Feedwater Flow Rate 1 per steam generator

26. Reactor Coolant System Subcooling Margin Monitor 1

27. PORV Position Indicator 1

28. PORV Block Valve Position Indicator 1 hh 29. Safety Valve Position Indicator 1/ valve Y

b; u

G

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TABLE 4.3-10 (continued) p POST-ACCIDENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS a CHANNEL CIIANNEL p INSTRUMENT CHECK CALIBRATION

25. Auxiliary Feedwater Flow Rate M R h 26. Reactor Coolant System Subcooling Margin Monitor M R H

- 27. PORV Position Indicator M R

28. PORV Hlock Valve Position Indicator M R

29. Pressurizer Safety Valve Position Indicator M R R

e 5

u i

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REAC IOR, COO!ATT, SYSI Ey RELIEF VALVE _,_0P,ERATING_

LDillING CONDITION FOR OPERATION 3.4.11 The power operated relief valve (PORV) and its associated block valves shall be OPERABLE.

APPLICABILITY: MODES 1,2, and 3.

ACTION:

a. With the PORV inoperable, within I hour either restore the PORV to OPERABLE status or close the associated block valve and remove power from the block valve; otherwise, be in at lecst HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months ,

b. With the block valve inoperable, within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months either restore the b'ock valve to OPERABLE status or close the block valve and remove power from the block valve; otherwise, be in at least H01 STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

SURVEILLANCE RFi_qu1REMENTS 4.4.11.1 The PORV shall be demonstrated OPERABLE at least once per 18 months by performance of a CHANNEL CALIBRATION.

4.4.11.2 The block valve shall be demonstrated OPERABLE at least once per 92 days by operating the valve through one complete cycle of full travel.

DAVIS-BESSE, UNIT 1 3/4 4-32

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. I ADMitil57PATIVE C0!iTROL5 6.3 FACILITY STAFF QUAllFICATIONS 6.3.1 Each member of the facility forstaff shall meet or exceed the minimum comparable positions, except for (i) qualifications of ANSI N18.1-1971 l the (Radiation Protection Manager) who shall meet of exceed the quali-fications of Regulatory Guide 1.8, September 1975f A l 6.4 TRAINit1G 6.4.1 A retraining and replacement . raining program for the facility staff shall be maintained under the direction of the (position title) and shall meet or exceed the requirements and recomendations 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 Bridage shall be maintained under the direction of the Fire Marshall and shall meet or exceed the requirements of Section 27 of the NFPA Code-1976.

l 6.5 REVIEW AND AUDIT 6.5.1 STATION REVIEW BOARD (SRB)

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

wie skn 7 fand (p + te SWt Te ch nica l A d viss e kave a. b uh e lo r 's deye< oe epv a lent-511 A SCick$ibit OY di} ihet Y ikj C. i$ C if l5s -c win specike frauy in plad desip,\

G d rcJp0hSc d.n d 4 h 4. [y S if o[ ISC for +ra n synis and a cc ide ds p fant C _

OAV15-BESSE, UNIT 1 6-5 k end ,ent No. 9

" TABLE 6.2-1 MINIMUM SHIFT CREW COMPOSITION #

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

OL 2 1 2 1 Non-Licensed Shift Tukul Abu" i Nne reyind

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

Shift crew composition may be less than the minimum requirements for a period of time not to exceed 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months in order to accommodate unexpected absence of on duty shift crew members provided immediate action is taken to restore the shift crew composition to within the minimum requirements of Table 6.2-1.

l DAVIS-BESSE, UNIT 1 6-4

R_EACTOR COOLANT SYSTEM BASES 3/4.4.4 PRESSURIZER A steam bubble in the pressurizer ensures that the RCS is not a hydraulically solid system and is capable of accomodating pressure surges during operation. The steam bubble also protects the pressurizer code safety valves and power operated relief valves against water relief.

The low level limit is based on providing enough water volume to prevent a reactor coolant system low pressure condition that would actuate the Reactor Protection System or the Safety Featura Actuation System. The high level limit is based'on providing enough steem volume to prevent a pressurizer h.ich level as a result of any transient.

ower ope ted relie alves a le fun to )

f Th RCS relie pre ure durin 11 dest steam transien s. Oper on of the I

po r operat relief v ses minim' es the estrabl penin j .; ring-loatd oressu ~ er code fety v s.

3/4.4.5 STEAM GENERATORS _ DELETE The Surveillance Requirements for inspection of the steam generator tubes ensure that the structural integrity of this portion of the RCS will be maintained. The program for inservice inspection of steam generator tubes is based on a modification of Regulatory Guide 1.83, Revision 1. i Inservice inspection of steam generator tubing is essential in order to maintain surveillance of the conditions of the tubes'in the event that there is evidence of mechanical damage or progressive degradation due to design, manufacturing errors, or inservice conditions that lead to l corrosion. Inservice inspection of steam generator tubing also provides a means of characterizing the nature and cause of any tube degradation so that corrective measures can be taken.

The plant is expected to be operated in a manner such that the secondary coolant will be maintained within those chemistry limits found to result in negligible corrosion of the steam generator tubes. If the secondary coolant chemistry is not maintained within these chemistry i limits, localized corrosion may likely result in stress corrosion cracking.

The extent of crack:ng during p'. ant operation would be limited by the limitation of steam generator tube leakaa systemandthesecondarycoolantsystem{ebetweentheprimarycoolantprim Cracks having a primary-to-secondary leakage less than this limit during operation will have an adequate margin of safety to withstand the loads 1

DAVIS-BESSE, UNIT 1 B 3/4 4-2

REACTOR COOLANT SYSTEM BASES 3/4.4.10 STRUCTURAL INTEGRITY The inspection programs for ASME Code Class 1, 2 and 3 components, except steam generator tubes, ensure that the structural integrity of these components will be maintained at an acceptable level throughout the life of the plant. To the extent applicable, the inspection program for these components is in compliance with Section XI of the ASME Boiler and Pressure Vessel Code.

The internals vent valves are provided to relieve the pressure generated by steaming in the core following a LOCA so that the core remains sufficiently covered. Inspection and manual actuation of the interne.ls vent valves 1) ensure OPERABILITY, 2) ensure that the valves are not stuck open during normal operation, and 3) demonstrates that the valves are fully open at the forces equivalent to the differential pressures assumed in the safety analysis. .

3/4.4.11 RELIEF VALVE The power operated relief valve (PORV) operates to relieve RCS pressure below the setting of the pressurizer code safety valves. This relief valve has a remotely operated block valve to provide a positive shutoff capability should the relief valve become inoperable. The electrical power for both the relief valve and the block valve is supplied from an essential power source to ensure the ability to seal this possible RCS leakage path.

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DAVIS-BESSE, UNIT 1 B 3/4 4-13

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ML19338D314

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