Text

Amends 118 & 116 to Licenses DPR-80 & DPR-82,respectively, Revising Combined TS for Plant to Revise 30 TS & Add Two New TS SRs to Support Implementation of Extended Fcs
	ML20138B606
Person / Time
Site:	Diablo Canyon
Issue date:	04/14/1997
From:	Steven Bloom; NRC (Affiliation Not Assigned)
To:	;
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ML20138B617	List: ML20138B606;
References
	NUDOCS 9704290219
	Download: ML20138B606 (40)
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i M #Cc UNITED STATES y

j NUCLEAR REGULATORY COMMISSION g

WASHINGTON. D.C. 305NHmoi o

+4 * * * *

f PACIFIC GAS AND ELECTRIC COMPANY 00.CKET NO. 50-275 DIABLO CANYON NUCLEAR POWER PLANT. UNIT NO. 1 l

AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.118 License No. DPR-80

-1.

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

A.

The application for amendment by Pacific Gas and Electric Company (the licensee) dated February 14, 1996, as supplemented by letter dated February 24, 1997, complies with the standards and requirements of the Atomic Energy Act of 1954,. as amended (the Act), and the Comission's regulations set forth in 10 CFR Chapter I; B.

The facility will operate in conformity with the application, the

)

provisions of the Act, and the rules and regulations of the 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 sot be inimical to the common 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 amendment, and paragraph 2.C.(2) of Facility Operating License.No. DPR-80 is hereby amended to read as follows:

9704290219 970414 PDR ADOCK 05000275 P

PDR

7

=

(2)

Technical Soecifications i

The Technical Specifications contained in Appendix A and the Environmental Protection Plan contained in Appendix B, as revised through Amendment No. 118, are hereby incorporated in the license.

Pacific Gas and 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 is effective as of its date of issuance to be implemented within 90 days of the date of issuance.

FOR THE NUCLEAR REGULATORY COMMISSION Steven D. Bloom, Project Manager i

Project Directorate IV-2 Division of Reactor Projects III/IV i

Office of Nuclear Reactor Regulation

]

Attachment:

Changes to the Technical Specifications Date of Issuance:

April 14, 1997 k

pmat;p t

UNITED STATES g

g j

NUCLEAR REGULATORY COMMISSION WASHINGTON. D.C. 20666 0001 l

'+9 * * * * +,o PACIFIC GAS AND ELECTRIC COMPANY DOCKET NO. 50-323 DIABLO CANYON NUCLEAR POWER PLANT. UNIT NO. 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 116 License No. DPR-82 1.

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

A.

The application for amendment by Pacific Gas and Electric Company (the licensee) dated February 14, 1996, as supplemented by letter dated February 24, 1997, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Comission's regulations set forth it.10 CFR

~

Chapter I; B.

The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; 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 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 amendment, and paragraph 2.C.(2) of Facility Operating License No. DPR-82 is hereby amended to read as follows:

~

(2)

Technical Soecifications The Technical Specifications contained in Appendix A and the Environmental Protection Plan contained in Appendix.B, as revised through Amendment No.116, are hereby incorporated in the license.

Pacific Gas and 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 is effective as of its date of issuance to be implemented within 90 days of the date of issuance.

FOR THE NUCLEAR REGULATORY COMMISSION Steven D. Bloom, Project Manager Project Directorate IV-2 Division of Reactor Projects III/IV Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical Specifications Date of Issuancei April 14, 1997 l

e

1

)

ATTACHMENT TO LICENSE AMENDMENTS AMENDMENT NO.118 TO FACILITY OPERATING LICENSE NO. DPR-80 AND AMENDMENT NO.116 TO FACILITY OPERATING LICENSE NO. DPR-82 DOCKET NOS. 50-275 AND 50-323 Revise Appendix A Technical Specifications by removing the pages identified below and inserting the enclosed pages. The revised pages are identified by Amendment number and contain marginal lines indicating the areas of change.

The corresponding overleaf pages are also provided to maintain document completeness.

]

REMOVE INSERT 1-8 1-8 3/4 1-19 3/4 1-19 3/4 1-20 3/4 1-20 3/4 3-10 3/4 3-10 3/4 3-11 3/4 3-11 3/4 3-12 3/4 3-12 3/4 3-32 3/4 3-32 3/4 3-33 3/4 3-33 3/4 3-34 3/4 3-34 3/4 3-35 3/4 3-35 3/4 4-9 3/4 4-9 3/4 4-20 3/4 4-20 3/4 5-5 3/4 5-5 3/4 5-6 3/4 5-6 3/4 6-10 3/4 6-10

' 3/4 6-12

~

3/4 6-12 3/4 6-14

~ ~ ~ _

3/4 6-14 3/4 6-15 3/4 6-15 3/4 6-18 3/4 6-18 3/4 7-5 3/4 7-5 3/4 7-9a 3/4 7-9a 3/4 7-11 3/4 7-11 3/4 7-12 3/4 7-12 B 3/4 0-2 B 3/4 0-2 l

l

?

4 TABLE 1.1 i

FRE0VENCY NOTATION NOTATION FRE0VENCY r

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

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

W At least once per 7 days.

l M

At least once per 31 days.

Q At least once per 92 days.

SA At least once per 184 days.

P At least once per 18 months.

.24, REFUELING At least once per 24 months.

INTERVAL S/U Prior to each reactor startup.

P Completed prior to each release.

N.A.

Not applicable.

1 DIABLO CANYON - UNITS 1 & 2 1-8 Unit 1 - Amendment No.118 Unit 2 - Amendment No.116

..1

REACTIVITY CONTROL SYSTEMS POSITION INDICATION SYSTEM - SHUTDOWN LIMITING CONDITION FOR OPERATION 3.1.3.3 One digital rod position indicator (excluding demand position indication) shall be OPERABLE and capable of determining the control rod position within i 12 steps for each shutdown or control rod not fully inserted.

APPLICABIllll:

MODES 3*#, 4*# and 5*#.

ACTION:

With less than the above required position indicator (s) OPERABLE, immediately open the Reactor Trip System breakers.

SURVEIllANCERE0VIpEMENTS 4.1.3.3 Each of the above required digital rod position indicator (s) shall be determined to be OPERABLE by verifying that the digital rod position indicators agree with the demand position indicators within~12 steps when exercised over the full range of rod travel at least once each REFUELING INTERVAL.

1

-l

With the Reactor Trip System breakers in the closed position.

See Special Test Exceptions Specification 3.10.4.

DIABLO CANYON - UNITS 1 & 2 3/4 1-19 Unit 1 - Amendment No.118 Unit 2 - Amendment No.116

~

REACTIVITY CONTROL SYSTEMS R0D DROP TIME LIMITING CONDITION FOR OPERATION 3.1.3.4 The individual full-length shutdown and control rod drop time from

.the fully withdrawn position shall be less than or equal to 2.7 seconds from beginning of decay of stationary gripper coil voltage to dashpot entry with:

a.

Tm greater than or equal to 541*F, and b.

All reactor coolant pumps operating.

APPLICABILITY:

MODES 1 and 2.

ACTION:

With the drop time of any full-length rod determined to exceed the above limit, restore the rod drop time to within the above limit prior to proceeding to MODE 1 or 2.

SURVEILLANCE RE0VIREMENTS 4.1.3.4 The rod drop time of full-length rods shall be demonstrated through measurement prior to reactor criticality:

a.

For all rods following each removal of the reactor vessel head, b.

For specifically affected individual rods following any maintenance on or modification to the Control Rod Drive System which could affect tne drop time of those specific rods, and c.

At least once each REFUELING INTERVAL.

l DIABLO CANYON - UNITS 1 & 2 3/4 1-20 Unit 1 - Amendment No. M 772,118 Unit 2 - Amendment No. 3GrM,116

~

TABAE 3.3-2 (Continued)

REACTOR TRIP SYSTEM INSTRUMENTATION RESPONSE TIMES i

g.

FUN"*10NAL 6 NIT RESPONSE TIME

~7.

Turtine Trip 1

a.

Low Fluid Oil Pressure N. A.

t.

Turbine Stop Valve N. A.

If.

Safety Injection Input from ISF N.A.

29.

Reactor Coolant Pump Breaker Position Trip N.A.

2C, Reactor Trip Breakers N. A.

22.

Autor.atic Trip and Interlock Logic N.A.

22 Ree:ter Trip Syster Ir.terlocks N.A.

23.

Seis-ic Trip h.A.

I

(

T DIABLO CANYON - UNITS 1 & 2-3/4 3-9

TABLE 4.3 l 4

REACT 0P, TRIP SYSTEM INSTRUMENTATION SURVEILLANCE REQUIREMENTS-TRIP ACTUATING MODES FOR o

CHANNEL DEVICE WHICH n

E CHANNEL CHANNEL OPERATIONAL OPERATIONAL ACTUATION SURVEILLANCE.

. y FUNCTIONAL UNIT CHECK CALIBRATION TEST TEST LC3IC TEST-IS REQUIRED

1.. Manual Reactor Trip N.A.

N.A.

R24(14)

N.A.

1,2,3*,4*,5*.-l zZ 2.

Power Range, Neutron Flux a.

High Setpoint S

D(2, 4),

Q N.A.

N.A.

1, 2

~

M(3, 4),

Q(4, 6),

R(4, 5) b.

Low Setpoint S

R(4)

S/U(1)

N.A.

l###, 2 3.

Power Range, Neutron Flux, N.A.

R(4)

Q N.A.

N. A.'

1, 2 y

High Positive Rate

=

w 4.

Power Range, Neutron Flux, N.A.

R(4)

Q N.A.

N.A.

1, 2 -

h High Negative Rate 5.

Intermediate Range, S

R(4, 5)

S/U(1)

N.A.

1###, 2 Neutron Flux

6. Source Range, Neutron Flux S

R(4,5)

S/U(1),Q(8)

N.A.

2##, 3, 4, 5

7. Overtemperature AT S

R Q

N.A.

1, 2

{ {

8.

Overpower aT S

R Q

N.A.

1, 2 9.

Pressurizer Pressure-Low S

R Q

N.A.

1 oo[ [

10. Pressurizer Pressure-High S

R Q

N.A.

1, 2 OO(

11. Pressurizer Water Level-High S R

Q N.A.

N.A.

1 m

12. Reactor Coolant Flow-Low S

R Q

N.A.

1 m

.m.. r.-

m

-w-e

TABLE 4.3-1 REACTOR TRIP SYSTEM INSTRUMENTATION SURVEILLANCE REQUIREMENTS S

B TRIP 5

ACTUATING MODES FOR CHANNEL DEVICE

WHICH n-E -

CHANNEL CHANNEL OPERATIONAL 0PERATIONAL ACTUATION SURVEILLANCE y FUNCTIONAL UNIT CHECK CALIBRATION TEST-TEST LOGIC TEST IS REQUIRED

' '13. Steam Generator Water Level -

E-Low-Low a.

Steam Generator S

R Q

N.A.

1, 2

~

Water Level-Low-Low b.

RCS Loop AT N.A.

R Q

N.A.

1, 2

14. DELETED

15. Undervoltage-Reactor N.A.

R N.A.

Q N.A.

I w

1 Coolant _ Pumps w

.L

16. Underfrequency-Reactor N.A.

R N.A.

Q N.A.

I

~

Coolant Pumps E E 17. Turbine Trip 33 a.

Low Fluid Oil Pressure N.A.

N.A.

S/U(1, 9)

N.A.

1-b.

Turbine Stop Valve N.A.

N.A.

S/U(1, 9)

N.A.

1

~~

i i Closure

e z-55

18. Safety Injection Input N.A, N.A.

N.A.

R24 N.A 1, 2 l

EE from ESF 55 E E 19. Reactor Coolant Pump N.A.

N.A.

R24 N.A.

'l l

g:g:

Breaker Position Trip

20. Reactor Trip System Interlocks o m

-P!

a.

Intermediate Range N.A.

R(4)

R N.A.

N.A.

2##

U$

Neutron Flux, P-6 lol o b.

Low Power Reactor E

Trips Block, P-7 N.A.

R(4)

R N.A.

N.A.

1

g c.

Power Range Neutron Flux, P-8 N.A.

R(4)

R N.A.

N.A.

1

TABLE 4.3-1 REACTOR TRIP SYSTEM INSTRUMENTATION SURVEILLANCE REQUIREMENTS-2 E

TRIP G

ACTUATING MODES FOR n

CHANNEL DEVICE WHICH E

CHANNEL CHANNEL OPERATIONAL OPERATIONAL ACTUATION SURVEILLANCE Ei FUNCTIONAL UNIT CHECK CALIBPATION TEST TEST LOGIC TEST

-IS REQUIRED z

20. Reactor Trip System Interlocks E

(Continued) d.

Power Range Neutron

~

Flux, P-9 N.A.

R(4)

R N.A.

N.A.

1 e.

Low Setpoint Power Range Neutron Flux, P-10 N.A.

R(4)

R N.A.

N.A.

1, 2 f.

Turbine Impulse Chamber Pressure, P-13 N.A.

R R

N.A.

1

21. Reactor Trip Breaker N.A.

N.A.

M(7, 10)

N.A.

1,2,3*,4*,5*

w

22. Automatic Trip and N.A.

N.A.

M(7) 1,2,3*,4*,5*

w g

Interlock Logic

23. Seismic Trip N.A.

R N.A.

R R

1, 2

24. Reactor Trip Bypass N.A N.A.

N.A.

M(7,15),R24(16)N.A.

1,2,3*,4*,5*

l 1

ccgy Breaker ro -

1 I aa ER aa

.F.F

)3)E er cn co

.. ~

TABLE 3.3 5 fcanti M TABLE IM ATIW15 (1) Diesel generator starting delay not included because offsite power available.

!(

(2) Notation deleted.

l (3) Diesel generator starting and loading delays included.

Diesel generator starting delay not included because offsite (4)

Response time limit includes opening of valves to establish $powr is eve 11able.

1 path and attairewnt of discharge pressure for centrifuge 1 charging pulps (ediere applicable). Seguen.

l tial transfer of charging pump suction from the VCT to the 4157 (415T valves spen.

then VCT valves close) is included.

(5) Diesel generator starting and sequence loading delays included. Offsite pa a r is not available. Response time limit includes opening of valves to establish $1 path and attainment of discharge pressure for contrifugal chargi Sequential transfer of charging pump suction from the VCT to the Ef5T (

valves open, then 1

VCT valves close) is included.

(6) The maximum response time of 48.5 seconds is the tiaz h when the containment pressure exceeds the High Nigh Setpoint until the spray pump is started and the discharge valve travels to the fully open position assuming off site power is not available. The time of 48.5 seconds includes the 28 second maximum delay related to ESF loading sequence. Spray riser piping fill time is not included. The 80-

]

second maximum spray delay time does not include the time from LOCA start to *P*

signal.

(7) Diesel generator starting and sequence loading delays included. Sequeritial trans-fer of charging pump suction from the VCT to the Ef5T (Ed5T valves open, then VCT valves close) is not included. Response time limit includes opening of valves to establish 51 flow path ar4 attainment of discharge pressure for centrifugal l

charging pumps. SI. and R$ pumps (where applicable).

(8) Does not include Trip Time Delays. Response times include the transmitters. Eagle-21 Process Protection cabinets. Solid State Protection System cabinets and actus-1 tion devices only. This reflects the response times necessary for TIERMAL PGdER in excess of 502 RTP.

i DIABLO CANYON LS11TS 1 & 2 3/4 3 31 AmendmentNos.3g&60.fe&N.

M & 83

^

TABLE 4.3-2 ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION o

SURVEILLANCE REOUIREMENTS E

TRIP ACTUATING 9

CHANNEL DEVICE MODES FOR 5

CHANNEL OPERA-CPERA-MASTER SLAVE WHICH CHANNEL CALI-TIONAL TIONAL ACTUATION RELAY RELAY SURVEILLANCE i

FUNCTIONAL UNIT CHECK BRATION TEST TEST LOGIC TEST TEST J1Sl_

IS REOUIRED Ci'i

1. Safety Injection, (Reactor Trip d

Feedwater Isolation, Start Diesel Generators, Containment Fan Cooler Units, and Component e.

Cooling Water) m a.

Manual Initiation N.A.

N.A.

R24 N.A.

N.A.

1, 2, 3, a l

b.

Automatic Actuation N.A.

N.A.

M(1)

R 1, 2, 3, 4 Logic and Actuation Relays m

b c.

Containment Pressure-High S

R Q

N.A.

1, 2, 3, 4 d.

Pressurizer Pressure-Low S

R Q

N.A.

1, E, 3 e.

DELETED cc oa??

f.

Steam Line S

R Q

N.A.

1, 2, 3 l

ro -

Pressure-Low I I g k

. Containment Spray (coincident 2

3 with SI signal)

EE a.

Manual Initiation N.A.

N.A.

R N.A.

N.A.

1, 2, 3, 4 88

%a b.

Automatic Actuation Logic N.A.

N.A.

M(1)

R 1, 2, 3, 4 and Actuation Relays 22

<n<n c.

Containment Pressure-S R

Q N.A.

N.A.

1, 2, 3, 4 P!

High-High 32

)E)E i ?

wui aa en w

TABLE 4.3-2 (Continued)

ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION SURVEILLANCE REQUIREMENTS c3 T.!"

TRIP ACTUATING 9

CHANNEL DEVICE MODES FOR 5

CHANNEL OPERA-OPERA-MASTER SLAVE WHICH CHANNEL CALI-TIONAL TIONAL ACTUATION RELAY RELAY SURVEILLANCE FUNCTIONAL UNIT CHECK BRATION TEST TEST LOGIC TEST TEST TEST IS RE0VIRED i

C5

3. Containment Isolation d

a.

Phase "A" Isolation

1) Manual N.A.

N.A.

R24 N.A.

N.A.

1, 2, 3, 4 l

2) Automatic Actuation N.A.

N.A.

M(1)

R 1, 2, 3, 4 n.

Logic and Actuation m

Relays R

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

b.

Phase "B" Isolation i'

1) Manual N.A.

N.A.

R24 N.A.

N.A.

1, 2, 3, 4 l 0

2) Automatic Actuation N.A.

N.A.

M(1)

R 1, 2, 3, 4 Logic and Actuation cc

". 3.

Relays 3)

Containment S

R Q

N.A.

1, 2, 3, 4 Pressure-High-High c.

Containment Ventilation

((

Isolation c

1) Automatic Actuation N.A.

N.A.

M(1)

R 1, 2, 3, 4 ss gy Logic and Actuation s@

Relays

2) Deleted

!3 R 3)

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

4)

Containment Ventilation iol o f N Exhaust Radiation-High i

lE!E (RM-44A and 448)

S R

Q N.A.

N.A.

1, 2, 3, 4 LL S!$

LL l3l3 LL I

TABLE 4.3-2 (Continued)

ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION SURVEILLANCE REQUIREMENTS c2 57p TRIP o

ACTUATING 9

CHANNEL DEVICE MODES FOR CHANNEL OPERA-OPERA-MASTER SLAVE WHICH CHANNEL CALI-TIONAL TIONAL ACTUATION RELAY RELAY SURVEILLANCE FUNCTIONAL UNIT CHECK BRATION TEST TEST LOGIC TEST TEST TEST IS REQUIRED C5

4. Steam Line Isolation a.

Manual N.A.

N.A.

R24 N.A.

N.A.

1, 2, 3 l

U

[

b.

Automatic Actuation Logic N.A.

N.A.

U M)

R 1, 2, 3 M) and Actuation Relays m

c.

Containment Pressure-S R

Q N.A.

N.A.

1, 2, 3 High-High wi d.

Steam Line Pressure-Low S

R Q

N.A.

1, I, 3 y

e.

Negative Steam Line S

R Q

N.A.

6' g

Pressure Rate-High

5. Turbine Trip and Feedwater

. cc E. =

Isolation

[

M)

M")

R 1, 2 U

a.

Automatic Actuation N.A.

N.A.

Logic and Actuation Relays b.

Steam Generator Water S

R Q

N.A.

1, 2

>k Level-High-High g

EE gg

6. Auxiliary Feedwater 55 a.

Manual N.A.

N.A.

R N.A.

N.A.

1, 2, 3

,n n

o iol b.

Automatic Actuation N.A.

N.A.

M")

R 1, 2, 3 o

{f Logic and Actuation Relays 2333 Steam Generator Water c.

Level-Low-Low FJah 0

1)

Steam Generator S

R Q

N.A.

1, 2, 3 )

Water Level-Low-Low uugg 2)

RCS Loop AT N.A.

R Q

N.A.

1, 2 6

+

e v-t-

v-

-+-

.-m.

m m

.. 2

..u..

.m -

TABLE 4 3-2 (Continued)

ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION.

SURVEILLANCE REQUIREMENTS S

TRIP 5

ACTUATING CHANNEL DEVICE MODES FOR n

R CHANNEL OPEPA-OPERA-MASTER SLAVE WHICH g

CHANNEL CALI-TIONAL TIONAL ACTUATION RELAY RELAY SURVEILLANCE F_UNCTIONAL UNIT CHECK BRATION TEST TEST LOGIC TEST TEST TEST IS REQUIRED Z

E

6. Auxiliary Feedwater (Continued)

~-e d.

Undervoltage - RCP N.A.

R N.A.

N.A.

1 e.

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

{

7.

Loss of Power w1 w

a.

4.16 kV Emergency Bus N.A.

R N.A.

N.A.

1, 2, 3, 4 g

Level 1 Es b.

4.16 kV Emergency Bus N.A.

R N.A.

N.A.

1, 2, 3, 4 3;

Level 2 Nw

8. Engineered Safety Feature Actuation System Interlocks pe5 ER a.

Pressurizer Pressure, N.A.

R Q

N.A.

1, 2, 3 85 P-ll Ea

< n on b.

Deleted J'T

!, 82 c.

Reactor Trip, P-4 N.A.

N.A.

R24 N.A.

N.A.

1, 2, 3 l

W JABLE NOTATIONS

")

Each train shall be tested at least every 62 days on a STAGGERED TEST BASIS.

For the Containment Ventilation Exhaust Radiation-High monitor only, a CHANNEL FUNCTIONAL TEST shall be performed (2)

! P at least once every 31 days.

(3) Trip function automatically blocked above P-ll (Pressurizer Pressure Interlock) setpoint and is automatically 1*1" blocked below P-11 when Safety Injection on Steam Line Pressure-Low is not blocked.

20

")

Deleted.

(5' For Mode 3, the Trip Time Delay associated with the Steam Generator Water Level-Low-low channel must be less than or equal to 464.1 seconds.

f py s awe 4 M 4 A l j QN 3/4.3.3 MONITORING INSTRUMENTATION RADIAT20N M NITOR]NG FOR PLANT OPERATIONS LIMITING CONDIT]DN FOR OPERATION 4

3.3.3.1 The radiation monitoring tastrumentation channels for plant operations shown in Table 3.3 6 shall be OPIAA8LE with their Alarmnrip 5etpoints within i

the specified limits.

APPLICABILITY: As shown in Table 3.5-6.

ACTION:

a.

With a radiation monitoring channel Alarm / Trip 5etpoint for plant 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 4

inoperable.

b.

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

The provisions of Specification 3.0.3 are not applicable.

l s.

8 3URVE1LLAN:E REQUIREMENTS 4 3.? 3 In:t radiation monitoring instrumentation channel for plant operations shall be derenstrated OPERABLE by the performance of the CHAN!!EL CHECK CHANNEL CALIBRATION and CHANNEL FUNCTIONAL TEST for the MODES and at the frequencies shown in Table 4.3-3.

i DIABLD EANYON - UNITS 1 & 2 3/4 3-36 Amendment Hos. 55 and 54

REACTOR COOLANT SYSTEM P

3/4.4.3 PRESSURIZER i

LIMITING CONDITION FOR OEPRATION 3.4.3 The pressurizer shall be OPERABLE with a water volume of less than or equal to 1600 cubic feet and two groups of pressurizer heaters each having a capacity of at least 150 kW.

APPLICABILITY: MODES 1, 2, and 3.

ACTION:

a.

With one group of pressurizer heaters inoperable, restore at least two groups to OPERABLE status within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-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 HOT SHUTDOWN within the following 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

b.

With the ~ pressurizer otherwise inoperable, be in at least HOT STANDBY with the Reactor trip breakers open within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in HOT SHUTDOWN within the following 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

SURVEILLANCE RE0VIREMENTS

)

4.4.3.1 The pressurizer water volume shall be determined to be within its limit at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

4.4.3.2 The capacity of each of the above required groups of pressurizer heaters shall be verified by measuring heater group power at least once per 92 days.

4.4.3.3 The emergency power supply for the pressurizer heaters shall be demonstrated OPERABLE at least once each REFUELING INTERVAL by transferring l

power from the normal to the emergency power supply and energizing the heaters.

1 l

5 i

4 i

DIABLO CANYON - UNITS 1 & 2 3/4 4-9 Unit 1 - Amendment No.118 Unit 2 - Amendment No.116

8 REACTOR COOLANT SYSTEM 3/4.4.4 RELIEF VALVES LIMITING CONDITION FOR OPERATION 3.4.4 All power-operated relief valves (PORVs) and their associated block valves shall be OPERABLE.

APPLICABILITY:

MODES 1, 2, and 3.

ACTION:

a.

With one or more PORV(s) inoperable because of excessive seat leak-age, within I hour either restore the PORV(s) to OPERABLE status or close the associated block valve (s) and maintain power to the block valve (s), otherwise, 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 HOT SHUTDOWN within the following 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months , b.

With one or more PORV(s) inoperable due to causes other than exces-sive seat leakage, within I hour either restore the PORV(s) to OPERABLE status or close the associated block valve (s) and remove power from the block valve (s), and l

1.

With only one Class 1 PORV OPERABLE, restore at least a total of two Class 1 PORVs to OPERABLE status within the following 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-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 HOT SHUTOOWN within the following 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months , or 2.

With no Class 1 PORVs OPERABLE, restore at least one Class 1 PORV to OPERABLE status within I hour and follow ACTION b.1, above, with the time requirement of that ACTION statement based on the time of initial loss of the remaining inoperable Class i PORV 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 HOT SHUTDOWN within the following 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

c.

With one or more block valve (s) inoperable, within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months i

1.

Restore the block valve (s) to OPERABLE status, or 2.

Close the PORV(s) and remove power from its associated solenoid.

l Also, comply with ACTION b, as appropriate, for the isolated PORV(s).

d.

The provisions of Specification 3.0.4 are not applicable.

DIABLf? CANYON - UNITS 1 & 2 3/4 4 10 Amendment Nos. ?? &.26.

6: & 80

REACTOR COOLANT SYSTEM q

SURVEILLANCE REQUIREMENTS 4.4.6.2.1 Reactor Coolant System leakagrs shall be demonstrated to be within each of the above limits by:

a.

Monitoring the containment atmosphere particulate or gaseous radioactivity monitor at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months ; b.

Monitoring the containment structure sump inventory and discharge at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months ; c.

Measurement of the CONTROLLED LEAKAGE to the reactor coolant pump seals at least once per 31 days when the Reactor Coolant System pressure is 2235 i 20 psig with the modulating valve fully open.

The provisions of Specification 4.0.4 are not applicable for entry into MODE 3 or 4; i

d.

Performance of a Reactor Coolant System water inventory balance at least once per 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months , except when T is being changed by m

greater than 5'F/ hour or when diverting reactor coolant to the liquid holdup tank, in which cases the required inventory balance shall be performed within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months after completion of the excepted operation; and e.

Monitoring the Reactor Head Flange Leakoff System at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

4.4.6.2.2 As specified in Table 3.4-1, Reactor Coolant System pressure isola-

)

tion valves shall be demonstrated OPERABLE pursuant to Specification 4.0.5, except that in lieu of any leakage testing required by Specification 4.0.5, each valve shall be demonstrated OPERABLE by verifying leakage to be within its limit:

j a.

At least once each REFUELING INTERVAL during startup, l

b.

Prior to returning the valve to service following maintenance, repair or replacement work on the valve, and c.

Within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months following valve actuation due to automatic or manual action or flow through the valve. After each disturbance of the valve, in lieu of measuring leak rate, leak-tight integrity may be verified by absence of pressure buildup in the test line downstream i

of the valve, j

The provisions of Specification 4.0.4 are not applicable for entry into. MODE 3 or 4.

I DIABLO CANYON - UNITS 1 & 2 3/4 4-20 Unit 1 - Amendment No. M,118 Unit 2 - Amendment No. M,116 D

EMERGENCY CORE COOLING SYSTEMS SURVEILLANCE RE0VIREMENTS (Continued) c.

By a visual inspection which verifies that no loose debris (rags, trash, clothing, etc.) is present in the containment which could be transported to the containment sump and cause restriction of the pump suctions during LOCA conditions.

This visual inspection shall be performed:

1)

For all accessible areas of the containment prior to establishing CONTAINMENT INTEGRITY, and 2)

At least once daily of the areas affected within containment by containment entry and during the final entry when CONTAINMENT INTEGRITY is established.

d.

At least once each REFUELING INTERVAL by a visual inspection of the l

containment sump and verifying that the subsystem suction inlets are not restricted by debris and that the sump components (trash racks, screens, etc.) show no evidence of structural distress or corrosion; e.

At least once each REFUELING INTERVAL by:

l l

1)

Verifying that each automatic valve in the flow path actuates to its correct position on a Safety Injection J

actuation test signal.

2)

Verifying that each of the following pumps start automatically upon receipt of a Safety Injection actuation test signal:

a)

Centrifugal charging pump, b)

Safety Injection pump, and c)

Residual Heat Removal pump.

f.

By verifying that each of the following pumps develops the indicated differential pressure on recirculation flow when tested pursuant to Specification 4.0.5:

1)

Centrifugal charging pump 2 2400 psid, 2)

Safety Injection, pump 2 1455 psid, and 3)

Residual Heat Removal pump 2165 psid.

DIABLO CANYON - UNITS 1 & 2 3/4 5-5 Unit 1 - Amendment No. MB,116 Unit 2 - Amendment No. MF,118

EMERGENCY CORE COOLING SYSTEMS j

i SURVEILLANCE REQUIREMENTS (Continued) g.

By verifying the correct position of each electrical and/or i

mechanical position stop for the following ECCS throttle valves:

}

1)

Within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months following completion of each valve stroking I

operation or maintenance on the valve when the ECCS subsystems are required to be'0PERABLE,'and 2)

At least once each REFUELING' INTERVAL.

l l

i

. Charging Injection Safety Injection Throttle Valves-Throttle Valves 1

8810A 8822A 8810B 88228 8810C 8822C 8810D 8822D h.

By performing a flow balance test, during shutdown, following completion of modifications to the ECCS subsystems that alter the i

]

subsystem flow characteristics and verifying that:

1)

For centrifugal charging pumps, with a single pump running:

a)

The sum of injection line flow rates, excluding the highest flow rate, is greater than or equal to 299 gpm, a

and i

1 l

I f

.DIABLO CANYON -- UNITS 1 & 2 3/4 5-6

. Unit 1 - Amendment 55,72,103,118 Unit 2 - Amendment 54,71,102.116 i -

c.

l

o.

!,o CONTAINMENT SYSTEMS

}k CONTAINMENT STRUCTURAL INTEGRITY j

LIMITING CONDITION FOR OPERATION l

3.6.1.6 The structural integrity of the containment shall be maintained at a level consistent with the acceptance criteria in Specification 4.6.1.6.

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

)

ACTION:

With the structural integrity of the containment not conforming to the above requirements, restore the structural integrity to within the limits within 24 i

hours 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 l

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

1 SURVEILLANCE RE0VIREMENTS j

i 4.6.1.6.1 Containment surfaces The structural integrity of the exposed accessible interior and exterior surfaces of the containment, including the liner plate, shall be determined during shutdown by a visual inspection of these surfaces.

This inspection shall be performed in accordance with the 3

Containment Leakage Rate Testing Program to verify no apparent changes in

{

appearance or other abnormal degradation.

4.6.1.6.2 Reports Any abnormal degradation of the containment structure detected during the above required inspections shall be reported to the Commission in a Special Report pursuant to Specification 6.9.2 within 15 days.

This report shall include a description of the condition of the concrete, the 4

inspection procedure, the tolerances on cracking, and the corrective actions taken.

4 i

)

l P

DIABLO CANYON - UNITS 1 & 2 3/4 6-9 Unit 1 - Amendment No.110 l

Unit 2 - Amendment No.109

CONTAINMENT SYSTEMS LONTAINMENT VENTILATION SYSTEM LIMITING CONDITION FOR OPERATION 3.6.1.7 One purge supply line and/or one purge exhaust line of the Containment Purge System may be open or the vacuum / pressure relief line may be open.

The vacuum / pressure relief line may be open provided the vacuum / pressure relief isolation valves are blocked to prevent opening beyond 50* (90* is fully open).

Operation with any two of these three lines open is permitted.

Operation with the purge supply and/or exhaust isolation valves open or with the vacuum /

pressure relief isolation valves open up to 50* shall be limited td less than or equal to 200 hours0.00231 days 0.0556 hours 3.306878e-4 weeks 7.61e-5 months during a calendar year.

APPLICABILITY:

MODES 1, 2, 3, and 4.

F ACTION:

With a containment purge supply and/or exhaust isolation valve open or the vacuum / pressure relief isolation valves open up to 50* for more than 200 hours0.00231 days 0.0556 hours 3.306878e-4 weeks 7.61e-5 months during a calendar year or the Containment Purge System open and the vacuum /

pressure relief lines open, or with the vacuum / pressure relief isolation valves open beyond 50*, close the open isolation valve (s) or isola'te the penetra-tion (s) within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months ; otherwise, 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 RE0VIREMENTS 4.6.1.7.1 The position of the containment purge supply and exhaust isolation valves and the vacuum / pressure relief isolation valves shall be determined closed at least once per 31 days.

4.6.1.7.2 The cumulative time that the purge supply and/or exhaust isolation valves or the vacuum / pressure relief isolation valves have been open during a calendar year shall be determined at least once per 7 days.

4.6.1.7.3 The vacuum / pressure relief isolation valves shall be verified to be blocked to prevent opening beyond 50* at least once each REFUELING INTERVAL.

l i

DIABLO CANYON - UNITS 1 & 2 3/4 6-10 Unit 1 - Amendment No.118 Unit 2 - Amendment No.116 u.

CONTAlfelENT SYSTEMS i

3/4.6.2 DEPRESSURIZATION AND COOLING SYSTEMS CONTAlletENT SPRAY SYSTEM LIMITIIIG CopOITION FOR OPERATION 3.6.2.1 Two Containment Spray Systems shall be OPERABLE with each Spray System capable of taking suction from the RWST and transferring spray function to a RHR System taking suction from the containment sump.

APPLICABILITY: HODES 1, 2, 3 and 4.

Ellg:

4 l

With one Containment Spray System inoperable, restore the inoperable Spray 4

System to OPERABLE status within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months or be in at least HOT STANDBY within 1

the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months ; restore the inoperable Spray System to OPERABLE status within l

the next 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months or be in COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

j SURVEILLANCE REOUIREMENTS 1

4.6.2.1 Each Containment Spray System shall be demonstrated OPERABLE:

a.

At least once per 31 days by verifying that each valve (manual, power operated or automatic) in the flow path that is not locked, sealed, l

or otherwise secured in position, is in its correct position; b.

By verifying that on recirculation flow, each pump develops a differential pressure of greater than or equal to 205 paid when i

tested pursuant to Specification 4.0.5; c.

At,least once per 18 months by:

1)

Verifying that each automatic valve in the flow path actuates to l

its correct position on an actual or simulated actuation signal, I

and i

2)

Verifying that each spray pump starts automatically on an actual i

or simulated actuation signal.

I d.

At least once par 10 years by performing an air or smoke flow test through each spray header and verifying each spray nozzle is unobstructed.

1 l

i I

DIABLO CANYON - UNITS 1 & 2 3/4 6-11 Unit 1 - Amendment No. 448,114 Unit 2 - Amendment No. 441,112

^

CONTAINMENT SYSTEMS SPRAY ADDITIVE SYSTEM LIMITING CONDITION FOR OPERATION 3.6.2.2 The Spray Additive System shall be OPERABLE with:

A spray additive tank with a contained volume of between 2025 and a.

4000 gallons of between 30 and 32% by weight Na0H solution, and b.

Two spray additive eductors each capable of adding NaOH solution from the chemical additive tank to a Containment Spray System pump fl ow.

APPLICABILITY:

MODES 1, 2, 3, and 4.

ACTION:

With the Spray Additive System inoperable, restore the system to OPERABLE status within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-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 ; restore the Spray Additive System to OPERABLE status within the next 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months or be in COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

SURVEILLANCE RE0VIREMENTS 4.6.2.2 The Spray Additive System shall be demonstrated OPERABLE:

At least once per 31 days by verifying that each valve (manual, a.

power-operated, or automatic) in the flow path that is not locked, sealed, or otherwise secured in position, is in its correct position; b.

At least once per 6 months by:

1)

Verifying the contained solution volume in the tank, and 2)

Verifying the concentration of the Na0H solution by chemical

analysis, c.

At least once each REFUELING INTERVAL by verifying that each l

automatic valve in the flow path actuates to its correct position on a Containment Spray actuation test signal; and d.

At least once per 5 years by verifying both spray additive and RWST full flow from the test valve 8993 in the Spray Additive System.

DIABLO CANYON - UNITS 1 & 2 3/4 6-12 Unit 1 - Amendment No.118 Unit 2 - Amendment No.116

CONTAINMENT SYSTEMS CONTAINMENT COOLING SYSTEM LIMITING CONDITION FOR OPERATION 3.6.2.3 The Containment Cooling System shall be OPERABLE with either:

a.

At least four containment fan cooler units (CFCUs), or b.

At least three CFCUs, each of the three supplied from a different vital bus.

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

ACTION:

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

at least two CFCUs OPERABLE and both Containment Spray Systems OPERABLE, restore the Containment Cooling System to OPERABLE status within 7 days, otherwise 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 .

b.

With the requirements of the above specification ~not satisfied and one Containment Spray System inoperable, but at least two CFCVs OPERABLE, restore the inoperable Containment Spray Sys~ tem to OPERABLE status within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months otherwise 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 .

Restore the Containment Cooling System.to OPERABLE status within 7 days of initial loss 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 .

SURVEILLANCE RE0VIREMENTS 4.6.2.3 Each containment fan cooler unit shall be demonstrated OPERABLE:

a.

At least ones per 31 days by:

1)

Starting each containment fan cooler unit and verifying that each containment fan cooler unit operates for at least 15

minutes, DIABLO CANYON - UNITS 1 & 2 3/4 6-13 Amendment Nos. 11 a 0 89 & 88

t-CONTAINMENT SYSTEMS CONTAINMENT COOLING SYSTEM SURVEILLANCE REQUIREMENTS (Continued) t 2)

Verifying a cooling water flow rate of greater than or equal to 1650* gpm to each cooler, and 3)

Verifying that each containment fan cooler unit starts on low speed.

b.

At least once each REFUELING INTERVAL by verifying that each l

containment fan cooler unit starts automatically on a Safety Injection test signal.

l

The CFCU cooling water flow rate requirement of TS 4.6.2.3a.2) may not be met during Section XI testing and in Mode 4 during residual heat removal heat exchanger operation.

118 DIABLO CnNYON - UNITS 1 & 2 3/4 6-14 Unit 1 - Amendment No. 69,116 Unit ? - Amendment No. 68, 4

~

i CONTAINMENT SYSTEMS j

3/4.6.3 CONTAINMENT ISOLATION VALVES LIMITING CONDITION FOR OPERATION 3.6.3 Each containment isolation valve shall be OPERABLE.*

APPLICABILITY:

MODES 1, 2, 3, and 4.

ACTION:

With one or more of the isolation valve (s) inoperable, maintain at least one isolation valve OPERABLE in each affected penetration that is open and:

a.

Restore the inoperable valve (s) to OPERABLE status within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months , or b.

Isolate each affected penetration within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months by use of at least one deactivated automatic valve secured in the isolation position, or c.

Isolate each affected penetration within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months by use of at least one closed manual valve or blind flange; or d.

Be in at least H0T 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~ hours.

Locked or sealed closed valves may be opened on an intermittent basis under administrative control.

SURVEILLANCE REQUIREMENTS 4.6.3.1 Each containment isolation valve shall be demonstrated OPERABLE prior to returning the valve to service after maintenance, repair or replacement work is performed on the valve or its associated actuator, control or power circuit by performance of a cycling test, and 'ierification of isolation time.

4.6.3.2 Each containment isolation valve shall be demonstrated OPERABLE at least once each REFUELING INTERVAL by:

l a.

Verifying that on a Phase "A" Isolation test signal, each Phase "A"

)

isolation valve actuates to its isolation position; b.

Verifying that on a Phase "B" Isolation test signal, each Phase "B" isolation. valve actuates to its isolation position; and c.

Verifying that on a Containment Ventilation Isolation test signal, each containment ventilation isolation valve actuates to its isolation position.

DIABLO CANYOH - UNITS 1 & 2 3/4 6-15 Unit 1 - Amendment No. 73,118 Unit 2 - Amendment No. 72,116

CONTAINMENT SYSTDtS SURVEILLANCE REQUIREMENTS (Continued) 4.6.3.3 The isolation time of each testable power-operated or automatic containment isolation valve shall be determined to be within its limit when tested pursuant to Specific.ation 4.0.5.

4.6.3.4 Each containment ventilation isolation valve, except the air sample supply and return valves, shall be demonstrated OPERABLE within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months after each closing of the valve, except when the valve is being used for multiple cycling, then at least once per 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months by verifying leakage rates in accordance with the Containment Leakage Rate Testing Program.

e DIABLO CANYON - LMITS 1 & 2 3/4 6-16 Unit 1 - Amendment No. M,110 Unit 2 - Amendment No. M,109

CONTAINMENT SYSTEMS i

i 3/4.6.4 COPSUSTIBLE GAS CONTROL HYDR 0 GEN ANALYZERS / MONITORS j

LIMITING CONDITION FOR OPERATION i

l 3.6.4.1 Two independent containment hydrogen analyzers / monitors shall.be j

OPERABLE.

1 j

APPLICABILITY:

MODES 1 and 2.

ACTION:

i a.

With one hydrogen analyzer / monitor inoperable, restore the inoperable analyzer / monitor to OPERABLE status within 30 days or be in at least j

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

j b.

With both hydrogen analyzer / monitors inoperable, restore at least one analyzer / monitor to OPERABLE status within.72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months or be in at least HDT STAND 8Y within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

J 1

SURVEILLANCE REQUIREMENTS i

-i i

4.6.4.1 Each hydrogen analyzer / monitor shall be demonstrated OPERABLE at i

least once per 92 days by performing a CHANNEL CALIBRATION using a zero and j

span gas.

i i

DIABLD CANYON - UNITS 1 & 2 3/4 6-17 Amendment Nos. 73 & 72'

CONTAINMENT SYSTEMS ELECTRIC HYDR 0 GEN RECOMBINERS LIMITING CONDITION FOR OPERATION 3.6.4.2 Two independent Hydrogen Recombiner Systems shall be OPERABLE.

APPLICABILITY:

H0 DES 1 and 2.

ACTION:

With one Hydrogen Recombiner System inoperable, restore the inoperable system to OPERABLE status within 30 days 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 .

SURVEILLANCE RE0VIREMENTS 4.6.4.2 Each Hydrogen Recombiner System shall be demonstrated OPERABLE:

a.

At least once each REFUELING INTERVAL by verifying, during a l

Recombiner System functional test, that the minimum heater sheath temperature increases to greater than or equal to~ 700*F within 90 minutes. Upon reaching 700*F, increase the power setting to maximum power for 2 minutes and verify that the power meter reads greater than or equal to 60 kW; and j

b.

At least once each REFUELING INTERVAL by:

l i

1)

Performing a CHANNEL CALIBRATION of all recombiner instrumentation and control circuits, 2)

Verifying through a visual examination that there is no evidence of abnormal conditions within the recombiner enclosure (i.e.,

loose wiring or structural connections, deposits of foreign materials, etc.), and 3)

Verifying the integrity of all heater electrical circuits by performing a resistance to ground test following the above required functional test.

The resistance to ground for any heater phase shall be greater than or equal to 10,000 ohms.

DIABLO CANYON - UNITS 1 & 2 3/4 6-18 Unit 1 - Amendment No. 73,102, 118 Unit 2 - Amendment No. 72,101, 116

=

l PLANT SYSTEMS I

SURVEILLANCE RE0VIREMENTS (2)

Verifying that each non-automatic valve in the pump flow path that is not locked, sealed, or otherwise secured in position, is in its correct position.

(3) Verifying that each non-automatic valve in both steam supplies to the steam turbine-driven pump that is not locked, sealed, or otherwise secured in position, is in its correct position.

b.

At least once per 92 days on a STAGGERED TEST BASIS by:

testing the steam turbine-driven pump and motor-driven pumps pursuant to Specification 4.0.5*.

The provisions of Specification 4.0.4 are not applicable for entry into MODE 3 for the steam turbine-driven pump.

c.

At least once each REFUELING INTERVAL by verifying that each I

auxiliary feedwater pump starts and valve opens

as designed automatically upon receipt of an Auxiliary Feedwater Actuation test signal.

For the steam turbine-driven pump, when the secondary steam supply pressure is greater than 650 psig.

DIABLO CANYON - UNITS 1 & 2 3/4 7-5 Unit 1 - Amendment No. 52,102,118 Unit 2 - Amendment No. 51,101,116

PL4NT SYSTEMS i

1 AUXILIARY FEEDWATER SOURCE q

LIMITING CONDITION FOR OPERATION j

3.7.1.3.The Condensate Storage Tank (CST) shall have a usable volume of at least 164,678 gallons of water with an open flow path to the Auxiliary Feedwater (AFW) pump suction, and the Fire Water Storage Tank (FWST) shall have a usable volume of at least 57,922 gallons of water for one Unit operation and 115,844 gallons of water for two Unit operation with a flow path 4

1 capable of being aligned to the AFW pump suction.

APPLICABILITY: MODES 1, 2 and 3.

j EIIM:

a.

With the CST usable volume less than 164,678 gallons, or with the CST flow path not open to the AFW pumps suction, within four hours restore the required conditions; 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 HOT SHUTDOWN within the following 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

j b.

With an FWST usable volume less than 57,922 gallons for one Unit operation and 115,844 gallons for two Unit operation, or with the i

FWST flow path not capable of being aligned to the AFW pump suction, within seven days restore the required FWST conditions; 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 HOT SHUTDOWN within the following 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

SURVEILLANCE REOUIREMENTS i

4.7.1.3.1 The CST volume shall be demonstrated at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months by verifying the usable volume is within its limits.

4.7.1.3.2 The FWST volume shall be demonstrated at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months by verifying the usable volume is within its limits.

4.7.1.3.3 Verify the FWST is capable of being aligned to the Auxiliary Feedwater System by cycling each FWST valve in the flow path necessary for realignment through at least one full r.ycle once per quarter.

DIABLO CANYON - UNITS 1 & 2 3/4 7-6 Amendment Nos. 75 & 74

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PLANT SYSTEMS STEAM GENERATOR 10% ATMOSPHERIC DUMP VALVES LIMITING CONDITION FOR OPERATION 3.7.1.6 Four steam generator 10% atmospheric dump valves (ADVs) with the associated block valves open and associated remote manual controls, including the backup air bottles, shall be OPERABLE.

APPLICABILITY:

MODES 1, 2, and 3.

ACTION:

a.

With one less than the required number of 10% ADVs OPERARL,E, restore the inoperable steam generator 10% ADV to OPERABLE status within ?

days; 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 HOT SHU1DOWN within the following 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

/

b.

With two less than the required numbered of 10% ADVs OPERABLE, restore at least one of the inoperable steam generator 10% ADVs to OPERABLE status within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-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 HOT SHUTDOWN within the following 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

SURVEILLANCE RE0VIREMENTS 4.7.1.6 Each steam generator 10% ADV, associated block valve and associated remote manual controls including the backup air bottles shall be demonstrated OPERABLE:

a.

At least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months by verifying that the backup air bottle for each steam generator 10% ADV has a pressure greater than or equal to 260 psig, and b.

At least once per 31 days by verifying that the steam generator 10%

ADV block valves are open, and c.

At least once each REFUELING INTERVAL by verifying that all steam I

generator 10% ADVs will operate using the remote manual controls and the backup air bottles.

DIABLO CANYON - UNITS 1 & 2 3/4 7-9a Unit 1 - Amendment No. &&r72,118 Unit 2 - Amendment No. GF,-74,116

O PLANT SYSTEMS 3/4.7.3 VITAL COMPONENT COOLING WATER SYSTEM LIMITING CONDITION FOR OPERATION 3.7.3.1 At least two vital component cooling water loops shall be OPERABLE.

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

ACTION:

With only one vital component cooling water loop OPERABLE, restore at least two loops to OPERABLE status within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-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 .

SURVEILLANCE REQUIREMENTS 4.7.3.1 At least ?.wo vital component cooling water loops shall be demonstrated I

.0PERABLE:

)

a.

At least once per 31 days by verifying that each valve (manual, power-operated, or automatic) servicing safety-related equipment that i

is not locked, sealed, or otherwise secured in position, is in its correct position; and b.

At least once each REFUELING INTERVAL, by verifying that each l

automatic valve servicing safety-related equipment actuates to its correct position on a Safety Injection or Phase "B" Isolation test signal, as appropriate.

c.

At least once each REFUELING INTERVAL, by verifying that each component cooling water pump starts automatically on an actual or simulated actuation signal.

DIABLO CANYON - UNITS 1 & 2 3/4 7-11 Unit 1 - Amendment No.118-Unit 2 - Amendment No.116

PLANT SYSTEMS 3/4.7.4 AUXILIARY SALTWATER SYSTEM l

LIMITING CONDITION FOR OPERATION 3.7.4.1 aAt least two auxiliary saltwater trains shall be OPERABLE.

APPLICABILITY:

MODES 1, 2, 3, and 4.

ACTION:

With only one auxiliary saltwater train OPERABLE, restore at least two ' trains i

to OPERABLE status within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-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 .

SURVEILLANCE RE0VIREMENTS 4.7.4.1 At least two auxiliary saltwater trains shall be demonstrated OPERABLE at least once per 31 days by verifying that each valve (manual, power-operated, or automatic) servicing safety-related equipment that is not locked, sealed, or otherwise secured in position, is in its correct position.

4.7.4.2 Each auxiliary saltwater pump shall be demonstrated OPERABLE at least once each REFUELING INTERVAL by verifying that each pump starts automatically on an actual or simulated actuation signal.

i DIABLO CANYON - UNITS 1 & 2 3/4 7-12 Unit 1 - Amendment No.118 Unit 2 - Amendment No.116 l

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APPLICABILITY L

BASES j

specification results in entry into a MODE 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 MODE of operation may not be used to extend the allowable outage time that is applicable when a Limiting Condition for Operation is not met in a lower MODE of operation.

The shutdown requirements of Specification 3.0.3 do not apply in MODES 5 and 6 because the ACTION requirements of individual specifications define the remedial measures to be taken, r

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

It precludes placing the facility in a higher MODE of operation when the requirements for a Limiting Condition for Operation 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 MODES of operation are not entered when corrective action is being taken to obtain compliance with a specification by restoring equipment to OPERABLE status or i

parameters to specified limits. Compliance with ACTION requirements that permit continued operation of the facility for an unlimited period of time 4

provides an acceptable level of safety for continued operation without regard to the status of the plant before or after a MODE change.

Therefore, in this i

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.

4 I

L' hen 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.

1 4

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

APPLICABILITY BASES 3.0.5 This specification delineates the applicability of each specification to Unit I and Unit 2 operation.

4.0.1 This specification establishes the requirement that surveillances must be performed during the OPERATIONAL MODES or other conditions for which the requirements of the Limiting Conditions for Operation apply unless otherwise stated in an individual Surveillance Requirement.

The purpose of this specification is to ensure that surveillances are performed to verify the opert.tional status of systems and components and that parameters are within specified limits to ensure safe operation of the facility when the plant is in a MODE or other specified condition or which the associated Limiting Conditions for Operation are applicable.

Surveillance Requirements do not have to be performed when the facility is in an OPERA:10NAL MODE for which the requirements of the associated Limiting Condition for Operation do not apply unless otherwise specified.

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

4.0.2 Specification 4.0.2 establishes the limit for which the specified time, interval for Surveillance Requirements may be extended.

It permits an allowable extension of the normal surveillance interval to facilitate l

surveillance scheduling and consideration of plant operating conditions that may not be suitable for conducting the surveillance; e.g., transient conditions or other ongoing surveillance or maintenance activities.

It also provides flexibility to accommodate the length of a fuel cycle for surveillances that s

are specified to be performed at least once each REFUELING INTERVAL.

It is not intended that this provision be used repeatedly as a convenience to extend surveillance intervals beyond that specified for surveillances that are not performed once each REFUELING INTERVAL.

Likewise, it is not the intent that REFUELING INTERVAL surveillances be performed during power operation unless it is consistent with safe plant operation.

The limitation of Specification 4.0.2 is based on engineering judgment and the recognition that the most probable result of any particulate surveillance being performed is the verification of conformance with the Surveillance Requirements.

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

4.0.3 This specification establishes the failure to perform a Surveillance Requirement within the allowed surveillance interval, defined by the provisions of Specification 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 to be OPERABLE when Surveillance Requirements have been satisfactorily performed within the specified time interval.

However, nothing in this provision is to be construed as implying that systems or components are 4

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 surveillan.a interval and that the time limits of the ACTIOP requirements apply from the point in time it is identified that a a

surveillaace has not been performed and not at the time that the allowed DIABLO CANYON - UNITS 1 & 2 B 3/4 0-2 Unit 1 - Amendment No. 9,118 Unit 2 - Amendment No. %,116 y e i.

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