Text

Amends 55 & 54 to Licenses DPR-80 & DPR-82,respectively, Changing Tech Spec Sections 3.0.4,4.0.3 & 4.0.4 & Associated Bases to Define Applicability of Limiting Conditions for Operation & Surveillance Requirements
	ML20043G826
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Site:	Diablo Canyon
Issue date:	06/11/1990
From:	Larkins J; Office of Nuclear Reactor Regulation
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ML20043G827	List: ML20043G826; ML20043G835;
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h UNITED STATES 7

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NUCLEAR REGULATORY COMMISSION g

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WASHINGT ON, D. C. 20555 4

PACIFIC GAS AND ELECTRIC COMPANY o

4 DIABLO CANYON NUCLEAR POWER PLANT, UNIT 1 i

DOCKET NO. 50-275 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 55 License No. DPR-80 1.

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

A.

The application for amendment by Pacific Gas & Electric Company (the licensee), dated April 18, 1988, as supplemented by letter dated December 21,1989, complies with the standards and requirementsoftheAtomicEnergyActof1954,asamended(the Act). and the Comission's regulations set forth in 10 CFR Chapter I; B.

The facility will operate in conformity with the ap)1ication, the provisions of the Act, and the regulations of t1e Comission; 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 Comission's regulations; D.

The issuance of this amendment will not be inimical to the common i

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 Comission's regulations and all applicable requirements have been satisfied.

9 i

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.i 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-80 is hereby amended to read as follows:

(2) Technical Specifications The Technical Specifications contained in Appendix A and the Environmental Protection Plan contained in Appendix B, as revised through Amendment No. 55, are hereby incorporated in the license.

Pacific Gas & Electric Company shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan, except where otherwise stated in specific license conditions.

3.

This license amendment becomes effective at the date of its issuance.

FOR THE NUCLEAR REGULATORY COMMISSION John T. Larkins, Acting Director Project Directorate V Division of Reactor Projects - III, IV, V and Special Projects Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical Specifications-Date of-Issuance: June 11, 1990

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NUCLEAR REGULATORY COMMISSION WASHINGT ON, D. C. 20555 e

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PACIFIC GAS AND ELECTRIC COMPANY DIABLO CANYON NUCLEAR POWER PLANT. UNIT 2 DOCKET NO. 50-323 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 54 slicense No. DPR-82 1.

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

A.

The application for amendment by Pacific Gas & Electric Company (thelicensee),datedApril 18, 1988, as supplemented by letter dated December 21, 1989, co.nplies with the standards and requirementsofthe.AtomicEnergyActof1954,asamended(the Act), and the Comission's regulations set forth in 10 CFR Chapter I;'

B..

The fa'cility will operate in conformity with the application, the provisions of the Act, and the 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 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 CFR Part 51 of the Comission'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 l

amendment,andparagraph2.C.(2)ofFacilityOperatingLicense No. DPR-82 is hereby amended to read as follows:

1 (2) Technical Specifications The Technical Specifications contained in Appendix A and the Environmental Protection Plan contained in Appendix B, as revised through Amendment No. 54, are hereby incorporated in the license.

Pacific Gas & Electric Company shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan, except where otherwise stated in specific license conditions.

3.

This license amendment becomes effective at the date of its issuance.

FOR THE NUCLEAR REGULATORY COMMISSION A

John T. Larkins, Acting Director Project Directorate V Division of Reactor Projects - III, L

IV, Y and Special Projects L

Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical Specifications Date of Issuance: June 11, 1990 t

L 1 :.

1

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ATTACHMENT TO LICENSE AMENDMENT NOS. 55 AND 54 FACILITY OPERATING LICENSE NOS. DPR-80 and DPR-82 DOCKET NOS. 50-275 AND 50-323 Replace the following ) ages of the Appendix "A" Technical Specifications with the attached pages. T1e revised pages are identified by amendment number and contain vertical lines indicating the areas of change. Overleaf pages are also included.

Remove Page-Insert Page 3/4 0-1 3/4 0-1 3/4 0-2 3/4 0-2 3/4 3-2 3/4 3-2 3/4 3-3 3/4 3-3 3/4.3-4 3/4 3-4 3/4 3-15 3/4 3-15 3/4 3-17 3/4 3-17 3/4 3-18 3/4 3-18 3/4 3-19 3/4 3-19 3/4 3-21 3/4 3-21 3/4 3-36 3/4 3-36 3/4 3-38 3/4 3-38 3/4 3-40 3/4 3-40 3/4 3-41 3/4 3-41 3/4 3-44 3/4 3-44 3/4 3-54 3/4 3-54 3/4 3-55 3/4 3-55 3/4 3-59 3/4 3-59 3/4 3-64 3/4 3 3/4 4-35 3/4 4-35 3/4 4-37 3/4 4-37 3/4 7-24 3/4 7-24 3/4 7-26 3/4 7-26 3/4 7-28 3/4 7-28 3/4 7-30 3/4 7-30 3/4 7-32 3/4 7-32 3/4 7-33 3/4 7-33 3/4 7-36 3/4 7-36 3/4 7-40 3/4 7-40 3/4 8-23 3/4'8-23 3/4 9-7 3/4 9-7 3/4 9-10 3/4 9-10 3/4 9-12 3/4 9-12 3/4 9-13 3/4 9-13

ATTACHMENT TO LICENSE AMENDMENT NOS. 55 AND 54 (CONTINUED)

FACILITY OPERATING LICENSE NOS. DPR-80 and DPR-82 DOCKET NOS. 50-275 AND 50-323 i

Replace the following pages of the Appendix "A" Technical Specifications with the attached pages.

T1e revised pages are identified b contain vertical lines indicating the areas of change. y amendment number and Overleaf pages are also included.

Remove Page

_ Insert Page 3/4 11-5 3/4 11-5 3/4 11-6 3/4 11-6 3/4 11-7 3/4 11-7 3/4 11-12 3/4 11-12 3/4 11-13 3/4 11-13 3/4 11-14 3/4 11-14 3/4 11-15 3/4 11-15 3/4 11-16 3/4 11-16 3/4 11-17 3/4 11-17 3/4 11-18 3/4 11-18 3/4 12-2 3/4 12-2 3/4 12-12 3/4 12-12 3/4 12-13 3/4 12-13 B 3/4 0-1 8 3/4 0-1 B 3/4 0-la B 3/4 0-1b B 3/4 0-2 B 3/4 0-2 B 3/4 0-2a B 3/4 0-3 B 3/4 0-3 L

3/4. LINITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS

,r 3/4.0 APPLICABILITY' LIMITING CONDITION FOR OPERATION 3.0.1 Compliance with the Limiting Conditions for Operation contained in the succeeding specifications is required during the OPERATIONAL ICDES or other conditions specified therein; except that upon failure to meet the Limiting Conditions for Operation, the associated ACTION requirements shall be est.

3.0.2 Noncompliance with a specification shall exist when the requirements of the Limiting Condition for Operation and associated ACTION requirements are not est within the specified time intervals.

If the Limiting Condition for Operation is restored prior to expiration of the specified time intervals, completion of the ACTION requirements is not required.

3.0.3 When a Limiting Condition for Operation is not set, except as provided i

in the associated ACTION requirements, within I hour action shall be initiated to place the unit in a MODE in which the specification does not apply by placing it, as applicable, in:

'a.

At least HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months , b.

At least HOT SHUTDOWN within the following 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months , and c.

At least COLD SHUTDOWN within the subsequent 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

Where corrective measures.are completed that persit operation under the ACTION requirements, the action may be taken in accordance with the specified time limits as measured from the time of failure to meet the Limiting Condition for Operation.

Exceptions of these requirements are stated in the individual specifications.

This specification is not applicable in MODE 5 or 6.

3.0.4 Entry into an OPERATIONAL MODE or other specified condition shall not be made when the conditions for the Limiting Conditions for Operation are not met and the associated ACTION requires a shutdown if they are not met within a specified time interval.

Entry into an OPERATIONAL MODE or specified condition may be made in accordance with ACTION requirements when conformance to then

' permits continued operation of the facility. for an unlimited period of time.

This provision shall not prevent passage through or to OPERATIONAL MODES as required to comply with ACTION statements.

Exceptions to these requirements are stated in the individual specifications.

3.0.5 Limiting Conditions for Operation including the associated ACTION re-quirements shall apply to each unit individually unless otherwise indicated as follows:

a.

Whenever the Limiting Conditions for Operation refers to systems or components which are shared by both units, the ACTION requirements will apply to both units simultaneously. This will be indicated in the ACTION section; b.

Whenever the Limiting Conditions for Operation applies to only one unit, this will be identified in the APPLICABILITY section of the specification; and c.

Whenever certain portions of a specification contain operating param-eters, Setpoints, etc., which are different for each unit, this will be identified in parentheses, footnotes or body of the requirement.

DIABLO CANYON - UNITS 1 & 2 3/4 0-1 Amendment Nos. 55 and 54

- - ~ - - - -

APPLICABILITY-SURVEILLANCE-REQUIREMENTS 4.0.1 Surveillance Requirements shall be met during the OPERATIONAL MODES or other conditions specified for individual Limiting Conditions for Operation unless otherwise stated in an individual Surveillance Requirement.

4.0.2 Each Surveillance Requirement shall be performed within the specified time interval with:

a.

A maximum allowable extension not to exceed 25% of the surveillance interval, but b.

The combined time interval for any 3 consecutive surveillance. intervals shall not exceed 3,25 times the specified surveillance interval.

4.0.3 Failure to perform a Surveillance Requirement within the allowed surveillance interval defined bj Specification 4.0.2 shall constitute non:ompliance with the OPERABILITY requirements for a Limiting Condition for Operation. The time limits of the ACTION requirements are applicable at the time it is identified that a Surveillance Requirement has not been performed.

The ACTION requirements may be delayed for up to 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months to permit the completion of the surveillance when the allowable outage time limits of the ACTION requirements are less thin 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

Exceptions to these requirements are stated in the individual specifications.

Surveillance Requirements do not have to be performed on inoperable equipment.

4.0.4 Entry into an OPERATIONAL MODE or other specified condition shall not be made unless the Surveillance Requirement (s) associaf.ed with the Limiting Condition for Operation has been performed within the stated surveillance interval or as otherwise specified. This provision st.all not prevent passage through or to OPERATIONAL MODES as required to comply with ACTION requirements.

4.0.5 Surveillance Requirements for inservice insrection and testing of ASME l-Code Class.1, 2 and 3 components shall be applicable as follows:

Inservice.inspectionofASMEkodeClass1,2and3componentsand a.

inservice testing of ASME Code Class 1, 2 and 3 pumps and valves shall be performed in accordance with Section XI of the ASME Boiler and Pres-sure Vessel Code and applicable Addenda as required by 10 CFR 50, Sec-t i

tion 50.55a(g), except where specific written relief has been granted by the Commission pursuant to 10 CFR'50, Section 50.55a(g)(6)(1);

b.

Surveillance intervals specified in Section XI of the ASME Boiler and Pressure Vessel Code and applicable Addenda for the inservice inspection and testing activities required by the ASME Boiler and Pressure Vessel Code and applicable Addenda shall be applicable as follows in these Technical Specifications:

ASME BOILER AND PRESSURE VESSEL REQUIRED FREQUENCIES FOR CODE AND APPLICABLE ADDENDA PERFORMING INSERVICE L

TERMIN0 LOGY FOR INSERVICE INSPECTION AND TESTING l

INSPECTION AND TESTING ACTIVITIES ACTIVITIES Weekly At least once per 7 days Monthly At least once per 31 days Quarterly or every 3 months At least once per 92 days Semiannually or every 6 months At least once per 184 days Every 9 months At least once per 276 days Yearly or annually At least once per 366 days DIABLO CANYON - UNITS 1 & 2 3/4 0-2 Amendment Nos. 55 and 54 L

o m

m a

^

l o

TABLE 3.3-1 h

l

. REACTOR TRIP SYSTEM INSTRUMENTATION l~

l' 9

MINIMUM t

i.

5 TOTAL NO.

CHANNELS CHANNELS APPLICABLE i

@ FUNCTIONAL UNIT OF CHANNELS TO TRIP OPERABLE MDDES ACTION c

1.

Manual Reactor Trip 2

1 2

1, 2 1

5 2

1 2

3*, 4*, 5*

11 l

d s

2.

Power Range, Neutron Flux o.

a.

High Setpoint 4

2 3

1, 2 2

to b.

Low Setpoint 4

2 3

I W,2 2

3.

Power Range, Neutron Flux 4

2 3

1, 2 2

High Positive Rate R

4.

Power Range, Neutron Flux 4

2 3

1, 2 2

High Negative Rate i

T 5.

Intermediate Range, Neutron Flux 2

1 2

IW,2 3

6.

Source Range, Neutron Flux a.

Startup 2

1 2

2N 4

b.

Shutdown 2

1-2 3*, 4*, 5*

11 c.

Shutdown 2

0 1

3, 4, and 5 5

I F

7.

Overtemperature AT 4

2 3

1, 2 6

i E

8.

Overpower AT 4

2 3

1, 2 6

)

I 9.

Pressurizer Pressure-Low 4

2.

3 1

6 o

P 10.

Pressurizer Pressure-High 4

2 3

1, 2 6

m g

Pressurizer Water Level-High 3

2 2

1 6

11.

O

,_.s

I V

TABLE 3.3-1 (Continued) o

. REACTOR TRIP SYSTEM INSTRUNENTATION 9

5

. MINIMUM g

TOTAL NO.

CHANNELS CHANNELS

~ APPLICABLE FUNCTIONAL UNIT DF CHANNELS TO TRIP OPERABLE MODES ACTION 12.

Reactor Coolant Flow-Low N

a.

Single Loop 3/ loop 2/ loop'in 2/ loop in 1

6 (Above P-8) one loop each loop e

b.

Two Loops 3/ loop 2/ loop in 2/ loop in 1

6 m

(Above P-7 and below P-8) two loops each loop

13. Steam Generator Water 3/S.G.

2/S.G. in 2/S.G. in 1, 2 6(1)

Level-Low-Low one S.G.

each S.G.

R* 14. Steam Generator Water Level-Low 2 S.G. level 1 S.G. level 1 S.G. level 1, 2 6

y Coincident With and coincident with and Steam /Feedwater Flow 2 sta./ feed 1 sta./ feed 2 sta./ feed w

Mismatch flow flow flow mismatch, mismatch mismatch in or per S.G.

same S.G.

2 S.G. level and y

1 sta./ feed 8

flee mismatch per S.G.

m

15. Undervoltage-Reactor Coolant 2/ bus 1/ bus 1/ bus 1

6(1) l 5

5 Pumps both busses

?

16. Underfrequency-Reactor Coolant 3/ bus 2 on same bus 2/ bus 1

6 u,

Pumps

." 17. Turbine Trip T

a.

Low Autostop 011 Pressure 3

2 2

1 7

b.

Turbine Stop Valve Closure 4

4 4

O 9.

6' e

. TABLE 3.3-1 (Continued) g g

REACTOR TRIP SYSTEM INSTRUMENTATION t,

9 MININUM 5

TOTAL NO.

CHANNELS CHANNELS APPLICABLE

@ FUNCTIONAL UNIT OF CHANNELS TO TRIP OPERABLE MDDES ACTION e

c 18.

Safety Injection Input 5

from ESF.

2 1

2 1, 2 10 1

v 19.

Reactor Coolant Pump Breaker-l g

l a.

Position Trip above P-7 1/ breaker 2

1/ breaker 1

9 I

y i

j 20.

Reactor Trip Breakers 2

1 2

1, 2 10, 12 2

1 2

3*, 4*, 5*

11 l

21. Automatic Trip and Interlock 2

1 2

1, 2 10 i

l R

Logic 2

1 2

3*, 4*, 5*

11

{ 22.

Reactor Trip System Interlocks a.

-Intermediate Range Neutron Flux, P-6 2

1 2

2N 8

I 1

l b.

Low Power Reactor Trips Block, P-7 P-10 Input-4 2

3 1

M P-13 Input 2

1 2

1 M

l F

c.

Power Range Neutron Flux, P-8 4

2 3

1 M

i o.g d.

Power Range Neutron E.

Flux, P-9 4

2 3

1 M

{

g e.

Power Range Neutron Flux, P-10 4

2 3

1, 2 M

f.

Turbine Impulse Chamber y

Pressure, P-13 (Input to P-7) 2 1

2 1

M

~

c' k 23.

Seismic Trip 3 direc-

'2/3 loca-2/3 loca-1, 2 13 l

l g

tions (x,y,z) tions one tions all in 3 locations direction dir xtions i9 9

-~-

- - ~. -

c, TABLE 3.3-3 g

ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION

.g r

5 MINIMUM TOTAL NO.

CHANNELS CHANNELS APPLICABLE FUNCTIONAL UNIT OF CHANNELS TO TRIP OPERABLE MDDES ACTION 5

1.

Safety Injection'(Reactor d

Trip, Feedwater Isolation, g

Start Diesel Generators, e.

Containment Fan Cooler Units, and Component Cooling Water) m i

a.

Manual Initiation 2

1 2

1,2,3,4 19 b.

Automatic Actuation 2

1 2

1,2,3,4 14 w)

Logic and Actuation I

Relays w

c.

Containment 3

2 2

1,2,3,4 15 o'

Pressure-High t

d.

Pressurizer 4

2 3

1, 2, 3#

20 Pressure-Low t

4 l

8 e.

Differential 3/ steam line 2/ steam line 2/ steam line 1, 2, 3 15

- i l

Pressure Between any steam line t

8 Steam Lines-High E

f.

Steam Flow in Two 2/ steam Hne 1/ steam line. 1/ steam line 1,2,3M 15 T

Steam Lines-High any 2 steam g

lines E

Coincident With Either T,,g-LeLw 1 T,,g/ loop 1 T,,,any 1 T,,, any 1, 2, W 15 2 loops 3 loops Or l

Steam Line Pressure-Low 1 pressure /_

1 pressure 1 pressure 1, 2, 3M 15 loop any 2 loops any 3 loops f

+

. -.. _,,,, _ ~,.,,.

, _ -.. - - - =. -

,.r,--

.~,-. _ _ _. _

y.

a,

TABLE 3.3-3 (Continued)

?-.$

ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION 5

n MINIMUM R

CHANNELS CHANNELS APPLICABLE TOTAL NO.

g OF CHANNELS TO TRIP OPERABLE MODES ACTION.

z FUNCTIONAL UNIT

.E 2.

Containment Spray 3

a.

Manual _

2 2 with 2 2

1,2,3,4 19 coincident g

switches N

b.

Automatic Actuation 2

1 2

1,2,3,4 14 Logic and Actuation Relays c.

Containment Pressure-4 2

3 1,2,3 17 High-High R

3.

Containment Isolation w

A a.

Phase "A" Isolation m

1)

Phnual 2

1

-2 1,2,3,4 19 2)

Automatic Actuation 2 1

2 1,2,3,4~

14 Logic and' Actuation Relays 3)

Safety Injection See Item 1. above for all Safety Injection initiating functions and requirements.

b.

Phase "B" Isolation 1)

Manual 2

2 with 2 2

1,2,3,4 19 coincident switches.

e O

e

~

o.

. TABLE 3.3-3 (Continued)

{

ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUENTATION

~

9 MINIMUM 5

TOTAL NO.

CHANNELS CHANNELS APPLICABLE.

E FUNCTIONAL UNIT OF CHANNELS TO TRIP OPERABLE MDDES ACTION i

a c

3.

Containment Isolation (Continued) 5 w*

2)

Automatic Actua-2 1

2 1,2,3,4 14 tion Logic aM

.[

Actuation Relays 3)

Containment 4

2 3

1,2,3 17

-Pressure-High-High w

c.

Containment Ventilation 1

Isolation T

1)

Automatic Actua-2 1

2

.1, 2, 3, 4 18 l

M tion Logic and l

Actuation Relays 2)

Plant Vent Noble 2

1 2

1,2,3,4 18 l

Gas Activity-High (RM-14A and 148)

E g

3)

' Safety Injection-See Ites 1. above for all Safety Injection initiating functions and l

l.

g requirements.

e A

4.

Steam Line Isolation z

8 a.

Manual 1 manual 1 manual 1 manual 1,2,3,4' 24 switch / steam switch / steam switch /

E line line operating I

g steam line i

o.

h i

m

TABLE 3.3-3 (Continued) e, 5

ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUPENTATION

'g g

s MINIMUM TOTAL NO.

CHANNELS CHANNELS APPLICABLE FUNCTIONAL UNIT OF CHANNELS TO TRIP OPERABLE MODES ACTION 4.

Steam Line Isolation (Continued) 3 b.

Automatic' Actuation 2

1 2

1,2,3 22 Logic and Actuation N

Relays c.

Containment Pressure-4 2

3 1,2,3 17 High-High R

d.

Steam Flow in Two 2/ steam line 1/ steam line 1/ steam line 1, 2, 3N 15 l

Steam Lines-High any 2 steam Y

lines 5

Coincident With Either 1 T,,g/ loop 1 T,,,any 1 T,,,any 1, 2, W 15 l

T,,g-Le Lw 2 loops 3 loops Or E

1 pressure /f 1 pressure 1 pressure 1, 2, 3N 15 l

Steam Line Pressure-Low loop any 2 loops any 3 loops o

" 5.

Turbine Trip &

F Feedwater Isolation Y'

a.

Automatic Actuation 2

.1 2

1, 2 25 w

Logic and Actuation E

Relays b.

Steam Generator 3/sta. gen.

2/sta. gen.

1, 2 15 l

Water Level-in any operat-in each oper-High-High ing sta. gen.

stm.~ gen.

e G

f f

e-TABLE 3.3-3 (Continued) e ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION o'

g i

o E

MINIMUM E

TOTAL NO.

CHANNELS CHANNELS APPLICABLE l

e FUNCTIONAL UNIT OF CHANNELS TO TRIP OPERABLE MODES ACTION C

l

}

6.

Auxiliary Feedwater m

i

~

a.

Manual Initiation 1 manual 1 manual 1 manual 1,2,3 24 e

switch / pump switch / pump switch / pump b.

Automatic Actuation 2

1 2

1,2,3 22 Logic and Actuation Relays

'l l

1 Low-Low I

w c.

Sta. Gen. Water Level-T 1)

Start Motor-j 0

Driven Pumps 3/sta. gen.

2/sta. gen.

1, 2, 3 15 l

in any opera-in each ting stm. gen. operating stm. gen.

l 2)

Start Turbine-i R

Driven Pump 3/sta. gen.

2/sta. gen.

2/sta. gen

' 1, 2, 3 15 l

in any in each R

2 operating operating g

stm. gen.

sts. gen.

d.

L % rvoltage-RCP Bus 2/ bus 1/ bus on 1/ bus 1

20 l

' l

=

l 8

Start Turbine-both busses l

Driven Pump Start Motor-Driven

[

l e.

Safety Injection See Item 1. above for all Safety Injection initiating functica and Pumps requirements.

i

=

{

[

h

.n a

-- ~,

s,

TABLE 3.3-3 (Continued)

E ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION 5

c>

E MINIMUM l

TOTAL HO.

CHANNELS CHANNELS APPLICABLE 4

FUNCTIONALllNIT OF CHANNELS TO TRIP OPERABLE MDDES ACTION E

7.

Loss of Power Z

(4.16 'tV Emergency Bus I

Underv>1tage) w a.

First Level 1, 2, 3, 4 m

1) Diesel Start 1/ Bus 1/ Bus 1/ Bus 16

2) Initiation of Load Shed 2/ Bus 2/ Bus 2/ Bus 16 R

b.

Second Level 1, 2, 3, 4 s

T

1) Undervoltage Relays 2/ Bus 2/ Bus 2/ Bus 16

2) Timers to Start Diesel 1/ Bus 1/ Bus 1/ Bus 16

3) Timers to Shed

. Load 1/ Bus 1/ Bus 1/ Bus 16 8.

Engineered Safety Features Actuation' System Interlocks a.

Pressurizer Pressure,LP-11 3

2 2

1,2,3 21 4

2 3

1, 2, 3 21 Low-Low T,,g, P-12 b.

c.

Reactor Trip, P-4 2

2 2

1,2,3 23 e

TABLE 3.3-3 (Continued)

TABLE NOTATIONS

'# rip function may be blocked in this MODE below the P-11 (Pressurizer T

Pressure Interlock) Setpoint.

" Trip function may be blocked in this MODE below the P-12 (Low-Low

. Interlock) Setpoint.

l ACTION STATEMENTS ACTION 14 - With the number of OPERABLE channels one less than the Minimum Channels OPERABLE requirement, be in at least HOT STANDBY within 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 ; however, one channel 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, provided the.

o other channel is OPERABLE.

ACTION 15 - With the number of OPERABLE channels one less than the Total Number of Channels, operation may proceed until performance of the next required ANALOG CHANNEL OPERATIONAL TEST.provided the inoperabl.e 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 16 - With the number of OPERABLE Channels one less than the Total Number of Channels, declare the affected~ Emergency Diesel Generator (s) inoperable and comply with the. ACTION statements of Specification 3.8.1.1; however, one channel 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.

ACTION 17 -.With the number of OPERABLE channels one less than the. Total-Number of Channels, operation may proceed provided the inoperable channel is placed in the bypassed condition and the Minimum' Channels OPERABLE requirement is met. One additional channel 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.

ACTION 18 - With less than the Minimum Channels OPERABLE requirement, operation may continue provided the containment purge supply and exhaust valves-(RCV-11, 12, FCV 660, 661, 662, 663, 664) are maintained closed.

o I

DIABLO CANYON - UNITS 1 & 2 3/4 3-21 Amendment Hos.55 and 54 m-

TABLE 3.3-3 (Continued)

ACTION STATEMENTS (Continued)

ACTION 19 - With the number of OPERABLE channels one less than.the Minimum Channels OPERABLE re.wirement, 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 SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

ACTION 20 - With the number of OPERABLE channels one less than the Total Number of Channels, STARTUP and/or POWER OPERATION may proceed provided the following conditions are satisfied:

The inoperable channel is placed in the tripped condition a.

within I hour, and b.

The Minimum Channels OPERABLE requirement is met; however, the 1noperable channel 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 of other channels per Specification 4.3.2.1.

ACTION 21 -'With less than the Minimum Number of Channels OPERABLE, within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months determine by observation of the associated permissive annunciator window (s) that the interlock is in its required state for the existing pient condition, or apply Specification 3.D.3.

ACTION 22 - With the number of 0PERABLE Channels one less than the Minimum Channels OPERABLE requirement, be in at least HOT STANDBY within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in at least HOT SHUTDOWN within the following 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months ; however, one' channel 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 provided the lother channel is OPERABLE.

ACTION 23 - With the number of OPERABLE channels one less-than the Total Number of Channels, restore the inoperable channel to.0PERABLE 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 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in at least HOT SHUTDOWN within the following 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

ACTION 24 - 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 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months or declare the associated pump or valve inoperable and take the ACTION required by Specification 3.7.1.5 or 3.7.1.2 as applicable.

ACTION 25 - With the number of OPERABLE channels one less than the Minimum

' Channels OPERABLE requirement, be in at least HOT STANDBY within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months ; however, one channel 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 provided the other channel is OPERABLE.

DIABLO CANYON - UNIT 2 3/4 3-22 l

1

- - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - ~ ~ - - ~ - - ~ - - -

~~

TABLE 4.3-2 (Continued)'

~.

E^

5 ENGINEERED SAFETY FEATURES ACTUATION SYSTEN INSTRUNENTAT!Ds-'-

m SURVL1LtANCL REQUIRtMLNI5 o>

E E

TRIP ANALOG AC10ATING e

CHANNLL DEVICE NODES FOR e$

CHANNEL OPERA-OPERA-NASTER SLAVE WHICH CHANNEL CALI-'

IIONAL TIONAL ACTUATION RELAY RELAY SURVEILLANCE ~

[FUNCTIONALUNIT CHECK BRATION TEST TEST LOGIC TEST TEST TEST IS REQUIRED '

i

o. 6.

Auxiliary Feedwater (Continued) d.

Undervoltage - RCP N.A.

R N.A.

N.A.

I e.

Safety Injection See Item 1. above for all Safety Injection Surveillance Requirements.

7.

loss of Power a.

4.16 kV Emergency Bus N.A.

R N. A.

R N.A.

N.A.

M.A.

1,2,3,4 i

Level 1

[

1 b.

4.16 kV Emergency Bus N. A.

R N.A.

N.A.

1, 2, 3, 4 w

Level 2

w

.t

8.

Engineered Safety Feature Actuation System Interlocks i

a.

Pressurizer Pressure, N.A.

R N

N. A.

N.A.

1, 2, 3 P-11 b.

Low-low T, P-12 N. A.

R Q

N.A.

M.A.

N.A.

1, 2, 3 l

c.

Reactor Trip, P-4 N. A.

N.A.

N. A.

R N.A.

N. A..

N.A.

.1, 2, 3 y

2" TABLE NOTATIONS E

z 3 (1) Each train shall be tested at least every 62 days on a STAGGEEED TEST BASIS.

',(2) For the Plant Vent Activity-High monitor only, a CHANNEL FUNCTIONAL TEST sha11 be perfomed at least once every

, 31 days.

m l

o O.

w w

OT i

~

INSTRUMENTATION 3/4.3.3 MONITORING INSTRUMENTATION RADIATION MONITORING FOR PLANT DPERATIONS l

LIMITING CONDITION FOR OPERATION 3.3.3.1 The radiation monitoring instrumentation channels for plant operations shown in Table 3.3-6 shall be OPERABLE with their. Alarm / Trip Setpoints within the specified limits.

APPLICABILITY:

As shown in Table 3.3-6.

ACTION:

With a radiation monitoring channel Alarm / Trip Setpoint for plant a.

operations exceeding the value shown in Table 3.3-6, adjust the Setpoint to within the limit within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months or declare the channel inoperable.

b.

With one or more radiation monitoring channels for plant operations inoperable, take the ACTION shown in Table 3.3-6, c.

The provisions of Specification 3.0.3 are not applicable.

.l'

' SURVEILLANCE REQUIREMENTS 4.3.3.1 Each radiation monitoring instrumentation channel for plant operations shall be demonstrated OPERABLE by the performance of the CHANNEL CHECK, CHANNEL CALIBRATION and CHANNEL FUNCTIONAL TEST for the MODES and at the frequencies shown in Table 4.3-3.

DIABLO CANYON - UNITS 1 & 2 3/4 3-36 Amendment Nos. 55 and 54

4 c,

TABLE 3.3-6 E

~

g~

RADIATION NONITORING INSTRUNENTATION FOR PLANT OPERATIONS g

NININUN CHANNELS APPLICABLE ALARN/ TRIP Q

INSTRUNENT OPERABLE NCDES SETP0 INT ACTION h

1.

Fuel Storage Area 5

i g

a.

Spent Fuel Pool 1

$ 75 mR/hr 30 & 32**

l b.

New Fuel Storage 1

1 15 mR/hr 30.& 32**

2.

Control Room Ventilacion Mode Change 2***

All i 2 mR/hr 34 1

3.

Containment m2 m

a.

Gaseous Activity I

ww

1) Containment 1

6 Per Specification 33 l

Ventilation 3.3.3.10 i

Isolation (RM-14A or 148) t

2) RCS Leakage 1

1,2,3,4 M.A.

31 b.

Particulate Activity RCS Leakage 1

1,2,3,4 N.A.

31

.a MN t

$[

With fuel in the spent fuel pool or new fuel storage vault.

- With irradiated fuel in the spent fuel pool.

e-4 g g ***0ne channel for each normal intake to the Control Room Ventilation System (common to both units).

~

c)

O e

to i

TABLE 3.3-6 (Continued)

ACTION STATEMENTS ACTION 30 -

With less than the Minimum Channels OPERABLE requirement, opera-tion may continue for up to 30 days provided an appropriate portable continuous monitor with the same Alarm Setpoint or an individual qualified in radiation protection procedures with a radiation dose rate monitoring device is provided in the fuel storage pool area.

Restore the inoperable monitors to OPERABLE,

status within 30 days or suspend all operations involving fuel movement in the fuel storage pool areas.

ACTION 31 -

With the number of OPERABLE channels less than required by the Minimum Channels OPERABLE requirement, comply with the ACTION requirements of Specification 3.4.6.1.

The provisions of Specification 3.0.4 are not applicable.

ACTION 32 -

With the number of OPERABLE channels less than required by the Minimum Channels OPERABLE requirement, comply with the ACTION requirements of Specification 3.9.12.

ACTION 33 -

With the number of OPERABLE channels less than required by the Minimum Channels OPERABLE requirement, comply with the ACTION requirements of Specification 3.9.9.

ACTION 34 -

With the number of OPERABLE channels less than required by the Minimum Channels OPERABLE requirement, within I hour initiate and maintain operation of the Control Room Ventilation System in a recirculation mode with the HEPA filter and charcoal adsorber bank in operation.

l l-l

-DIABLO CANYON - UNITS 1 & 2 3/4 3-38 Amendment Nos. 55 and 54 l

u e~-

TABLE 4.3-3 3

E

_R_ADIATION MONITORING INSTRUNENTATION FOR PLANT OPERATIONS SURVEILLANCE REQUIREMENTS E>

n CHANNEL MODES FOR WHICH E

CHANNEL CHANNEL FUNCTIONAL SURVEILLANCE g

CHECK CALIBRATION TEST IS REQUIRED 1.

Fuel Storage Area

- z O

a.

Spent Fuel Pool 5

R M

w w

b.

New Fuel Storage S

R M

c.

2.

Control Room n

Ventilation Mode Change S

R M

All 3.

Containment i

w a.

Gaseous Activity s*

1)

Containment S

R M

6 T

Ventilation Isolation (RM-14A or 148) 2)

RCS Leakage 5

R M

1,2,3,4 I

b.

Particulate Activity t

l RCS Leakage S

R M

1, 2, 3, 4 i

i

With fuel in the spent fuel pool or new fuel storage vault.

i

-,s

.~,.v-.

.r

- - - -*.~.

O INSTRUMENTATION NOVABLE'INCORE DETECTORS I

LIMITING CONDITION FOR OPERATION 3.3.3.2 The Movable Incore Detection System shall be OPERABLE with:

a.

At least 75% of the detector thimbles, b.

A minimum of two detector thimbles per core quadrant, and c.

Sufficient movable detectors, drive, and readout equipment to map these thimbles.

APPLICABILITY:

When the Movable Incore Detection System is used for:

a.

Recalibration of the Excore Neutron Flux Detection System, or b.

Monitoring the QUADRANT POWER TILT RATIO, or MeasurementofFh,F(Z)andF,y.

c.

9 ACTION:

With the Movable Incore Detection System inoperable, do not use the system for the above applicable monitoring or calibration functions.

The provisions of Specification 3.0.3 are not applicable.

l 1

SURVEILLANCE REQUIREMENTS 4.3.3.2 The Movable Incore Detection System shall be demonstrated OPERABLE at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months Oy normalizing each detector output when required l

for:

a.

Recalibration of the Excore Neutron Flux Detection System, or b.

Monitoring the QUADRANT POWER TILT RATIO, or MeasurementofFh,F(Z)andF c.

q 9

i DIABLO CANYON - UNITS 1 & 2 3/4 3-40 Amendment Nos. 55 and 54

S I'NSTRUMENTATION i

SEISMIC INSTRUMENTATION i

LIMITING CONDITION FOR OPERATION 3.3.3.3 The seismic monitoring instrumentation # shown in Table 3.3-7 shall be OPERABLE.

APPLICABILITY:

At all times.

ACTION:

With one or more seismic monitoring instruments inoperable for more a.

j than 30 days, prepare and submit a Special Report to the Commission pursuant to Specification 6.9.2 within the next 10 days outlining the cause of the malfunction and the plans for restoring the instrument (s) to OPERABLE status, b.

The provisions of Specification 3.0.3 are not applicable.

l SURVEILLANCE REQUIREMENTS 4.3.3.3.1 Each of the above seismic monitoring instruments shall be demonstrated OPERABLE by the performance of the CHANNEL CHECK, CHANNEL CALIBRATION and CHANNEL-FUNCTIONAL TEST at the frequencies shown in Table 4.3-4.

4.3.3.3.2 Each of the above seismic monitoring instruments actuated during a seismic event shall be restored to OPERABLE status within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months and a CHANNEL CALIBRATION, as applicable, performed within 10 days following the seismic 4

event.

Data shall be retrieved from actuated instrumerts and analyzed to deter-mine the magnitude of the vibratory ground motion.

A i.ecial Report shall be prepared and submitted to the Commission pursuant to s,n:ification 6.9.2 within 14 days describing the magnitude, frequency spectrum in::. resultant affect upon facility features important to safety.

The seismic monitoring instrumentation is common to both units but located in Unit 1 or common areas.

DIABLO CANYON - UNITS 1 & 2 3/4 3-41 Amendment Nos. 55 and 54 m

=

w

-, -, - + -.

-e--

TABLE 3.3-7 l

SEISMIC MONITORING INSTRUMENTATION MINIMUM HEASUREMENT INSTRUMENTS INSTRUMENTS AND SENSOR LOCATIONS RANGE OPERABLE

1. Triaxial Time-History Accelographs

a. Containment Base Slab El 89, 180' 1 Ig in b.. Top Unit 1 Containment, El 303.5, 225' 1 2g I

c. Aux Building, El 64 1 Ig i

2. Triaxial Peak Accelographs

a. Containment Base Slab, El 89, 180' 1 2g i

b. Top Unit 1 Containment, El 303.5, 225' 1 Sg 1

c. Intake near ASW Pump 1-2 Bay El 2 12g i

d. Turbine Building, El 85, Machine Shop 1 2g i

e. Aux Building, El 140 Hot Shop 1 2g i

f. Aux Building, El 140, Near Control 1 2g i

Room Door

3. Triaxial Response Spectrum Recorders Containment Base Slab El 89, 180*

1.6 - 90 g 1

2-25.4 Hz

With reactor control room indications or annunciation.

DIABLO CANYON - UNITS 1 & 2 3/4 3-42 m

TABLE 4.3-4 j

SEISMIC MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS CHANNEL INSTRUMENTS AND SENSOR LOCATIONS C C CA BA ON 1S

1. Triaxial Time-History Accelographs

a. Containment Base Slab El 89, 180'**

M*

R SA

b. Top Unit 1 Containment, El 303.5, 225' M*

R SA

c. Aux Building, El 64 M*

R SA

2. Triaxial Peak Accolographs

a. Containment Base Slab. El 89, 180' N.A.

R***

N.A.

b. Top Unit 1 Containment, El 303.5, 225' N.A.

R***

N. A.

c. Intake near ASW Pump 1-2 Bay, El 2 N.A.

R***

N.A.

d. Turbine Building, El 85, Machine Shop N.A.

R***

N.A.

e. Aux Building, El 140, Hot Shop N. A.

R***

N.A.

f. Aux Building, El 140, Near Control N.A.

R***

N.A.

Room Door

3. Triaxial Response-Spectrum Recorders Containment Base Slab, El 89, 180' N.A.

R***

N. A.

Except seismic trigger.

- With reactor control room indications or annunciation.

- - Channel calibration shall be in accordance with ANSI /ANS-2,2-1978.

l DIABLO CANYON - UNITS 1 & 2 3/4 3-43 1

\\

INSTRUMENTATION METEOROLOGICAL INSTRUMENTATION i

LIMITING CONDITION FOR OPERATION 3.3.3.4 The meteorological monitoring instrumentation channels # shown in Table 3.3-8 shall be OPERABLE.

APPLICABILITY:

At all times.

ACTION:

With one or more required meteorological monitoring channels inoperable a.

l for more than 7 days, prepare and submit a Special Report to the Commission pursuant to Specification 6.9.2 within the next 10 days l

outlining the cause of the malfunction and the plans for restoring the channel (s) to OPERABLE status, b.

The provisions of Specification 3.0.3 are not applicable.

l l

. SURVEILLANCE RE0VIREMENTS 4.3.3.4 Each of the above meteorological monitoring instrumentation channels shall be demonstrated OPERABLE by the performance of the CHANNEL CHECK and CHANNEL CALIBRATION at the frequencies shown in Table 4.3-5.

1 1

The meteorological monitoring instrumentation channels are common to both units.

I DIABLO CANYON - UNITS 1 & 2 3/4 3 44 Amendment Nos. 55 and 54 W

~..m

~

TABLE 4.3-7 c

h ACCIDENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS o

9$

CHANNEL CHANNEL g

INSTRUMENT CHECK CALIBRATION 1.

-Containment Pressure M

R E

2.

Reactor Coolant Outlet Temperature - Thot (Wide Range)

M R

m 3.

Reactor Coolant Inlet Temperature - T I"

N* T )

cold

[

4.

Reactor Coolant Pressure - Wide Range M

R

=

5.

Pressurizer Water Level M

R 6.

Steam Line Pressure M

R 7.

Steam Generator Water Level - Narrow Range M

R i

8.

Refueling Water Storage Tank Water Level M

R 1

9.

Containment Reactor Cavity Sump Level-Wide Range M

R 10.

Containment Recirculation Sump Level-Marrow Range M

R l

11. Auxiliary Feedwater Flow Rate M

R l

12.

Reactor Coolant System Subcooling Margin Monitor M

R

[

i 13.

PORY Position Indicator M

R i

14.

PORY Block Valve Position Indicator M

R 15.

Safety Valve Position Indicator M

R h

16.

In Core Thermocouple.;

M R

17. Main Steam Line Radiation Monitor M

R l

f 18.

Containment Area Radiation Monitor-High Range M

R*

19.

Plant Vent Radiation Monitor-High Range M

R 20.

Reactor Vessel Level Indication System M

R

CHANNEL CALIBRATION may consist of an electronic calibration of the channel, not including the detector, for range decades above 10 R/h and a one point calibration check of the detector below 10 R/h with an installed or portable gamma $9urce.

i 1

INSTRUMENTATION CHLORINE DETECTION SYSTEMS LIMITING CONDITION FOR OPERATION 3.3.3.7 Two independent Chlorine Detection Systems,# with their Alam/ Trip Setpoints adjusted to actuate at a chlorine concentration of less than or equal to 5 ppe, shall be OPERABLE.

APPLICABILITY: All MODES, when bulk chlorine gas is stored on the plant site.

ACTION:

With one Chlorine Detection System inoperable, restore the inoperable i

a.

system to OPERABLE status within 7 days or within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months initiate and maintain operation of the Control Room Ventilation System in a recirculation mode with the HEPA filter and charcoal i

absorber system in operation.

1 b.

With both Chlorine Detection Systems inoperable, within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months initiate and maintain operation of the Control Room Ventilation System in a recirculation mode with the HEPA filter and charcoal absorber system in operation.

1 l

SURVEILLANCE REQUIREMENTS 4.3.3.7 Each Chlorine Detection System shall be demonstrated OPERABLE by per-l formance of a CHANNEL CHECK at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and a CHANNEL FUNCTIONAL l

TEST at least once per 31 days.

At least once per 18 months, the following inspections and maintenance shall be performed:

a.

Check constant head bottle level and refill as necessary, b.

Clean the sensing cells, c.

Check flow meter operation and clean or replace filters and air lines as necessary, d.

Check air pump for proper operation, and e.

Verify that the detector responds to chlorine.

l L

Thc Chlorine Detection System is common to both units and is installed in the normal intak.. to the Control Room Ventilation System.

DIABLO CANYON - UNITS 1 & 2 3/4 3-54 Amendment Nos. 55 and 54 l

. - - -. ~ -

~

. INSTRUMENTATION FIRE DETECTION INSTRUMENTATION i

LIMITING CONDITION FOR OPERATION 3.3.3.8 As a minimum, the fire detection instrumentation for each fire detection zone shown in Table 3.3-11 shall be OPERABLE.

APPLICABILITY: Whenever equipment protected by the fire detection instrument is required to be OPERABLE.

ACTION:

a.

With the number of OPERABLE fire detection instrument (s) less than the Minimum Instruments OPERABLE requirement of Table 3.3-11, within I hour establish a fire watch patrol to inspect the zone (s) with the inoperable instrument (s) at least once per hour, unless the instrument (s) is located inside the containment, then inspect the containment at least once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months or monitor the containment air temperature at least once per hour at the locations I'sted in Specification 4.6.1.5.

b.

Within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months following a seismic event in excess of 0.02 g,hin each zone shown in Table 3.3-11 shall be inspected for fires.

Wit 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months an engineering evaluation shall be performed to verify the OPERABILITY of the Fire Detection System, c.

The provisions of Specification 3.0.3 are not applicable.

l SURVEILLANCE REQUIREMENTS 4.3.3.8.1 Each of the above required fire detection instruments which are accessible during plant operation shall be demonstrated OPERABLE at least once per 6 months by performance of a CHANNEL FUNCTIONAL TEST.

Fire detectors which are not accessible during plant operation shall be demonstrated OPERABLE by the performance of a CHANNEL FUNCTIONAL TEST during each COLD SHUTOOWN exceeding 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months unless performed in the previous 6 months.

4.3.3.8.2 The supervision circuitry associated with the detector alarms of each of the above required fire detection instruments shall be demonstrated OPERABLE at least once per 6 months.

l DIABLO CANYON - UNITS 1 & 2 3/4 3-55 Amendment Nos. 55 and 54 1

i l

-., [

TABLE 3.3-11 FIRE DETECTION INSTRUMENTS PANEL A ZONE INSTRUMENT LOCATION MINIMUM INSTRUMENTS OPERABLE SMOKE HEAT OR FLAME 1

Cable Spreading Room 10 4(1) 3 4kV Switchgear Bus F Room 1

N.A.

)

4kV Switchgear Bus G Room 1

N.A.

4kV Switchgear Bus H Room 1

N. A.

4kV Switchgear Ventilation Fan Room 1

N.A.

4 4kV Switchgear Bus F Cable Spreading Area 1

N.A.

4kV Switchgear Bus G Cable Spreading Area 1

N.A.

4kV Switchgear Bus H Cable Spreading Area 1

N.A.

7 Containment Electrical Penetration Zone 7 4

N. A.

8 Containment Electrical Penetration Zone 8 3

N.A.

9 Rod Control Programmer / Reactor Trip Breaker Area 3

N.A.

l Battery No.1 Charger Room 1

N.A.

Battery No. 2 Charger Room 1

N.A.

Battery No. 3 Charger Room 1

N. A.

10 480 Volt Bus F Area 1

N.A.

480 Volt Bus G Area 1

N. A.

480 Volt Bus H Area 1

N.A.

Hot Shutdown Panel 1

N.A.

5) l 12 Inside Containment 17 N. A.

13 Control Room Ventilation Return / Exhaust 1

N.A.

L 14 Control Room Ventilation Return / Exhaust 1

N.A.

15 Outside the Auxiliary Salt Water Pump Room 1

N. t..

DIABLO CANYON - UNITS 1 & 2 3/4 3-56 I

.--..,--.-,,e

.-e,

w-

- ~ ~ ' ' *

~

)

INSTRUMENTATION RADI0 ACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION l

LIMITING CONDITION FOR OPERATION 3

3.3.3.9 The radioactive liquid effluent monitoring instrumentation channels shown in Table 3.3-12 shall be OPERABLE with their Alarm / Trip Setpoints set to ensure that the limits of Specification 3.11.1.1 are not exceeded.

The Alare/

Trip Setpoints of these channels shall be determined in accordance with the methodology and parameters in the OFFSITE DOSE CALCULATION PROCEDURE (ODCP).

APPLICABILITY:

At all times.

ACTION:

With a radioactive liquid effluent monitoring instrumentation channel a.

Alarm / Trip Setpoint less conservative than required by the above specification, immediately suspend the release of radioactive liquid effluents monitored by the affected channel or declare the channel inoperable, b.

With less than the minimum number of radioactive liquid effluent monitoring instrumentation channels OPERABLE, take the ACTION shown in Table 3.3-12.

Restore the inoperable instrumentation to OPERABLE status within the time specified in the ACTION, or explain in the next Semiannual Radioactive Effluent Release Report pursuant to Specification 6.9.1.6 why this inoperability was not corrected within the time specified.

The provisions of Specification 3.0.3 are not applicable.

l c.

SURVEILLANCE REQUIREMENTS 4.3.3.9.1 Each radioactive liquid effluent monitoring instrumentation channel shall be demonstrated OPERABLE by performance of the CHANNEL CHECK, SOURCE CHECK, CHANNEL CALIBRATION and CHANNEL FUNCTIONAL TEST at the frequencies shown in Table 4.3-8.

4.3.3.9.2 At least one saltwater pump shall be determined operating and l

providing dilution to the discharge structure at least once per 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months whenever dilution is required to meet the limits of Specification 3.11.1.1.

DIABLO CANYON - UNITS 1 & 2 3/4 3-59 Amendment Nos. 55 and 54 1

TABLE 3.3-12 RADI0 ACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION MINIMUM CHANNELS INSTRUMENT OPERABLE ACTION 1.

Radioactivity Monitors Providing Alarm and Automatic Termination of Release Liquid Radweste Effluent Line (RM-18)#

1 40 a.

b.

Steam Generator Blowdown Tank (RM-23) 1 41 2.

Flow Rate Measurement Devices Liquid Radwaste Effluent Line (FR-20)#

1 43 a.

b.

Steam Generator Blowdown Effluent Lines (FR-53) 1 43 c.

Otly Water Separator Effluent Line (FR-251)#

1 43 3.

Radioactivity Monitor Not Providing Automatic Termination of Release Olly Water Separator Effluent Line (RM-3)#

1 42

This Radioactive Liquid Effluent Monitoring Instrumentation is common to both units.

1 DIABLO CANYON - UNITS 1 & 2 3/4 3-60

TABLE 4.3-8 (Continued)

TABLE NOTATION (1) The CHANNEL FUNCTIONAL TEST shall hiso demonstrate that automatic isola-tion of this pathway and control room alarm annunciation occurs if any of the following conditions exists:

a.

Instrument indicates measured levels above the Alarm / Trip Setpoint (isolation and alarm), or b.

Relay control circuit failure (isolation only), or c.

Instrument indicates a downscale failure (alarm only), or d.

Instrument controls not set in operate mode (alarm only).

(2) The CHANNEL FUNCTIONAL TEST shall also demonstrate that control room alarm annunciation occurs if any of the following conditions exists:

.a.

Instrument indicates measured levels above the Alarm Setpoint, or b.

Circuit failure, or c.

Instrument indicates a downscale failure, or d.

Instrument controls not set in operate mode.

(3) The initial CHANNEL CALIBRATION shall be performed using one or more of the referen 9 standards certified by the National Bureau of Standards (NBS) or irg standards that have been obtained from suppliers that participate in measurement assurance activities with NBS.

These standards shall permit calibrating the system over its intended range of energy and measurement range.

For subsequent CHANNEL CALIBRATION, sources that have been related to the initial calibration shall be used.

(4) CHANNEL CHECK shall consist of verifying indication of flow during periods of release.

CHANNEL CHECK shall be made at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months on days on which continuous, periodic, or batch releases are made.

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l DIABLO CANYON - UNITS 1 & 2 3/4 3-63 i

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INSTRUMENTATION RADI0 ACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION LIMITING CONDITION FOR OPERATION I

3.3.3.10 The radioactive gaseous effluent monitoring inst shown in Table 3.3-13 shall be OPERABLE with their Alamr.'unentation cha rip Setpoints set to ensure that the limits of Specifications 3.11.2.1 and 3.*t1.2.5 are not exceeded.

The Alam/ Trip Setpoints of these channels meeting Specification 3.11.2.1 shall 4

be detemined and adjusted in accordance with the methodology and parameters in the ODCP.

APPLICABILITY: As shown in Table 3.3-13.

ACTION:

a.

With a radioactive gaseous effluent monitoring instrumentation

{

channel Alarm / Trip Setpoint less conservative than required by the l

l above specification, immediately suspend the release of radioactive I

gaseous effluents monitored by the affected channel, or declare the channel inoperable.

b.

With the number of OPERABLE radioactive gaseous effluent monitoring instrumentation channels less than the Minimum Channels OPERABLE, take the ACTION shown in Table 3.3-13.

Restore the inoperable instrumentation to OPERABLE status within the time specified in the ACTION or explain in the next Semiannual Radioactive Effluent Release Report pursuant to Specification 6.9.1.6 why this inopera-l bility was not corrected within the time specified.

c.

The provisions of Specification 3.0.3 are not applicable.

SURVEILLANCE REQUIREMENTS l

l l

4.3.3.10 Each radioactive gaseous effluent monitoring instrumentation channel l

shall be demonstrated OPERABLE by perfomance of the CHANNEL CHECK, SOURCE CHECK, CHANNEL CALIBRATION and CHANNEL FUNCTIONAL TEST at the frequencies l

L shown in Table 4.3-9.

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DIABLO CANYON - UNITS 1 & 2 3/4 3-64 Amendment Nos. 55 and 54 l

}

O REACTOR COOLANT SYSTEM OVERPRESSURE PROTECTION SYSTEMS LIMITING CONDITION FOR OPERATION 3.4.9.3 The following Overpressure Protection Systems shall be OPERABLE:

a.

Two power-operated relief valves (PORVs) with a lift setting of less than or equal to 450 psig, or th: Aeactor Coolant System (RCS) depressurizeo with an RCS vent of greater than or equal to 2.07 square inches.

APPLICABILITY:

MODE 4 when the temperature of any RCS cold leg is less than or equal to 323*F, MODE 5 and MODE 6 with the reactor vessel head on.

ACTION:

a.

With one PORV inoperable, restore the inoperable PORV to OPERABLE status within 7 days or deprescurize and vent the RCS through a 2.07 square inch vent (s) within the next 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months , b.

With both PORVs inoperable, depressurize and vent the RCS through a 2.07 square inch vent (s) within 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months .

c.

In the event either the PORVs or the RCS vent (s) are used to mitigate an RCS pressure transient, a Special Report shall be prepared and submitted to the Commission pursuant to Specification 6.9.2 within 30 days. The report shall describe the circumstances initiating the transient, the effect of the PORVs or vent (s) on the transient, and any corrective action necessary to prevent recurrence.

4 DIABLO CANYON - UNITS 1 & 2 3/4 4-35 Amendment Nos. 55 and 54 l

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REACTOR COOLANT SYSTEM SURVEILLANCE REQUIREMENTS 4.4.9.3.1 Each PORV shall be demonstrated OPERABLE by:

a.

Performanc'e of a CHANNEL FUNCTIONAL TEST on the PORV actuation channel, but excluding valve operation, within 31 days prior to entering a condition in which the PORV is required OPERABLE; b.

Performance of a CHANNEL CALIBRATION on the PORV actuation channel at least once per 18 months; and Verifying the PORV isolation valve is open at least once per 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months c.

when the PORV is being used for overpressure protection.

4.4.9.3.2 The RCS vent (s) shall be verified to be open at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months

when the vent (s) is being used for overpressure protection.

"Except when'the vent pathway is provided with a valve which is locked, sealed, or otherwise secured in the open position, then verify these valves open at least once per 31 days, DIABLO CANYON - UNITS 1 & 2 3/4 4-36 1

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o REACTORCOOLANTSYQg 3/4.4.10 STRUCTURAL INTEGRITY LIMITING CONDITION FOR OPERATION i

3.4.10 The structural integrity of ASME Code Class 1, 2 and 3 components chall be maintained in accordance with Specification 4.4.10.

APPLICABILITY: All MODES.

ACTION:

a.

With the structural integrity of any ASME Code Class I component (s) not conforming to the above requiromints, restore the structural integrity of the affected component (s) to within its limit or isolate the affected component (s) prior to increasing the Reactor Coolant System temperature more than 50*F above the minimum temperature required by NDT considerations.

b.

With the structural integrity of any ASME Code Class 2 component (s) not conforming to the above requirements, restore the structural integrity of the affected component (s) to within its limit or isolate the affected component (s) prior to increasing the Reactor Coolant System temperature above 200'F.

c.

With the structural integrity of any ASME Code Class 3 component (s) not conforming to the above requirements, restore the structural l

integrity of the affected component (s) to within its limit or isolate the affected component (s) from service.

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SURVEILLANCE REQUIREMENTS 4.4.10 In addition to the requirements of Specification 4.0.5, each reactor coolant' pump flywheel shall be inspected per the recommendations of Regulatory Position C.4.b of Regulatory Guide 1.14. Revision 1, August 1975.

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DIABLO CANYON - UNITS 1 & 2 3/4 4-37 Amendment Nos. 55 and 54

REACTOR COOLANT SYSTEM 3/4.4.11 REACTOR VESSEL HEAD VENT,$,

LIMITING CONDITION FOR OPERATION 3.4.11 At least one reactor vessel head vent path consisting of at least two valves in series powered from emergency busses shall be OPERABLE and closed.

APPLICABILITY:

MODES 1, 2, 3, and 4.

ACTIO_N:

With the above reactor vessel head vent path inoperable, STARTUP and/or POWER OPERATION may continue provided the inoperable vent path is maintained closed with power removed from the valve actuator of all the valves in the inoperable vent path; restore the inoperable vent path to OPERABLE status within 30 days, or, be in HOT STANDBY within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SHUTDOWN within the following 30 hoJrs.

SURVEILLANCE REQUIREMENTS 4.4.11 Each reactor vessel head vent path shall be demonstrated OPERABLE at least once per 18 months by:

a.

Verifying all manual isolation valves in each vent path are locked or sealed in the open position, b.

Cycling each valve in the vent path through at least one complete cycle of full travel from the control room during COLD SHUTDOWN or REFUELING, and c,

Verifying flow through the reactor vessel head vent paths during venting during COLD SHUTDOWN or REFUELING.

DIABLO CANYON - UNITS 1 & 2 3/4 4-38 l

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9 8

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REJECT I

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1 CONTINUE-

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l TESTING 2

3 r

2 ACCEPT 1

0 10 20 30 40 50 80 70 80 90 100 N

FIGURE 4.7-1 SAMPLE PLAN 2) FOR SNUBBER FUNCTIONAL TEST DIABLO CANYON - UNITS 1 & 2 3/4 7-23

'O PLANT $YSTEMS 4

3/4.7.8 SEALED SOURCE CONTAMINATION i

i LIMITING CONDITION FOR OPERATION 3.7.8.1 Each sealed source containing radioactive material in excess of 100 microcuries of beta and/or gamma emitting material or 10 microcuries of alpha emitting material shall be free of greater than or equal to 0.005 micro-curie of removable contamination.

APPLICABILITY: At all times.

ACTION:

a.

With a sealed source having removable contamination in excess of the above limits, immediately withdraw the sealed source from use, and either:

1.

Decontaminate and repair the sealed source, or 2.

Dispose of the sealed source in accordance with Commission Regulations.

i b.

The provisions of Specification 3.0.3 are not applicable.

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SURVEILLANCE REQUIREMENTS 4.7.8.1.1 Test Requirements - Each sealed source shall be tested for leakage and/or contamination by:

a.

The licensee, or b.

Other persons specifically authorized by the Commission or an Agreement State, The test method shall have a detection sensitivity of at least 0.005 micro-curie per test sample.

4.7.8.1.2 Test Frequencies - Each category of sealed sources (excluding startup sources and fission detectors previously subjected to core flux) shall be tested at the frequency described below, s.

Sources in use - At least once per 6 months for all sea 16d sources containing radioactive materials:

1)

With a half-life greater than 30 days (excluding Hydrogen 3),

and 2)

In any form other than gas.

DIABLO CANYON - UNITS 1 & 2 3/4 7-24 Amendment Nos. 55 and 54

f(ANT. SYSTEMS SURVEILLANCE REQUIREMENTS (Continued) i b.

Stored sources not in use - Each sealed source and fission detector shall be tested prior to use or transfer to another licensee unless tested within the previous 6 months.

Sealed sources and fission detectors transferred without a certificate indicating the last test date shall be tested prior to being placed into use; and c.

Startup sources and fission detectors - Each sealed startup source and fission detector shall be tested within 31 days prior to being subjected to core flux or inscalled in core components or the core and following repair or maintenance of the source.

4.7.8.1.3 Reports - A report shall be prepared and submitted to the Commission on an annual basis if sealed source or fission detector leakage tests reveal the presence of greater than or equal to 0.005 microcurie of removable contamination.

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DIABLO CANYON - UNITS 1 & 2 3/4 7-25

_ PLANT SYSTEMS 3/4.7.9 FIRE SUPPRESSION SYSTEMS FIRE SUPPRESSION WATER SYSTEM LIMITING CONDITION FOR OPERATION 3.7.9.1 The Fire Suppression Water System shall be OPERABLE with; a.

At least two high pressure pumps, each with a capacity of 2260 gps, taking suction from the firewater tank containing a minimum usable volume of 270,000 gallons, with its discharge aligned to the fire suppression

header,

~

b.

Gravity feed to the fire suppression header from a raw water reservior with a minimum usable volume of 270,000 gallons, and c.

An OPERABLE fire suppression header flow path through distribution piping with OPERABLE sectionalizing control or isolation valves to the yard hydrant curb valves, the last valve ahead of the water flow alarm device on each sprinkler, hose standpipe or Spray System riser required to be OPERABLE per Specifications 3.7.9.2 and 3.7.9.5.

APPLICABILITY:

At all times.

ACTION:

a.

With either one pump and its water supply or the raw water gravity feed water supply inoperable, restore the inoperable equipment to OPERABLE status within 7 days, or provide an alternate backup pump or supply.

The provisions of Specification 3.0.3 are not applicable. l b.

With the Fire Suppression Water System otherwise inoperable establish a backup Fire Suppression Water System within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

Except the suppression header check valve bypass valves shall be closed unless the gravity feed to the suppression header is inoperable, or inadequata to supply the system for fire protection purposes.

DIABLO CANYON - UNITS 1 & 2 3/4 7-26 Amendment Nos. 55 and 54

~

PLANT SYSTEMS SURVEILLANCE REQUIREMENTS 4.7.9.1 The Fire Suppression Water System shall be demonstrated OPERABLE:

a.

At least once per 7 days by verifying the water supply volume, b.

At least once per 31 days by starting each pump and operating it for at least 15 minutes on recirculation flow, c.

At least once per 31 days by verifying that each valve * (manual, power-operated, or automatic) in the flow path is in its correct

position, d.

At least once per 6 months by performance of a system flush of the outside distribution loop to verify no flow blockage, e.

At least once per 12 months by cycling each testable valve in the flow path through at least one complete cycle of full travel, f.

At least once per 18 months by:

1)

Verifying that each pump develops at least 2250 gpm at a developed head of 80 psig, 2)

Cycling each valve in the flow path that is not testable during i

plant operation through at least one complete cycle of full travel, and 3)

Verifying that each high pressure pump starts to maintain the Fire Suppression Water System pressure greater than or equal to 67 psig.

g.

At least once per 3 years by performing a flow test of the. system in accordance with Chapter 5, Section 11 of the Fire Protection Handbook, 14th Edition, published by the National Fire Protection Association.

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1

Except valves which are located inside the containment and are locked, sealed, or otherwise secured in position.

These valves shall be verified in the cor-rect position during each COLD SHUTDOWN except such verification need not be performed more often than once per 92 days.

DIABLO CANYON - UNITS 1 & 2 3/4 7-27

O

. PLANT SYSTEMS SPRAY AND/0R SPRINKLER SYSTEMS LIMITING CONDITION FOR OPERATION 3.7.9.2 The following spray and/or Sprinkler Systems shall be OPERABLE:

a.

500/25 kV Main Transformer Bank, b.

25/4 kV Unit Auxiliary Transformer No. 2, c.

230/12 kV Standby Startup Transformer No.1, d.

12/4 kV Standby Startup Transformer No. 2, e.

Auxiliary Feedwater Pumps Area, l

f.

Centrifugal Charging Pumps Area, i

g.

Component Cooling Water Pumps Area, and h.

Containment Penetration Area.

APPLICABILITY:

Whenever equipment protected by the Spray / Sprinkler System is required to be OPERABLE.

l ACTION:

'l a.

With one or more of the above required Spray and/or Sprinkler Systems inoperable, within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months , establish a continuous fire watch with backup fire suppression equipment for those areas in which redundant systems or components could be damaged; for other areas, establish an hourly fire watch patrol.

b.

The provisions of Specification 3.0.3 are not applicable.

l SURVEILLANCE REQUIREMENTS l

4.7.9.2 Each of the above required Spray and/or Sprinkler Systems shall be demonstrated OPERABLE:

a.

At least once per 31 days by verifying that each valve (manual, power-p operated, or automatic) in the flow path is in its correct position, b.

At least once per 12 months by cycling each testable valve in the flow path through at least one cycle, c.

At least once per 18 months:

1)

By performing a system functional test which includes simulated automatic actuation of the system, and:

DIABLO CANYON - UNITS 1 & 2 3/4 7-28 Amendment Nos. 55 and 54 l

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J l

PLANT SYSTEMS j

SURVEILLANCE REQUIREMENTS (Continu6d) a)

Verifying that the automatic valves in the flow path actuate to their correct positions on a test signal, and b)

Cycling each valve in the flow path that is not testable during plant operation through at least one cycle.

2)

By a visual inspection of the dry pipe spray and sprinkler headers to verify their integrity, and 3)

By a visual inspection of each nozzle's spray area to verify the spray pattern is not obstructed.

d.

At least once per 3 years by performing an air or water flow test through each open head spray / sprinkler / deluge header and verifying each open head spray / sprinkler / deluge nozzle is unobstructed.

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DIABLO CANYON - UNITS 1 & 2 3/4 7-29 l

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PLANT SYSTEMS

)

CO SYSTEM 2

l.

LIMITING CONDITION FOR OPERATION 3.7.9.3 The Low Pressure CO System with the subsystems shown in Table 3.7-3 shall be OPERABLE.

2 APPLICABILITY: Whenever equipment protected by the Low Pressure CO IY't'* I' required to be OPERABLE.

2 ACTION:

With the above required automatic Low Pressure CO,ith backup f a.

System inoperable, within I hour, establish a continuous fire watch W suppression equipment for those areas in which redundant systems or components could be damaged; for other areas, establish an hourly fire watch patrol. With a hose reel station inoperable, provide backup fire suppression equipment in the affected area within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months .-

b.

The provisions of Specification 3.0.3 are not applicable.

SURVEILLANCE REQUIREMENTS 4.7.9.3 The abovs required Low Pressure CO OPERABLE:

2 System shall be demonstrated a.

At least once per 7 days by verifying CO storage tank level to be 2

1 50% and pressure to be 1 290 psig, b.

At least once per 31 days by verifying that each valve (manual, power-operated, or automatic) in the flow path is in its correct position, and c.

At least once per 18 months by verifying:

1)-

The system valves and associated ventilation dampers and fire door release mechanisms actuate manually and automatically, upon receipt of a simulated actuation signal, and 2)

Flow from each nozzle during a " Puff Test."

t DIABLO CANYON - UNITS 1 & 2 3/4 7-30 Amendment Nos. 55 and 54

-, ~.. _. -

i TABLE 3.7-3 C0 SYSTEM 7

1.

Diesel Generator No. I flooding subsystem.

2.

Diesel Generator No. 2 flooding subsystem.

3.

Diesel Generator No. 3 flooding subsystem (common to both units).

4.

Cable spreading room flooding subsystem.

5.

C0 hose reel subsystem stations:

p LOCATION UNIT 1 UNIT 2 4 & 12 kV Switchgear Room No. 1 or 2 No. 13 or 14 Vital 4 kV Cable Spreading Rooms No. 3 or 4 No. 15 or 16 l

Vital 4 kV Switchgear Rooms No. 5 or 6 No. 17 or 18 Vital 480 V Load Centers F, G, and H No. 8 No. 9 Battery Rooms No. 10 No. 12 Rod Control Programmer Room No. 11 No. 11 5

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E DIABLO CANYON - UNITS 1 & 2 3/4 7-31 i

HANTSYSTEMS i

HALON SYSTEM 4

LIMITING CONDITION FOR OPERATION 3.7.9.4 The Protection and Safeguards Actuation System Room Halon System shall be OPERABLE.

APPLICABILITY: Whenever equipment protected by the Halon System is required to be OPERABLE.

ACTION:

a.

With the above required Halon System inoperable, within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months estab-lish a continuous fire watch with backup fire suppression equipment.

b.

The provisions of Specification 3.0.3 are not applicable.

l SURVEILLANCE REQUIREMENTS 4.7.9.4 The above required Halon System shall be demonstrated OPERABLE:

a.

At least once per 6 months by verifying Halon storage tank weight to be at least 95% of full charge weight and pressure to be at least 90%

of full charge pressure, l

b.

At least once per 18 months by:

1)

Verifying the system, including associated ventilation dampers, actuates manually and automatically, upon receipt of a simulated test signal, and 2)

Performance of a flow test through headers and nozzles to assure no blockage, c.

Prior to the expiration of its service life and at least once per 5 years by replacement of the explosive initiator with an explosive initiator from a certified manufacturing lot.

DIABLO CANYON - UNITS 1 & 2 3/4 7-32 Amendment Nos. 55 and 54 4

e

, PLANT $YSTEMS FIRE HOSE STATIONS LIMITING CONDITION FOR OPERATION 3.7.9.5 The fire hose stations shown in Table 3.7-4 shall be OPERABLE.

APPL 7CABILITY:

Whenever equipment in the areas protected by the fire hose stations is required to be OPERABLE.

p ACTION:

a.

With one or more of the fire hose stations given in Table 3.7-4 inoperable, route an additional equivalent capacity fire hose to the unprotected area (s) from an OPERABLE hose station within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months if the inoperable fire hose is the primary means of fire suppression; otherwise route the additional hose within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months , i

d.

The provisions of Specification 3.0.3 are not applicable.

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SURVEILLANCEREQUIROEjj'S 4.7.9.5 Each of the fire hose stations shown in Table 3.7-4 shall be demonstrated OPERt.PLE:

a.

At least once per 31 days, by visual inspection of the stations accessible during plant operations to assure all required equipment is at the station, b.

At least once per 18 months, by:

1)

Visual inspection of the stations not accessible during plant operations to assure all required equipment is at the station,-

2)

Removing the hose for inspection and re-racking, and 3)

Inspecting all gaskets and replacing any degraded gaskets in couplings.

c.

At least once per 3 years by:

1)

' Partially opening each hose station valve to verify valve OPERABILITY and no flow blockage.

2)

Conducting a hose hydrostatic test at a pressure of 300 psig or

.i at least 50 psig above the maximum fire main operating pressure, whichever is greater.

DIABLO CANYON - UNITS 1 & 2 3/4 7-33 Amendment Nos. 55 and 54

TABLE 3.7-4 FIRE HOSE STATIONS LOCATION ELEVATION IDENTIFICATION kyj UNIT 1 UNIT 2 Near Fence North of Main Bank 95 YL-S N.A.

Near Fence North of No. 1 Startup Bank.

85 YL-6 YL-8 Near Fence North of No. 2 Startup Bank for Unit 1 and South of No. 2 Startup Bank for Unit 2 85 YL-7 YL-19 Near Main Transformer 85 YL-9 YL-20 Between Main Transformer and Aux. Boiler 85 YL-10 N.A.

I South of Diesel Generator Rooms 85 N.A.

YL-18 2.

Auxiliary Building Near West End of Hall for Unit I and near East End of Hall for Unit 2 64 FW-Al-1 FW-A6-2' Outside RHR Pump Room 64 FW-A2-1 FW-A5-2 Near Containment Spray Pumps 73 FW-A8-1 FW-A10-2 Near No. 3 CCW Pump 73 FW-A7-1 FW-A9-2 Outside Letdown HX Room 85 FW-A14-1 FW-A16-2 Penetration Area Near Doorway to Secondary 85 FW-A11-1 FW-A17-2 Sample Room Fuel Handling Bldg. North of Door to Auxiliary Feedpumps for Unit 1 and South of Door to Auxiliary Feedpumps for Unit 2 100 FW-A21-1 FW-A30-2 Penetration Area 100 FW-A22-1 FW-A28 Penetration. Area 100 FW-A23-1 FW-A29-2 Near Door to VCT Room 100 FW-A24-1 FW-A26-2 North of Boric Acid Transfer Pumps for Unit 1 and South of Boric Acid Transfer Pumps for Unit 2 100 FW-A25-1 FW-A27-2 Penetration Area 115 FW-A?S-1 FW-A42-2 Penetration Area 115 FW-A36-1 FW-A41-2 Stairwell East of Cable Spreading Room (common to both units) 127 FW-A55-1 FW-A55-1 DIABLO CANYON - UNITS 1 & 2 3/4 7-34

TABLE 3.7-4 (Continued) f o

FIRE HOSE STATIONS LOCATION ELEVATION IDENTIFICATION UNIT 1 UNIT 2 3.

Containment Near Main Airlock 140 FW-C7-l' FW-C7-2 Near Equipment Hatch 140 FW-C6-1 FW-C6-2 Near Emergency Airlock 140 FW-C5-1 FW-CS-2 Near CFCU No. 1 140 FW-C8-1 FW-C8-2 Near ECCS Sump 91 FW-C3-1 FW-C3-2 135*, outer wall 91 FW-C2-1 FW-C2-2 4.

Turbine Building Between Diesels and 12/4 kV room 85 FW-T,49-1 FW-T52-2 Corridor outside Diesel Mufflers for Unit I and Near SW Evaporator for Unit 2 104 FW-T50-1 FW-T23-2 Near Unit 1 Passenger Elevator and near Unit 2 Freight Elevator 104 FW-T19-1 FW-T20-2 North of Switchgear Vent Fans for Unit I and' South of Switchgear Vent Fans for Unit 2 119 FW-T51-1 FW-T54-2 5.

Intake Structure Wall outside ASW Pump Room

(-) 2 FW-3-I2-1 FW-3-I3-2 l

I 6.

Fuel Handling Building L

Outside, near east entrance to Aux.

115 FW-A53-1 FW'A58-2 Building Filters Outside near entrance to Fuel Handling Building Filters for Unit I and inside Fuel Handling Building for Unit 2 140 FW-A52-1 FW-A51-2 l

DIABLO CANYON - UNITS 1 & 2 3/4 7-35 t

1 1

l 5

PLANT SYSTEMS 3/4.7.10 FIRE BARRIER PENETRATIONS LIMITING CONDITION FOR OPERATION 3.7.10 All fire barrier penetrations (including cable penetration barriers, fire doors, and fire dampers) in fire area boundaries protecting safety-related areas shall be functional.

APPLICABILITY: Whenever the equipment protected by the fire barrier penetrations is required to be OPERABLE.

ACTION:

With one or more of the above required fire barrier penetrations a.

non-functional, within I hour, either establish a continuous fire watch on at least one side of the affected penetration, or verify the OPERABILITY of fire detectors on at least one side of the non-functional fire barrier and establish an hourly fire watch patrol.

b.

The provisions of Specification 3.0.3 are not applicable.

l SURVEILLANCE REQUIREMENTS 4.7.10 Each of the above required fire barrier penetrations shall be verified to be-functional:

a.

At least once per'18 months by a visual inspection, and b.

Prior to returning a fire barrier penetration to functional status following repairs or maintenance by the performance of a visual inspection of the affected fire barrier penetrations.

DIABLO CANYON - UNITS 1 & 2 3/4 7-36 Amendment Nos 55 and 54

PLANT. SYSTEMS

,3/4.7.12 ULTIMATE HEAT SINK LIMITING CONDITION FOR OPERATION 3.7.12 The ultimate heat sink (VHS)* shall be OPERABLE with an inlet water temperature of less than or equal to 64'F.

APPLICABILITY:

MODES 1, 2, and 3.

l ACTION:

With the requirements of the above specification not satisfied, place a second

. vital component cooling water heat exchanger in service within 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 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 at-least HOT SHUTDOWN within the following 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months . The provisions of Specification 3.0.4 are not applicable.

SURVEILLANCE REQUIREMENTS a

L 4.7.12 The VHS shall be determined OPERABLE by verifying the inlet water tem-perture to be within its limit:

a.

At least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months when the inlet water temperature is equal to or less than 60*F, or b.

At least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months when the inlet water temperature is greater than 60'F but less than 62*F, or c.

At least once per 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months when the inlet water temperature is equal to or greater than 62 F but less than or equal to 64'F.

The UHS is common to both units.

DIABLO CANYON - UNITS 1 & 2 3/4 7-39

PLANT SYSTEMS

- 3/4.7.13 FLOOD PROTECTION LIMITING CONDITION FOR OPERATION 3.7.13 The full length of both breakwaters (east and west)* shall be above the mean lower low water (MLLW) level.

APPLICABILITY: MODES 1, 2, 3, and 4.

ACTION:

a.

With any of ehe breakwaters length reduced to less than MLLW 1evel, prepare and submit to the Commission within 90 days pursuant to Specification 6.9.2, a Special Report that includes the following information:

1.

Explanation of how the degradation occurred and if the breakwaters are continuing to degrade, 2.

A planned course of action to repair the damage and the schedule for accomplishing the repair, and 3.

Summary description of action (s) to be taken to prevent a recurrence.

I b.-

With 500 feet or more of the breakwater length reduced to less than MLLW 1evel, be in at least HOT STANDBY within 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 REQUIREMENTS 4.7.13.1 The breakwaters shall be visually inspected at least once per 31 days during the months of November through April and the full length of each shall be verified above MLLW 1evel.

4.7.13.2 The crest of the breakwaters shall'be visually inspected for settle-ment and displacement at least once per 12 months.

Photographs shall be taken during the inspection, from a s::fficient vantage point, to show the approximate condition of both breakwaters.

4.7.13.3 The results of any visual ins damage and the associated photograph (s)pection as well as surveys that detect shall be included in the May Monthly Operating Report in accordance with Specification 6.9.1.7.

Both breakwaters are common to both units.

DIABLO CANYON - UNITS 1 & 2 3/4 7-40 Amendment Nos. 55 and 54 1

, ELECTRICAL POWER SYSTEMS.

CONTAINMENT PENETRATION CONDUCTOR OVERCURRENT PROTECTIVE DEVICES LIMITING CONDITION FOR OPERATION 1

3.8.4.2 For each containment penetration provided with a containment penetra-tion overcurrent protective device (s), each device shall be OPERABLE.

APPLICABILIU:

MODES 1, 2, 3, and 4.

ACTION:

With one or more of the above required containment penetration conductor overcurrent protective device (s) inoperable:

Restore the protective device (s) to OPERABLE status or deenergize a.

the circuit (s) by tripping the associated protective device or racking out or removing the inoperable protective device within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months , declare the affected system or component inoperable, and verify the associated protective device to be tripped or removed, or the inoperable protective device racked out or removed at least once per 7 days thereafter; or I

b.

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 .

SURVEILLANCE REQUIREMENTS 4.8.4.2 Protective devices required to be operable as containment penetration overcurrent' protective devices shall be demonstrated OPERABLE:

a.

At least once per 18 months:

1)

By verifying that the medium voltage 12 kV circuit breakers are OPERABLE by selecting, on a rotating basis, at least 10% of the circuit breakers and performing the following:

a)

A CHANNEL CALIBRATION of the associated protective relays, b)

An integrated system functional test which includes simulated automatic actuation of the system and verifying that each relay and associated circuit breaker and overcurrent control circuit function as designed, and DIABLO CANYON - UNITS 1 & 2 3/4 8-23 Amendment Nos55 and 54 b

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., REFUELING OPERATIONS

3/4. 9. 7 CRANE TRAVEL - FUEL HANDLING BUILDING LIMITING CONDITION FOR OPERATION 3.9.7 Loads in excess of 2500 pounds

shall be prohibited from travel over fuel assemblies in the spent fuel pool.

APPLICABILITY: With fuel assemblies in the spent fuel pool.

ACTION:

With the requirements of the above specification not satisfied. place a.

- the crane load in a safe condition,

b..

The provisions of Specification 3.0.3 are not applicable.

l SURVEILLANCE REQUIREMENTS

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4.9.7 Loads shall be verified to be less than 2500 pounds prior to movement over fuel assemblies in the spent fuel pool, i

R The movable fuel handling building walls may travel over fuel assemblies in the. spent fuel pool.

DIABLO CANYON - UNITS 1 & 2 3/4 9-7 Amendment Nos. 55 and 54

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_,. REFUfLING OPERATIONS 3/4.9.9 CONTAINMENT VENTILATION ISOLATION SYSTEM LIMITING CONDITION FOR OPERATION 3.9.9 The Containment Ventilation Isolation System shall be OPERABLE.

APPLICABILITY:

During CORE ALTERATIONS or movement of irradiated fuel within i

containment.

ACTION:

a.

With the Containment Ventilation Isolation System inoperable, close each of the ventilation penetrations providing direct access from the containment atmosphere to the outside atmosphere, a

b.

The provisions of Specification 3.0.3 are not applicable.

l i

i SURVEILLANCE REQUIREMENTS 4.9.9 The Containment Ventilation Isolation System shall be demonstrated

.0PERABLE within 100 hours0.00116 days 0.0278 hours 1.653439e-4 weeks 3.805e-5 months prior to the start of and at least once per 7 days during CORE ALTERATIONS by verifying that containment ventilation isolation occurs on a High Radiation test signal from the plant vent noble gas activity monitoring instrumentation channels.

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DIABLO CANYON - UNITS 1 & 2 3/4 9-10 Amendment Nos. 55 and 54

.7 REFUELING OPERATIONS

,4 0

3/4.9.11 WATER LEVEL-- SPENT FUEL POOL.

j LIMITING CONDITION FOR OPERATION 3.9.11 At least 23 feet of water shall be maintained over the top of irradiated i

fuel assemblies seated in the storage racks.

I APPLICABILITY: Whenever irradiated fuel assemblies are in the spent fuel pool.

ACTION:

With the requirements of the above specification not satisfied, a.

suspend all movement of fuel assemblies and crane operations with loads in the fuel storage areas and restore the water level to within its-limit within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months , b.

The provisions of Specification 3.0.3 are not applicable.

l SURVEILLANCE REQUIREMENTS 4.9.11 The water level in the spent fuel pool shall be determined to be at least its minimum required depth at least once per 7 days when irradiated fuel i

assemblies are in the spent fuel pool.

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l DIABLO CANYON - UNITS 1 & 2 3/4 9-12 Amendment Nos. 55 and 54 w++

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REFUELING OPERATIONS 3/4.9.12 -FUEL' HANDLING BUILDING VENTILATION SYSTEM LIMITING CONDITION FOR OPERATION l

l-3.9.12 Two Fuel Handling Building Ventilation Systems shall be OPERABLE.

L APPLICABILITY: Whenever irradiated fuel is in the spent fuel pool.

ACTION:

R L

a.

With one Fuel Handling Building Ve dilation System inoperable, fuel movement within the spent fuel pool or crane operation with loads 1

over the spent fuel pool may proceed provided the OPERABLE Fuel Handling Building Ventilation System is capable of being powered from an OPERABLE emergency power source and is in operation and discharging through at least one train of HEPA filter:; and charcoal adsorbers, b.

With no Fuel Handling Building Ventilation System OPERABLE, suspend all operations involving movement of fuel within the spent fuel pool or crane operation with loads over the spent fuel pool until at least one Fuel Handling Building Ventilation System is restored to OPERABLE status, c.

The provisions of Specification 3.0.3 are not applicable.

SURVEILLANCE REQUIREMENTS 4.9.12 The above required Fuel Handling Building Ventilation Systems shall be demonstrated OPERABLE:

a.

At least once per 31 days by initiating-flow through the HEPA filters and charcoal adsorbers and verifying that the system operates for at least 15 minutes; u

b.

At least once per 18 months or (1) after any structural maintenance on the HEPA filter or charcoal adsorber housings, or (2) following painting, fire, or chemical release in any ventilation zone communi-cating with the system by:

1 1)

Visually verifying that, with the system operating at a flow rate of 35,750 cfm i 10% and exhausting through the HEPA filters and I

charcoal adsorbers, the damper valve M-29 is closed; l

2)

Verifying that the cleanup system satisfies the in place pene-tration and bypass leakage testing acceptance criteria of less l-

. than 1% and uses the test procedures guidance in Regulatory Positions C.S.a, C.S.c, and C.S.d of Regulatory Guide 1.52, Revision 2, March 1978, and the system flow rate is 35,750 cfm i 30%;

DIABLO CANYON - UNITS 1 & 2 3/4 9-13 Amendment Nos. 55 and 54

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REFUELING OPERATIONS l

SURVEILLANCE REQUIREMENTS (Continued) 3)

Verifying, within 31 days after removal, that a laboratory analysis of a representative carbon sample obtained in accor-dance with Regulatory Position C.6.b of Regulatory Guide 1.52, Revision 2, March 1978, meets the laboratory testing criteria of Regulatory Position C.6.a of Regulatory Guide 1.52, Revision 2, March 1978, for a methyl iodide penetration of less than 4.3%;

and 4)

Verifying a system flow rate of-35,750 cfm i 10% during system operation when tested in accordance with ANSI N510-1980.

c.

After every 720 hours0.00833 days 0.2 hours 0.00119 weeks 2.7396e-4 months of charcoal adsorber operation by verifying within 31 days after removal, that a laboratory analysis of a repre-sentative carbon sample obtained in accordance with Regulatory Position C.6.b of Regulatory Guide 1.52 Revision 2, March 1978, meets the laboratory testing criteria of Regulatory Position C.6.a of Regulatory Guide 1.52, Revision 2. March 1978, for a methyl-iodide penetration of less-than 4.3%;

d.

At least once per 18 months by:

1)

Verifying that the pressure drop across the combined HEPA filters and charcoal adsorber banks is less-than 4.1 inches

' Water Gauge while operating the system at a flow rate of 35,750 cfm i 10%,

2)

Verifying that on a high radiation test signal, the system automatically starts (unless already operating) and directs its exhaust flow through the HEPA filters and charcoal adsorber banks, and 3)

Verifying that the system maintains the spent fuel storage pool area at a negative pressure of greater than or equal to 1/8 inch Water Gauge relative to the outside atmosphere during system operation.

4.

After each complete.or partial replacement of a HEPA filter bank, by verifying that the cleanup system satisfies the in place penetration and bypass leakage testing acceptance criteria of less than 1% in accordance with ANSI N510-1980 for a 00P test aerosol while operating the system at'a flow rate of 35,750 cfm i 10%; and f.

After each complete or partial replacement of a charcoal adsorber bank, by verifying that the cleanup system satisfies the in place penetration and bypass leakage testing acceptance criteria of less than 1% in'accordance with ANSI N510-1980 for a halogenated hydro-carbon test gas while operating the system at a flow rate of 35,750 cfm i 10%.

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DIABLO CANYON - UNITS 1 & 2 3/4 9-14 l

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RADI0 ACTIVE EFFLUENTS DOSE LIMITING CONDITION FOR OPERATION i

3.11.1.2 The dose or dose commitment to a ME M ER OF THE PUBLIC from radioactive materials in liquid effluents released, from each unit, to UNRESTRICTED AREAS

-(see Figure 5.1-3) shall be limited:

a.

During any calendar quarter to less than or equal to 1.5 area to the whole bo(y and to less than or equal to 5 area to any organ, and b.

During any calendar year to less than or equal to 3 area to the whole body and to less than or equal to 10 area to any organ.

APPLICABILITY: At all times.

ACTION:

a.

With the calculated dose from the release of radioactive materials in liquid effluents exceeding any of the above limits, prepare and submit to the Commission within 30 days, pursuant to Specifica-tion 6.9.2, a Special Report that identifies the cause(s) for exceed-ing the. limits (s) and defines the corrective actions that have been taken to reduce the releases and the proposed corrective actions to be taken to assure that subsequent releases will be in compliance with the above limits, b.

The provisions of Specification 3.0.3 are not applicable.

l SURVEILLANCE P.EQ JIREMENTS 4.11.1.2 Cumulative dose contributions from liquid affluents'for the current calendar quarter and the current calendar year shall' be determined in accordance with the methodology and parameters in the ODCP at least once per 31 days.

DIABLO CANYON - UNITS 1 & 2 3/4 11-5 Amendment Nos. 55 and 54

RADI0 ACTIVE EFFLUENTS 4

LIQUID RADWASTE TREATMENT SYSTEM ~

LIMITING CONDITION FOR OPERATION 3.11.1.3 The Liquid Raowaste Treatment System

shall be OPERABLE and appropriate portions of the system shall be used to reduce the radioactive materials in liquid wastes prior to their discharge when the projected doses due to the liquid effluent, from each unit, to UNRESTRICTED AREAS (see Fig /6e 5.1-3) would exceed 0.06 area to the whole body or 0.2 arem to any organ in a 31-day period.

APPLICABILITY:

At all times.

ACTION:,

a.

With any portion of the Liquid Radwaste Treatment System not in opera-l tion and with radioactive liquid waste being discharged without treat-ment and in excess of the above limits, prepare and submit to the Com-mission within 30 days, pursuant to Specification 6.9.2, a Special Report which includes the following information:

i l

1.

Explanation of why liquid radwaste was being discharged without l

treatment, identification of any inoperable equipment or subsys-4 tems, and the reason for the inoperability, 2.

Action (s) taken to restore the inoperable equipment to OPERABLE status, and 3.

Summary description of action (s) taken to prevent a recurrence, b.

The provisions of Specification 3.0.3 are not applicable.

l SURVEILLANCE REQUIREMENTS 4.11.1.3.1 Doses due to liquid releases from each unit to UNRESTRICTED AREAS l

shall be projected at least once per 31 days, in accordance with the methodology l_

and parameters in the ODCP when Liquid Radwaste Treatment Systems are not being fully utilized.

L 4.11.1.3.2 The installed Liquid Radwaste Treatment System shall be considered OPERABLE by meeting Specifications 3.11.1.1 and 3.11.1.2.

l

The Liquid Radwaste Treatment System is common to both units.

DIABLO CANYON - UNITS 1 & 2 3/4 11-6 Amendment Nos. 55 and 54 o

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,.RADI0 ACTIVE EFFLUENTS

~ LIQUIDHOLDbPTANKS LIMITING CONDITION FOR OPERATION 3.11.1.4 The quantity of radioactive material contained in any te sporary outdoor tanks shall be limited to less than or equal to 10 curies, excluding tritium and dissolved or entrained noble gases.

APPLICABILITY: At all times.

ACTION:

a.

With the quantity of radioactive material in any of the temporary out-door tanks exceeding the above limit, immediately suspend all additions of radioactive material to the tank, within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months reduce the tank contents to within the limit, and describe the svents leading to this condition in the next Semiannual Radioactive Ef fluent Release Report, pursuant to Specification 6.9.1.6.

b.

The provisions of Specification 3.0.3 are not applicable.

l SURVEILLANCE REQUIREMENTS 4.11.1.4 The quantity of radioactive material contained in each of the temporary outdoor tanks shall be determined to be within the above limit by analyzing a representative sample of the tank's contents at-least once per 7 days when radioactive materials are being added to the tank.

DIABLO CANYON - UNITS 1 & 2 3/4 11-7 Amendment Nos. 55 and 54

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RADIOACTIVE EFFLUENTS 3/4.11.2 GASEOUS EFFLUENTS DOSE RATE LIMITING CONDITION FOR OPERATION 3.11.2.1 The dose rate due to radioactive materials released in gaseous efflu-ents from the site to areas at or beyond the SITE BOUNDARY (see Figure 5.1-3) shall be limited to the following:

a.

For noble gases:

Less than or equal to 500 arem/yr to the whole body and less than or equal to 3000 arem/yr to the skin, and b.

For Iodine-131, for Iodine-133, for tritium, and for all radionuclides in particulate form with half-lives greater than 8 days:

Less than or equal to 1500 mrem /yr to any organ.

-APPLICABILITY:

At all times.

ACTION:

With the dose rate (s) exceeding the above limits, immediately decrease the release rate to within the above limit (s).

SURVEILLANCE REQUIREMENTS 4.11.2.1.1 The dose rate due to noble gases in gaseous effluents shall be determined to be within the above limits in accordance with the methodology and procedures of the ODCP.

4.11.2.1.2 The dose rate due to Iodine-131, Iodine 133, tritium, and all -radio-nuclides in particulate form with half-lives greater than 8 days in gaseous effluents shall be determined to be within the abooe limits in accordance with

'the methodology and procedures of the ODCP by obta ning representative samples and performing analyses in accordance with the sampling and analysis program specified in Table 4.11-2.

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DIABLO CANYON - UNITS 1 & 2 3/4 11-8

TABLE 4.11-2 (Continued)

TABLE NOTATIONS (Continued)

(4) Samples shall be changed at-least once per 7 days and analyses shall be completed within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months after changing or after removal from sampler.

Sampling shall also be performed at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months for at least 7 days following each shutdown, startup or THERMAL POWER change exceeding 15% of RATED THERMAL POWER within a 1-hour period and analyses shall be completed within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months of changing.

When samples collected for 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months are analyzed, the corresponding LLD's may be increased by a factor of 10.

This requirement does not apply if:

(1) analysis shows that the DOSE EQUIVALENT I-131 concentration in the reactor coolant has not increased more than a factor of 3; and (2) the noble gas monitor shows that effluent i

activity has not increased more than a factor of 3.

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(5) Tritium grab samples shall be taken at least once per 7 days from the ven-tilation exhaust from the spent fuel pool area, whenever spent fuel is in

, the spent fuel pool.

(6) The ratio ~of the sample flow rate to the sampled stream flow rate shall be known for the time period covered by each dose or dose rate calculation made in accordance with Specifications 3.11.2.1, 3.11.2.2, and 3.11.2.3.

(7) The principal gamma emitters for which the LLD specification applies include the following radionuclides:

Kr-87, Kr-88, Xe-133, Xe-133m, Xe-135, and Xe-138 in noble gas releases and-Mn-54, Fe-59, Co-58, Co-60, Zn-65, Mo-99, I-131, Cs-134, Cs-137, Ce-141, and Ce-144 in Iodine and particulate releases.

This list does not mean that only these nuclides are to be considered.

Other gamma peaks that are identifiable, together with those of.the above-nuclides, shall also be analyzed and reported in the Semiannual Radioactive Effluent Release Report pursuant to Specification 6.9.1.6 in the format j;

outlined in Regulatory Guide 1.21, Appendix B, Revision 1, June 1974.

(8) Grab samples shall be taken and analyzed at.least once per 31' days whenever there is flow through the steam generator blowdown tank.

Releases of radioiodines shall be= estimated based on secondary coolant concentration 3

and partitioning factors during releases or shall be measured.

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DIABLO CANYON - UNITS 1 & 2 3/4 11-11 i

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RADI0 ACTIVE EFFLUENTS DOSE - NOBLE GASES LIMITING CONDITION FOR OPERATION 3.11.2.2 The air dose due to noble gases. released in gaseous effluents, from

.each unit, to areas at or beyond the SITE BOUNDARY (see Figure 5.1-3) shall be limited to the following:

a.

During any calendar quarter:

Less than or equal to,5 mrad for gamma radiation and less than or equal to 10 mrad for beta radiation, and b.

During any calendar year:

Less than or equal to 10 mrad for gamma radiation and less than or equal to 20 erad for beta radiation.

APPLICABILITY:

At all times.

ACTION With the calculated air dose from radioactive noble gases in gaseous a.

effluents exceeding any of the above limits, prepare and submit to the Commission within 30 days, pursuant to Specification 6.9.2, a Special Report that identifies the cause(s) for exceeding the limit (s),

defines the corrective actions that have been taken-to reduce the releases and the proposed corrective actions to be taken to assure that subsequent releases will be in compliance with the above limits.

, b.

The provisions of Specification 3.0.3 are not applicable.

[

SURVEILLANCE REQUIREMENTS 4.11.2.2 Cumulative dose contributions for the current calendar quarter and current calendar year for noble gases shall be determined in accordance with' the methodology and parameters in the ODCP at.least once per 31 days.

DIABLO CANYON - UNITS 1 & 2 3/4 11-12 Amendment Nos. 55 and 54

l:

p, RADI0 ACTIVE EFFLUENTS h

MSE - IODINE-131.10 DINE-133. TRITIUM, AND RADI0 ACTIVE MATERIAL IN PARTICULATE.

E r0RM l

LIMITING CONDITION FOR OPERATION l

3.11.2.3 The dose to e MEMBER OF THE PUBLIC from Iodine-131. Iodine-133, L

tritium and all radionuclides in particulate form with half-lives greater than L

8 days in gaseous effluents released, from each unit, to areas at and beyond the SITE BOUNDARY (see Figure 5.1-3) shall be limited to the following:

a.

During any calendar quarter:

Less than or equal to 7.5 aren to any organ and, b.

During any calendar year: Less than or equal to 15 area to any organ.

APPLICABILITY:

At all times.

ACTION:

With the calculated dose from the release of Iodine-131 Iodine-133, a.

tritium, and radionuclides in particulate form with half-lives greater than 8 days, in gaseous effluents exceeding any of the above limits, prepare and submit to the Commission within 30 days, pursuant to l

Specification 6.9.2, a Special Report that identifies the cause(s) for exceeding the limit (s), defines the corrective actions that have been taken to reduce the releases and the proposed actions to be taken to assure that subsequent releases will be in compliance with the above limits, b.

The provisions of Specification 3.0.3 are not applicable.

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SURVEILLANCE REQUIREMENTS l

4.11.2.3 Cumulative dose contributions for the current calendar quarter and.

current calendar year for Iodine-131, Iodine-133, tritium, and radionuclides in particulate form with half-lives greater than 8 days shall be determined in accordance with the methodology and parameters in the 00CP at.least once per 31 days.

DIABLO CANYON - UNITS 1 & 2 3/4 11-13 Amendment Nos. 55 and 54

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l RADI0 ACTIVE EFFLUENTS GASE0US RADWASTE TREATMENT SYSTEM LIMITING CONDITION FOR OPERATION l

3.11.2.4 The GASEOUS RADWASTE SYSTEM and the VENTILATION EXHAUST TREATMENT SYSTEM shall be OPERABLE. The appropriate portions of these systems shall be used to reduce releases'of radioactivity when the projected doses in 31 days due te gaseous effluent releases, from each unit, to areas at and beyond the j

SITF BOUNDARY (see Figure 5.1-3), would exceed 0.2 mrad to air from gamma radiation or 0.4 mrad to air from beta radiation or 0.3 mrom to any organ of l-a MEMBER OF THE PUBLIC.

I l

APPLICABILITY: At all times.

ACTION:

l a.

With radioactive gaseous waste being discharged without treatment and in excess of the above limits, prepare and submit to the Commission within 30 days, pursuant to Specification 6.9.2, a Special Report that includes the following information:

1.

Identification of the inoperable equipment or subsystems and the reason for inoperability, 2.

Action (s) taken to restore the inoperable equipment to OPERABLE status, and 3.

Summary description of action (s) taken to prevent a recurrence, b.

The provisions of Specification 3.0.3 are not applicable.

l SURVEILLANCE REQUIREMENTS i

l 4.11.2.4.1 Doses due to gaseous releases from each unit to areas at and beyond the SITE BOUNDARY shall be projected at least once per 31 days, in accordance with the methodology and parameters in the ODCP when Gaseous Radwaste Treatment Systems are not being fully utilized.

4.11.2.4.2 The installed VENTILATION EXHAUST TREATMENT SYSTEM and GASEOUS

.RADWASTE SYSTEM shall be considered OPERABLE by meeting Specifications 3.11.2.1 and 3.11.2.2 or 3.11.2.3.

cw DIABLO CANYON - UNITS 1 & 2 3/4 11-14 Amendment Nos. 55 and 54

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,RADIDACTIVE EFFLUENTS EXPL0S!VE GAS MIXTURE

' LIMITING CONDITION FOR OPERATION

.)

3.11.2.5 The concentration of oxygen in the GASE00$ RADWASTE SYSTEM shall be limited. to less than or equal to 2% by volume whenever the hydrogen concentra-tion exceeds 4% by volume.

APPLICABILITY:

At all times.

' ACTION:

With the concentration of oxygen in the GASEOUS RADWASTE SYSTEM a.

greater than 2% by volume but less than or equal 4% by volume, reduce the oxygen concentration to the above limits-within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months .

b.

With the concentration of oxygen in the GASEOUS RADWASTE SYSTEM i

greater than 4% by volume and the hydrogen concentration greater than 4% by volume, immediately suspend all additions of waste gases to the system and reduce the concentration of oxygen to less than or equal to 4% by volume, then take ACTION a., above.

The provisions of Specification 3.0.3 are not applicable.

l c.-

SURVEILLANCE REQUIREMENTS 4.11.2.5 The concentration of hydrogen

and oxygen-in the GASE0US RADWASTE -

SYSTEM shall be determined to be within the above limits by monitoring the waste gases in the GASEOUS RADWASTE SYSTEM with the hydrogen and-continuous oxygen monitors required OPERABLE by Table 3.3-13 of Specification 3.3.3.10.

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If monitoring of the waste gases for hydrogen is not performed, the hydrogen concentration shall be assumed to be greater than 4% by volume.

DIABLO CANYON - UNITS 1 & 2 3/4 11-15 Amendment Nos. 55 and 54

RADI0 ACTIVE EFFLUENTS-GAS' STORAGE TANKS LIMITING CONDITION FOR OPERATION 3.11.2.6-The quantity of radioactivity contained in each gas decay tank shall be limited to less than or equal to 105 curies noble gases (considered as_Xe-133 equivalent).

APPLICABILITY: At all times.

ACTION:

With the quantity of radioactive material in any gas decay tank s.

exceeding the above limit, immediately suspend all additions of radioactive material to the tank,'within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months reduce the tank contents to within the limit, and describe the events leading to this condition in the next Semiannual Radioactive Effluent Release Report,-pursuant to Specification 6.9.1.6.

b.

The provisions of Specification 3.0.3 are not applicable.

l SURVEILLANCE REQUIREMENTS-4.11.2.6 The quantity of radioactive material contained in each gas decay tank shall be determined to be within the above limit at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months when radioactive' materials are being added to the tank.

DIABLO CANYON - UNITS 1 & 2 3/4 11-16 Amendment Nos. 55 and 54

RADI0 ACTIVE EFFLUENTS 3/4'.11.3' SOLID RADIDACTIVE WASTE LIMITING CONDITION FOR OPERATION J

3.11.3 Radioactive waste shall be solidified or dowatered in accordance with the PROCESS CONTROL PROGRAM to meet shipping and transportation requirements during transit, and disposal site requirements when received at the disposal

site, i

APPLICABILITY: At all times.

ACTION:

a.

With SOLIDIFICATION or dewatering not meeting disposal site and shipping and transportation requirements, suspend shipment of the inadequately processed wastes and correct the PROCESS CONTROL PROGRAM, the procedures and/or the Solid Waste System as necessary to prevent recurrence.

b.

With Solidification or dewatering not performed in accordance with the PROCESS CONTROL PROGRAM, test-the improperly processed waste in each container to ensure that it meets burial ground and shipping requirements and take appropriate administrative action to prevent recurrence.

c.

The provisions of Specification 3.0.3 are not applicable.

l SURVEILLANCE REQUIREMENTS 4.11.3 SOLIDIFICATION of at least one representative test specimen from at least every tenth batch of each type of wet radioactive wastes (e.g., filter sludges, spent resins, evaporator bottoms, boric acid solutions and sodium sulfate solutions) shall be verified in accordance with the PROCESS CONTROL PROGRAM:

a.

If any test specimen fails to verify SOLIDIFICATION, the SOLIDIFICATION of the batch under test shall be suspended-until such time as additional test specimens can be obtained, alternative SOLIDIFICATION parameters can be determined in accordance with the PROCESS CONTROL PROGRAM, and a subsequent test verifies SOLIDIFICATION.

SOLIDIFICATION of the batch may then be resumed using the alternative SOLIDIFICATION parameters determined by the PROCESS CONTROL PROGRAM; b.

If the initial test specimen from a batch of waste fails to verify SOLIDIFICATION, the PROCESS CONTROL PROGRAM shall provide for the collection and testing of representative test specimens from each consecutive batch of the same type of wet waste until at least three consecutive initial test specimens demonstrated SOLIDIFICATION.

THE PROCESS CONTROL PROGRAM shall be modified as required, as provided in Specification 6.13, to assure SOLIDIFICATION of subsequent batches of waste; and c.

With the installed equipment incapable of meeting Specification 3.11.3 or declared inoperable, restore the equipment to OPERABLE status or provide for contract capability to process wastes as necessary to satirfy all applicable transportation and disposal requirements.

DIABLO CANYON - UNITS 1 & 2 3/4 11-17 Amendment Nos. 55 and 54

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l RADI0 ACTIVE EFFLUENTS 3/4.11.4 TOTAL DOSE LIMITING CONDITION FOR OPERATION 3.11.4 The annual (calendar year) dose or dose commitment to any MEMBER OF THE PU3LIC due to releases of radioactivity and to radiation from uranium fuel cycle sources shall be ' limited to less than or equal to 25 areas to the whole body or any organ, except the thyroid, which shall be limited to less than or equal to 75 areas.

APPLICABILITY: At all times.

ACTION:

I a.

With the calculated doses from the release of radioactive materials in liquid or gaseous effluents exceeding twice the limits of Specifi-cation 3.11.1.2a., 3.11.1.2b., 3.11.2.2a., 3.11.2.2b., 3.11.2.3a., or 3.11.2.3b., calculations. shall be made including direct radiatien contributions from the units and from outside storage tanks to deter-mine whether the r. cove limits of Specification 3.11.4 have been exceeded.

If sv.:h is the case, prepare and submit to the Commission within 30 days, pursuant to Specification 6.9.2, a Special Report that defines t'.1e corrective action to be taken to reduce subsequent releases to p' event recurrence of exceeding the above limits and includes the schedule for achieving conformance with the above limits.

This Special Report, as defined in 10 CFR 20.405c, shall include an l'

analysis that estimates the radiation exposure (dose) to a MEMBER OF THE PUBLIC from uranium fuel cycle sources, including all effluent pathways and direct radiation, for the calendar year that includes the release (s) covered by this report.

It shall also describe levels of radiation and concentrations of radioactive material ~ involved, and the cause of the exposure levels or concentrations.

If the estimated dose (s). exceeds the above limits, and if the release condition result-ing in violation of 40 CFR Part 190 has not already been corrected, the Special Report shall include a request for a variance in accord-ance with the provisions of 40 CFR Part 190.

Submittal of the report is considered a timely request,.and a variance is granted until staff l-action on the request is complete.

b.

The provisions of Specification 3.0.3 are not applicable.

l SURVEILLANCE REQUIREMENTS 4.11.4.1 Cumulative dose contributions from liquid and gaseous effluents shall be determined in accordance with Specifications 4.11.1.2, 4.11.2.2, and 4.11.2.3, and in accordance with the methodology and parameters in the ODCP.

4.11.4.2 Cumulative dose contributions from direct radiation from the units and from outside storage tanks shall be determined in accordance with the methodology and parameters in the ODCP.

This requirement is applicable only under conditions. set forth in ACTION a. of Specification 3.11.4.

DIABLO CANYON - UNITS 1 & 2 3/4 11-18 Amendment Nos. 55 and 54

3/4.12 RADIOLOGICAL ENVIRONMENTAL MONITORING 3/4.12.1' MONITORING PROGRAM LIMITING CONDITION FOR OPERATION g

3.12.1. The Radiological Environmental Monitoring Program shall -be conducted as specit bd in Table 3.12-1.

APPLICABILITY:- At all times.

ACTION:

a.

With the Radiological Environmental Monitoring Program not being con-

_ ducted as specified in Table 3.12-1, prepare and submit to the Com-

?

mission, in the Annual Radiological Environmental Operating Report c

required by Specification 6.9.1.5, a description of the reasons for not conducting the program as required and the plans for preventing a recurrence.

b.

With the. level of radioactivity as the result of plant effluents in an environmental sampling medium at a specified location exceeding the reporting levels of Table 3.12-2 when averaged over any calendar quarter, prepare and submit to the Commission within 30 days, pursuant to Specification 6.9.2, a Special Report that identifies the cause(s) for exceeding the limit (s) and defines the corrective actions to be taken -to reduce radioactive effluents so that the potential annual y

dose

to a MEMBER OF THE PUBLIC is less than the calendar year limits y

of Specifications 3.11.1.2, 3.11.2.2, or 3.11.2.3.

When more than one of the radionuclides in Table 3.12-2 are detected in the sampling E

medium _this report shall be submitted if:

concentration (1) concentration (2)

... > 1. 0 reporting level (1)r, reporting level.(2),

When radionuclides-other than those in Table 3.12-2 are detected and are the result of plant effluents,'this report shall be submitted if the potential annual dose

to a MEMBER OF THE PUBLIC from all radio-nuclides is equal to or greater than the calendar year limits of Specifications 3.11.1.2,-3.11.2.2 or 3.11.2.3.

This report is not-required if the measured level of radioactivity was not the result of plant effluents; however, in such an event, the condition shall be reported and described in the Annual Radiological Environmental Operating Report required by Specification 6.9.1.5.

~

'The methodology and parameters used to estimate the potential annual dose to a MEMBER OF THE PUBLIC shall be indicated in this report, t

E 1

DIABLO CANYON - UNITS 1 & 2 3/4 12-1 a

RADIOLOGICAL ~ ENVIRONMENTAL MONITCRINC LIMITING CONDITION FOR OPERATION ACTION (Continued) c.

_With milk or vegetation samples not being performed as required by Table 3.12-1, identify specific locations for obtaining replacement-samples and add them within 30 days to the Radiological Environmental Monitoring Program given in the ERMP.

The specific locations from which samples were unavailable may then be deleted from the monitor-

- ing program.

Pursuant to Specification 6.14, submit in the next r

Semiannual Radioactive Effluent Release Report documentation for a change in the ERMP including a revised figure (s) and table for the ERMP reflecting the new location (s) with supporting information iden-tifying the cause of the unavailability of samples and justifying the selection of the new location (s) for obtaining samples.

d.

The provisions of Specification 3.0.3 are not applicable.

l-SURVEILLANCE REQUIREMENTS

'4.12.1' The radiological environmental monitoring samples shall be collected pursuant to Table 3.12-l' from the specific locations given in the table and i

figures in the ERMP, and shall be analyzed pursuant to the requirements of Table 3.12-1 and the detection capabilities required by Table 4.12-1.

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DIABLO CANYON - UNITS 1 & 2 3/4 12-2 Amendment Nos. 55 and 54

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TABLE 4.12-1 (Continued) l TABLE NOTATIONS (Continued) 4-It should be' recognized that the LLD is defined as an 3 oriori (before the fact) limit representing the capability of a esasurement system and not as an a posteriori (after the fact) limit for a particular measurement.

-Analyses shall be performed in such a manner that the stated LLDs will be achieved under-routine conditions.

Occasionally background fluctuations, unavoidable small sample sizes, the presence of interfering nuclides, or other uncontrollable circumstances may render these LLDs unachievable.

In such cases, the contributing factors shall be identified and described in the Annual Radiological Environmental Operating Report pursuant to Specification 6.9.1.5.

DIABLO CANYON - UNITS 1 & 2 3/4 12-11

RADIOLOGICAL ENVIRONMENTAL MONITORING 3/4.12.2 LAND USE CENSUS LIMITING CONDITION FOR OPERATION 3.12.2 A Land Use Census shall be conducted and shall identify within a distance of 8 km (5 miles) the location in each of the 16 meteorological sectors of the nearest milk animal, the nearest residence, and the nearest garden

of. greater than 50 m2 (500 ft*) producing broad leaf vegetation.

APPLICABILITY:

At all times.

-ACTI0h:

a.

With a Land Use Census identifying a location (s) that yields a cal-culated dose or dose commitment greater than the values currently being calculated in Specification 4.11.2.3, pursuant to Specifica-tion 6.9.1.6, identify the new location (s) in the next Semiannual Radioactive Effluent Release Report, b.

With a Land Use Census identifying a locatnon(s) that yields a calculated dose or dose commitment (via the same exposure pathway) 20% greater than at a location from which samples are currencly being obtained in accordance with Specification 3.12.1, add the new location (s) within 30 days to the Radblogical Environmental Moni-toring Program given in the ERMP.

Tne sampling location (s), exclud-ing the control station location, having the lowest calculated dose or dose commitment (s), via the same exposure pathway, may be deleted-from this monitoring program after October 31 of the year in which this Land Use Census was conducted.

Pursuant to Specification 6.14, submit in the next Semiannual Radioactive Effluent Release Report documentation for a change in the ERMP including a revised figure (s) and table (s) for the ERMP reflecting the new location (s) with informa-tion supporting the change in sampling locations.

c.-

The provisions of Specification 3.0.3 are not applicable.

l SURVEILLANCE REQUIREMENTS 4.12.2 The Land Use Census shall be conducted during the growing season at least once per 12 months using that information that will provide the best results, such as by a door-to-door survey, aerial survey, or by consulting local agriculture authorities. The results of the Land Use Census shall be included in the Annual Radiological Environmental Operating Report pursuant to Specification 6.9.1.5.

Broad leaf vegetation sampling of at least three different kinds of vegetation may be performed at the SITE BOUNDARY in each of two different direction sectors with the highest predicted D/Qs in lieu of the garden census.

Speci-fications for vegetation sampling in Table 3.12-1, Item 4.c., shall be followed, including analysis of control samples.

DIABLO CANYON - UNITS 1 & 2 3/4 12-12 Amendment Nos. 55 and 54 ee

RADIOLOGICAL ENVIRONMENTAL MONITORING 3/4.12.3 INTERLABORATORY COMPARISON PROGRAM LIMITING CONDITION FOR 0?! RATION 3.12.3 Analyses shall be perfttnned on all radioactive materials, supplied as part of an Interlaberatory Comparison Program that has been approved by the Cemission, that correspond to samples required by Table 3.12-1.

APPLICABit.ITY:

At all times.

ACTION, With analyses not being perfor*ed as required above, report the s.

corrective actions taken to preveni a recu +ence to the C, emission in the Annual Radiological Environmental Operating Repot', pursuant to Specification 6.9.1.5.

b.

The provisions of Specification 3.0.3 are not applicable.

l SURVEILLANCEREquIREMENTS 4.12.3 The Interlaboratory Comparison Program shall be described in the ERMP.

A summary of the results obtained as part of the above required Interlaboratory Cc%ssison Program shall be included in the Annual Radiological Environmental Operating Report pursuant to Specification 6.9.1.5.

l DIABLO CANYON - Uri!TS 1 & 2 3/4 12-13 Amendment Nos. 55 and 54

3/4.0 APPLICABILITY BA$ES The specifications for this section provide the general requirements

, applicable to each of the Limiting Conditions for Operation and surveillance Requirements within section 3/4.

In the event of a disagreement between the requirements stated in these Technical specifications and those stated in an applicable Federal Regulation or Act, the requirements stated in the applicable Federal Rwgulation or Act shall take precedence and shall be met except where a specific exemption to the regulation has been granted in the Technical Specifications or Facility License.

3.0.1 This specification establishes the Applicability statement within each individual specification as the requirement for when (i.e., in which OPERATIONAL MODES or other specified conditions) confomance to the Limiting Conditions for Operation is required for safe operation of the facility.

The ACTION requirements establish those remedial measures that amt be taken within specified time limits when the requirements of a Limiting Condition for Operation are not set. There' are two basic types of ACTION requirements.

The first specifies the remedial measures that pemit continued operation of the facility which is not further restricted by the time limits of the ACTION requirements.

In this case, confomance to the ACTION requirements provides an acceptable level of safety for unlimited continued operation as long as the ACTION requirements continue to be set.

The second type of ACTION requirement specifies a time limit in which conformance to the conditions of the Limiting Condition for Operation must be met. This time limit is the allowable outage time to restore an inoperable system or component to OPERABLE status or for restoring the parameters within specified limits.

If these actions are not completed within the allowable outage time limits, a shutdown is required to place the facility in a MODE or condition in which the specification no longer applies.

It is not intended that the shutdown portion of the ACTION requirements be used as an operational convenience which pemits removal of a redundant system (s) or component (s) from service.

The specified time limits of the ACTION requirements are applicable from the point in time it is Mentified that a Limiting Condition for Operation is not met.

The time limits of the ACTION requirements are also applicable when a system or component is removed from service for surveillance testing or inves-tigation of operational problems.

Individual specifications may include a specified time limit for the completion of surveillance Requirement when equipment is removed from service.

In this case, the allowable outage time limits of the ACTION requirements are applicable when this limit expires if the surveillance has not been completed. When a shutdown is required to comply with ACTION requirements, the plant may have entered a MODE in which a new specification becomes applicable.

In this case, the time limits of the ACTION requirements would apply from the point in time that the new specification becomes applicable if the requirements of the Limiting Condition for Operation are not met.

3.0.2 This specification establishes that noncompliance with a specifica-tion exists when the requirements of the Limiting Conditions for Operation are not met and the associated ACTION requirements have not been implemented within the specified time interval.

The purpose of this specification is to clarify that (1) implementation of the ACTION requirements within the specified time l

DIABLO CANYON - UNITS 1 & 2 8 3/4 0-1 Amendment Nos. 55 and 54 I

l

.I l

APPLICABILITY SAsE's l

interval constitutes compliance with a specification and (2) completion of the i

remedial measures of the ACTION requirements is not required when compliance I

with a Limiting Condition of Operation is restored within the time interval i

specified in the associated ACTION requi meents.

3.0.3 This specification establishes the shutdown ACTION requirements that must be implemented when a Limiting Condition for Operation is not met and the condition is not specifically addressed by the associated ACTION requirements.

i The purpose of this specification is to delineate the time limits for placing the unit in a safe shutdown MODE when plant operation cannot be maintained within the limits for safe operation defined by the Lietting Conditions for Operation and its ACTION requires,ents.

It is not intended that the shutdown portion of the ACTION requirements be used as an operational convenience which permits removal of redundant system (s) or component (s) from service. One hour is allowed to prepare for an orderly shutdown before initiating a change in plant operation.

This time pemits the operator to coordinate the reduction in electrical generation with the load dispatcher to ensure the stability and availability of the electrical grid.

The time limits specified to reach lower i

MODES of operation pemit the shutdown to proceed in a controlled and orderly manner that is well within the specified maximum cooldown rate and within the cooldown capabilities of the facility assuming only the minimum required 4

equipment is OPERABLE.

This reduces thermal stresses on com>onents of the primary coolant system and the potential for a plant upset tsat could challenge safety systems under conditions for which this specification applies.

If remedial measures permitting limited continued operation of the facility under the provisions of the ACTION requirements are completed, the shutdown may be terminated.

The time limits of the ACTION requirements are applicable from the point in time there was a failure to meet a Limiting Condition for Operation.

Therefore, the shutdown may be terminated if the ACTION requirements have been met or the time limits for the ACTION requirements have not expired, thus providing an allowance for the completion of the re.,uired actions.

The time limits of Specification 3.0.3 allow 37 hours4.282407e-4 days 0.0103 hours 6.117725e-5 weeks 1.40785e-5 months for the plant to be in the COLD SHUTDOWN MODE when a shutdown is required during the POWER MODE of operation.

If the plant is in a lower MODE of operation when a shutdown is required, the time limit for reaching the next lower MODE of operation applies.

However, if a lower MODE of operation is reached in less time than allowed, the total allowable time to reach COLD SHUTDOWN, or other applicable MODE, is not. reduced.

For example, if HOT STANDBY is reached in 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months , the time allowed to reach HOT SHUTDOWN is the next 11 hours1.273148e-4 days 0.00306 hours 1.818783e-5 weeks 4.1855e-6 months because the total time to i

reach HOT SHUTDOWN is not reduced from the allowable limit of 13 hours1.50463e-4 days 0.00361 hours 2.149471e-5 weeks 4.9465e-6 months .

Therefore, if remedial measures are completed that would permit a return to POWER operation, a penalty is not incurred by having to reach a lower MODE of operation in less than the total time allowed.

The same principle applies with regard to the allowable outage time limits of the ACTION requirements, if compliance with the ACTION requirements for one DIABLO CANYON - UNITS 1 & 2 B 3/4 0-la Amendment Nos. 55 and 54

l

. A>PLICABILITY BASES specification results in entry into a MDDE or condition of operation for another specification in which the requirements of the Limiting Condition for Operation are not met.

If the new specification becomes applicable in less time than specified, the difference may be added to the allowable outage time limits of the second specification. However, the allowable outage time limits of ACTION requirements for a higher MDDE of operation may not be used to extend tP -ilowable outane time that is applicable when a Limiting Condition for Opr dios. 's not met < n a lower MODE of operation.

T. 4 4 w. sown requirements of Specification 3.0.3 do not apply in MDDES 5 and 6 b t.e the ACTION requirements of individual specifications define the remedia) *sasures to be taken.

3.0.4 This specification establishes limitations on MODE changes when a Limiting Condition for Operation is not set.

It precludes placing the facility in a higher MODE of operation when the requirements for a Limiting Condition for Op2 ration are not met and continued noncompliance to these conditions would result in a shutdown to comply with the ACTION requirements if a change in MODES were permitted.

The purpose of this specification is to ensure that facility operation is not initiated or that higher MDDES of operation are not entered wher, corrective action is being taken to obtain compliance with a specification by restoring equipment to OPERABLE status or parameters to specified limits.

Compliance with ACTION requirements that permit continued operation of the facility for en unlimited period of time provides an acceptable level of safety for continued operation without regard to the status of the plant before or sfter a MODE change.

Therefore, in this case, entry into an OPERATIONAL MODE or other specified condition may be made in accordance with the provisions of the ACTION requirements.

The provisions of this specification should not, however, be interpreted as endorsing the failure to exercise good practice in restoring systems or components to OPERABLE status before plant startup.

When a shutdown is required to comply with ACTION requirements, the provisions of Specification. 3.0.4 do not apply because they would delay placing the facility in a lower MODE of operation.

DIABLO CANYON - UNITS 1 & 2 B 3/4 0-lb Amendment Nos. 55 and 54

APPLICABILITY i

l BASES i

J. 0. 5 This specification delineates the appli m ility of each specification i

to Unit 1 and Unit 2 operation.

4.0.1 This specification establishes the requirement that surveillances aust be performed during the OPERATIONAL MODES or other conditions for which i

i the requirements of the Limiting Conditions for Operation apply unless otherwise stated in an individual Surveillance Requirement.

The pu mose of this specification is to ensure that surveillances are perfomed to verify the l

operational status of systems and components and that parameters am within specified limits to ensure safe operation of the facility when the plant is in a MDDE or other specified condition for which the associated Limiting Conditions for Operation are applicable. Surveillance Requirements do not have to be perfomed when the facility is in an OPERATIONAL MDDE for which the requirements of the associated Limitino Condition for Operation do not apply unless otherwise specified.

The Survel11ance Requirements associated with a Special Test Exception are only applicable when the $pecial Test is used as an allowable exception to the requirements of a specification.

4.0.2 This specification establishes the conditions under which the specified time interval for Surveillance Requirements may be extended.

Item l

a. permits an allowable extension of the normal surveillance interval to l

facilitate surveillance scheduling and consideration of p?M operating conditions that may not be suitable for conducting the surntilance; e.c transientconditionsorotherongoingsurveillanceormaintenanceactivides.

Item b. limits the use of the provisions of ites a. to ensure that it is not used repeatedly to extend the surveillance interval beyond that specified.

Thelimitsof5pecification4.0.2arebasedonengineeringjudgementandthe l

recognition that the most probable result of any particular surveillance being i

performed is the verification of conformance with the Surveillance Requirements.

These provisions are sufficient to ensure that the reliability ensured through surveillance activities is not significantly degraded beyond that obtained from the specified surveillance interval.

l l

4.0.3 This specification establishes the failure to perform a l

Surveillance Requirement within the allowed surveillance interval, defined by the provisions of $)ecification 4.0.2 as a condition that constitutes a failure to meet the OPERABILITY requirements for a Limiting Condition for Operation.

Under the provisions of this specification, systems and components are assumed I

to be OPERABLE when Surveillance Re within the specified time interval.quirements have been satisfactorily performed However nothing in this provision is to be l

construed as implying that systems or compone,nts are OPERABLE when they are found or known to be inoperable although still meeting the Surveillance Requirements.

This specification also clarifies that the ACTION requirements are applicable when Surveillance Requirements have not been completed within the allowed surveil-lance interval and that the time limits of the ACTION requirements apply from the point in time it is identified that a surveillance has not been performed and not at the time that the allowed surveillance interval was exceeded.

Completion of the Surveillance Requirement within the allowable outage time limits of the ACTION requirements restores compliance with the requirements of Specification 4.0.3.

I I

DIABLO CANYON - UNITS 1 & 2 B 3/4 0-2 Amendment Nos. 55 and 54

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- APPLICABILITY BASES If the allowable outage time limits of the ACTION requirements are less than 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months or a shutdown is required to comply with ACTION requirements, e.g., specification 3.0.3, a 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months allowance is provided to permit a delay in implementing the ACTION requirements. This provides an adequate time limit to complete Surveillance Requirements that have not been performed.

The purpose of this allowance is to permit the completion of a surveillance before a shutdown is required to comply with ACTION requirements or before other remedial asasures would be required that may preclude completion of a surveillance. The basis for this allowance includes consideration for plant conditions, adequate planning, availability of personnel, the time required to perfo m the surveillance, and the safety significance of the delay in completing the required surveillance.

This provision also provides a time limit for t w completion of Surveillance Requirements that become applicable as a consequence of MODE changes imposed by ACTION requirements and for completing Surveillance Requirements that are applicable when an exception to the requirements of Specification 4.0.4 is allowed.

If a surveillance is not completed within the 24-hour all ance, the time limits of the ACTION requirements are applicable at that time, en a surveillance is performed within the 24-hour allowance and the Surveill nee Requirements are not met, the time limits of the ACTION requirements are applicable at the time that the surveillance is terminated.

Surveillance Requirements do not have to be performed on inoperable equi ment because the ACTION requirements define the remedial measures that apply.p-However,le equipment has been restored to OPERABLE status.the Surveillance Require inoperab DIABLO CANYON - UNITS 1 & 2 B 3/4 0-2a Amendment Nos. 55 and 54 m.m__..__--_m

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APPLICABILITY BASES 1

l 4.0.4. This specification establishes the requirement that all applicable surveillances must be met before entry into an OPERATIONAL MDDE or etwr condition of operation specified in the Applicability statement.

The of this specification is to ensure that systes and component OPERABILIgrpose requirements or parameter limits are met before entry into a MODE or condition for which these systems and components ensure safe operation of the facility.

1 This provision applies to changes in OPERATIONAL MDDES or other specified l

conditions associated with plant shutdown as well as startup.

Under the provisions of this s Requirements must be perframed with$cification the applicable Surveillance the specified surveillance interval to ensure that the Limiting Conditions for Operation are set during initial plant startup or following a plant outage.

l When a shutdown is required to comply with ACTION requirements, the provisions of Specification 4.0.4 do not apply because this would delay placing the facility in a lower MODE of operation.

4.0.5 This specification establishes the requirement that inservice inspection of ASME code Class 1 2 and 3 cosponents and inservice testing of ASME Code Class 1 2 and 3 pumps, an,d valves stall be performed in accordance 1

withaperiodicallyupdatedversioofSectionXIoftheASMEBoilerand Pressure Vessel Code and Addenda as required by 10 CFR 50.55a.

These requirements apply except when relief has been provided in writing by the Commission.

This specification includes a clarification of the frequencies for l

perfoming the inservice inspection and testing activities required by Section XI of the ASME Boiler and Pressure Vessel Code and applicable Addenda.

This clarification is provided to ensure consistency in surveillance intervals throughout the Technical Specifications and to remove any ambiguities relative to the frequencies for performing the required inservice inspection and testing activities.

Under the terms of this specification, the more restrictive requirements of the Technical Specifications take precedence over the ASME Boiler and Pressure Vessel Code and applicable Addenda.

The re utrements of Specification 4.0.4 to perform surveillance activities before ont into an OPERATIONAL MODE or other specified condition takes precedence over e ASME Boiler and Pressure Vessel Code provision which allows pumps and valves to be tested up to one week after return to normal operation.

The Technical Specification definition of OPERABLE does not allow a grace period before a component, that is not capable of per-forming its specified function, is declared inoperable and takes precedence over I

the ASME Boiler and Pressure Vessel Code provision which allows a valve to be incapable of performing its specified function for up to 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months before being declared inoperable.

4.0.6 This specification delineates the appitcability of the surveillance activities to Unit 1 and Unit 2 operations.

DIABLO CANYON - UNITS 1 & 2 B 3/4 0-3 Amendment Nos. 55 and 54 w,

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