Text

Amends 102 & 101 to Licenses DPR-80 & DPR-82,respectively, Re Changes to TS to Revise Certain SRs of Combined TS for Plant Consistent W/Recommendations in GL 93-05 Line Item TS Improvements to Reduce SRs for Testing During Power..
	ML20084R882
Person / Time
Site:	Diablo Canyon
Issue date:	05/26/1995
From:	Mark Miller; NRC (Affiliation Not Assigned)
To:	;
Shared Package
ML20084R884	List: ML20084R882; ML20084R898;
References
	GL-93-05, GL-93-5, NUDOCS 9506090446
	Download: ML20084R882 (25)
	v • d • e

..

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yt UNITED STATES l, Jg i j NUCLEAR REGULATORY COMMISSION 2

WASHINGTON, D.C. 20555-0001 k'N/4,[

PACIFIC GAS AND ELECTRIC COMPANY DOCKET NO. 50-275 DIABLO CANYON NUCLEAR POWER PLANT. UNIT NO. 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.102 License No. DPR-80 1.

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

A.

The application for amendment by Pacific Gas and Electric Company (the licensee) dated September 20, 1994, as supplemented by letter dated April 14, 1995, 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 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 Commission'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 Commission'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:

9506090446 950526 PDR ADOCK 05000275 P

PDR

. (2)

Technical Specifications l

The Technical Specifications contained in Appendix A and the Environmental Protection Plan contained in Appendix B, as revised i

through Amendment No. 102, 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.

i 3.

This license amendment is ef fective as of its date of issuance to be implemented 60 days from the date of issuance.

FOR THE NUCLEAR REGULATORY COMMISSION j

7mb t

Et Melanie A. Miller, Senior Project Manager i

rroject Directorate IV-2 Division of Reactor Projects III/IV Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical Specifications Date of Isseance:

May 26, 1995

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UNITED STATES E

NUCLEAR REGULATORY COMMISSION f

WASHINGTON, D.C. 20565 4001 s.;

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PACIFIC GAS AND ELECTRIC COMPANY DOCKET NO. 50-323 DIABLO CANYON NUCLEAR POWER PLANT. UNIT NO. 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 101 License No. DPR-82 3.

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

A.

The application for amendment by Pacific Gas and Electric Company (the licensee) dated September 20, 1994, as supplemented by letter dated April 14, 1995, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission'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 Commission; 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 Commission'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 Commission'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:

)

1 i

' (2)

Technical Specifications The Technical Specifications contained in Appendix A and the Environmental Protection Plan contaiaed in Appendix B, as revised through Amendment No.

101, are t.

incorporated in the license.

Pacific Gas and Elect.rk

,any shall operate the facility in accordance with th6.m&. scal 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 60 days from the date of issuance.

FOR THE NUCLEAR REGULATORY COMMISSION Melanie A. Miller, Senior Project Manager Project Directorate IV-2 Division of Reactor Projects III/IV Office of Nuclear Reactor Regulatirn

Attachment:

Changes to the Technical Specifications Date of Issuance:

May 26, 1995 i

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i

ATTACHMENT IQ LICENSE AMENDMENTS AMENDMENT NO. 102 TO FACILITY OPERATING LICENSE NO. DPR-80 r

AND AMENDMENT NO.101 TO FACILITY OPERATING LICENSE N0. DPR-82 DOCKET N05. 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 3/4 1-16 3/4 1-16 3/4 3-33 3/4 3-33 3/4 3-39 3/4 3-39 3/4 5-1 3/4 5-1 3/4 5-2 3/4 5-2 3/4 5-5 3/4 5-5 3/4 6-11 3/4 6-11 3/4 6-18 3/4 6-18 3/4 7-3*

3/4 7-4 3/4 7-4 3/4 7-5 3/4 7-5 3/4 10-1 3/4 10-1 3/4 11-3 3/4 11-3

No changes; reissued to become overleaf page

5 REACTIVITY CONTROL SYSTEMS 3/4.1.3 MOVABLE CONTROL ASSEMBLIES i

GROUP HEIGHT l

LIMITING CONDITION FOR OPERATION 3.1. 3.1 All full-length shutdown and control rods shall be OPERABLE and positioned within i 12 steps (indicated position) of their group demand position.

APPLICABILITY:

MDOES 1* and 2*.

ACTION:

With one or more full-length.ods inoperable due to being immovable a.

as a result of excessive friction or mechanical interference or known to be untrippable, determine that the SHUTDOWN MARGIN requirement of Specification 3.1.1.1 is satisfied within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months and be in HOT STANDBY within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

b.

With one full-length rod trippable but inoperable due to causes other than addressed by ACTION a., above, or misaligned from its group demand height by more than i 12 steps (indicated position), POWER OPERATION may continue provided that within 1 hour:

1.

The rod is restored to OPERABLE status withir. the above alignment requirements, or 2.

The rod is declared inoperable and the remainder of the rods in the group with the inoperable rod are aligned to within i 12 steps of the inoperable rod while maintaining the rod sequence and insertion limits of Specification 3.1.3.6.

The THERMAL POWER

(

level shall be restricted pursuant to Specification 3.1.3.6 during subsequent operation, or 3.

The rod is declared inoperable and the SHUTDOWN MARGIN requirement of Specification 3.1.1.1 is satisfied.

POWER OPERATION may then continue provided that:

a)

A reevaluation of each accident analysis of Table 3.1-1 is performed within 5 days; this reevaluation shall confirm that the previously analyzed results of these accidents remain valid for the duration of operation under these conditions; b)

THE SHUTDOWN MARGIN requirement of Specification 3.1.1.1 is determined at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months ;

See Special Test Exceptions Specifications 3.10.2 and 3.10.3.

DIABLO CANYON - UNITS 1 & 2 3/4 1-15 Amendment Nos.45 and 44

i REACTIVITY CONTROL SYSTEMS i

LIMITING CONDITION FOR OPERATION ACTION (Continued) c)

A power distribution map is obtained from the movable incore detectors and F Z) and F"a are verified to be within their limits wiY.(hin 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months ; and d)

The THERMAL POWER level is reduced to less than or equal to 75% of RATED THERMAL POWER within the next hour and within the following 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months the High Neutron Flux Trip Setpoint is reduced to less than or equal to 85% of RATED THERMAL POWER.

c.

With more than one rod trippable but inoperable due to causes other than addressed by ACTION a above, POWER OPERATION may continue s

provided that:

1.

Within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months , the remainder of the rods in the bank (s) with the inoperable rods are aligned to within i 12 steps of the inoperable rods while maintaining the rod sequence and insertion limits of Specification 3.1.3.6.

The THERMAL POWER level shall be restricted pursuant to Specification 3.1.3.6 during subsequent operation, and 2.

The inoperable rods are restored to OPERABLE status within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months .

d.

With more than one rod misaligned from its group demand position by more than i 12 steps (indicated position), be in HOT STANDBY within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

SURVEILLANCE REQUIREMENTS 4.1.3.1.1 The position of each full-length rod shall be determined to be within the group demand limit by verifying the individual rod positions at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months except during time intervals when the Rod Position Deviation Monitor is inoperable, then verify the group positions at least once per 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

4.1.3.1.2 Each full-length rod not fully inserted in the core shall be deter-mined to be OPERABLE by movement of at least 10 steps in any one direction at least once per 92 days.

l DIABLO CANYON - UNITS 1 & 2 3/4 1-16 Unit 1 - Amendment No. 4,102 Unit 2 - Amendment No. 4,101

TABLE 4.3-2 1 Continued)

ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION o

SURVEILLANCE REQUIREMENTS 2

E TRIP ACTUATING 9

CHANNEL DEVICE MODES FOR 5

CHANNEL OPERA-OPERA-MASTER SLAVE WHICH E

CHANNEL CALI-TIONAL TIONAL ACTUATION RELAY RELAY SURVEILLANCE i

FUNCTIONAL UNIT CHECK BRATION TEST TEST LOGIC TEST TEST TEST IS REQUIRED C

5 3. Containment Isolation d

a.

Phase "A" Isolation

1) Manual N.A.

N.A.

R N.A.

N.A.

1, 2, 3, 4 -

e.

2) Automatic Actuation N.A.

N.A.

M(1)

Q(4) 1, 2, 3, 4 Logic and Actuation m

Relays

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

b.

Phase "B" Isolation

1) Manual N.A.

N.A.

R N.A.

N.A.

1, 2, 3, 4 R

2) Automatic Actuation N.A.

N.A.

H(1)

M(1)

Q 1, 2,'3, 4 Logic and Actuation y

Relays g

3) Containment S

R Q

N.A.

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

Containment Ventilation EE Isolation 33

1) Automatic Actuation N.A.

N.A.

M(1)

Q 1, 2, 3, 4 Logic and Actuation

~~

Relays i

gg 2)

Plant Vent Noble Gas S

R M(2)

N.A.

.N.A.

N.A.

1, 2, 3, 4 Activity-High (RM-14A

..EE and 148)(*)

52

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

55

4) Containment Ventilation Exhaust Radiation-High zz

??

(RM-44A and 44B)(b)

S R

Q N.A.

N.A.

1, 2, 3, 4 L

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$ $ (a)

The requirements for Plant Vent Noble Gas Activity-High (RM-14A and 148) are not applicable following jo' installation of RM-44A and 44B.

o

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The requirements for Containment Ventilation Exhaust Radiation-High (RM-44A and 448) are applicable following

@,8 (b) installation of RM-44A and 44B.

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TRIP E

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Q CllANNEL IKVICL MODES FOR EllANNIL OPIRA-OPERA-NASTER SLAVE letiCH CilANNI'L CATI-il0NAL il0NAL ACTUATION RELAY RELAY SURVElllANCE FUNCTIONAL UNIT CHICK _

BRAll0N TLST TEST LOGIC TEST 1EST _ ' TEST IS NEQUIRED

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4.

Steam Line Isolation

[

a.

Manuel N.A.

N.A.

R N.A.

N.A.

1, 2. 3 b.

Automatic Actuation Logic N.A.

N.A.

M(1)

Q

1. 2. 3 and Actuation belays c.

Containment Pressure-S R

Q N.A.

N.A.

1. 2. 3 High.High d.

Steam line Pressure low 5

R Q

N.A.

1. 2. 3 e.

Negative Steam line 5

R Q

N.A.

M.A.

N.A.

3(3)

Pressure Rate-High se S.

Turbine Trip and Feedwater Isolation a.

Automatic Actuation N.A.

M.A.

N.A.

N(1)

M(1)

Q

l. 2 Logic and Actuation Nelays b.

Steam Generator Water S

R Q

N. e..

N.A.

1. 2 Level-Hi@-High 6.

Aux 111ery Feedwater a.

Manual N.A.

N.A.

M.A.

R N.A.

N.A.

1. 2. 3 g

b.

Automatic Actuation h.A.

N.A.

M.A.

M(1)

M(1) 0

1. 2. 3 Logic and Actuation Nelays c.

Steam Generator Water Level tow Low gg

1) Steam Generator S

R Q

N.A.

N. A. -

1. 2. 3 g&

Water Level-Low-tow k

2) RCS Loop aT N.A.

R Q

N.A.

1. 2. 3 I

TABLE 4.3-3 RADIATION MONITORING INSTRUMENTATION FOR PLANT OPERATIONS' SURVEILLANCE REQUIREMENTS 3

t r

S CHANNEL MODES FOR WHICH E

CHANNEL CHANNEL FUNCTIONAL SURVEILLANCE 5

CHECK CALIBRATION TEST IS REQUIRED 9

x 5

1.

Fuel Handling Building a.

Storage Area l

1)

Spent Fuel Pool S

R Q

E 2)

New Fuel Storage S

R Q-Z b.

Gaseous Activity Fuel Handling Building S

R Q

Ventilation Mode Change (*)

~

i 2.

Control Room Ventilation Mode Change S

R Q

All 3.

Containment a.

Gaseous Activity i

1)

Containment S

R Q

6 Ventilation m

Isolation N

[

(RM-14A or 14B)(*)

4, 2)

RCS Leakage S

R Q

1, 2, 3, 4 3)

Containment Venti-S R

Q 6

?

lation Isolation (RM-44A or 448)

S R

Q 6

4 b.

Particulate Activity 1)

Containment Venti-S R

Q 6

7 lation Isolation cc j

li (RM-44A or 448)(b) 2)

RCS Leakage S

R Q

1, 2, 3, 4 m-l 4 I gy

With fuel in the spent fuel pool or new fuel storage vault.
g(
(a) The requirements for Containment Ventilation Isolotion (RM-14A or 148) are not applicable following gg installation of RM-44A and 44B.
l AE (b) The requirements for Containment Ventilation Isolation (RM-44A or 448) are applicable following gg installation of RM-44A and 448.
~'
(c) The requirements for Fuel Handling Building Ventilation Mode Change are applicable following
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installation of RM-45A and 45B.
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INSTRUMENTATION l
MOVABLE INCORE DETECTORS 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 Sufficient movable detectors, drive, and readout equipment to map c.
these thimbles.
APPLICABILITY: When the Movable Incore Detection System is used for:
Recalibration of the Excore Neutron Flux Detection System, or a.
b.
Monitoring the QUADRANT POWER TILT RATIO, or MeasurementofFh,F(Z)andF,.
c.
q 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 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 by normalizing each detector output when required for:
a.
Reca11bration of the Excore Neutron Flux Detection System, or b.
Monitoring the QUADRANT POWER TILT RATIO, or NeasurementofFh,F(Z)andF,.
c.
q DiABLOCANYON-UNITS 1&2 3/4 3-40 Amendment Nos. 55.and 54 D
3/4.5 EMERGENCY CORE COOLING SYSTEMS 3/4.5.1 ACCUMULATORS LIMITING CONDITION FOR OPERATION 3.5.1 Each Reactor Coolant System accumulator shall be OPERABLE with:
a.
The isolation valve open and power removed,
~
b.
A contained borated water volume of between 836 and 864 cubic feet of borated water, c.
A boron concentration of between 2200 and 2500 ppm, and d.
A nitrogen cover-pressure of between 595.5 and 647.5 psig.
i 6,PPLICABILITY: MODES 1, 2 and 3.*
s 1
ACTION:
i a.
With one accumulator inoperable, except as a result of a closed isolation valve, restore the inoperable accumulator to OPERABLE status within I hour or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in at least HOT SHUTDOWN within the following 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .
b.
With one accumulator inoperable due to the isolation valve being closed, either immediately open the isolation valve or be in HOT STANDBY 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 4.5.1.1 Each accumulator shail be demonstrated OPERABLE:
a.
At least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months by:
1)
Verifying that the contained borated water volume and nitrogen cover-pressure in the tanks are within their limits, and 2)
Verifying that each accumulator isolation valve is open.
Pressurizer pressure above 1000 psig.
DIABLO CANYON - UNITS 1 & 2 3/4 5-1 Unit 1 - Amendment Nos. 14,72,102 Unit 2 - Amendment Nos. 13,71,101
EMERGENCY CORE COOLING SYSTEMS SURVEILLANCE REQUIREMENTS (Continued) b.
At least once per 31 days and within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months after each solution
. volume increase of greater than or equal to 1% of tank volume by verifying the boron concentration of the accumulator solution. This surveillance is not required when the volume increase makeup source is the RWST and the RWST has not been diluted since verifying that the RWST boron concentration is equal to or greater than the accumulator boron concentration limit; and c.
At least once per 31 days when the RCS pressure is above 1000 psig by verifying that power to the isolation valve operator is discon-nected by sealing the breaker in the open position.
I DIABLO CANYON - UNITS 1 & 2 3/4 5-2 Unit 1 - Amendment No. 102 Unit 2 - Amendment No. 101
4 EMERGENCY CORE COOLING SYSTEMS SURVEILLANCE REQUIREMENTS (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 per 18 months by a visual inspection of the containment sump and verifying that the subsystem suction inlets are s
not restricted by debris and that the sump components (trash racks, screens, etc.) show no evidence of structural distress or corrosion; i
e.
At least once per 18 months by:
1)
Verifying that each automatic valve in the flow path j
actuates to its correct position on a Safety Injection 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. 102 Unit 2 - Amendment No. 101
l 1
I I
EMERGENCY CORE COOLING SYSTEMS SURVEILLANCE REQUIREMENTS (Continued) g.
By verifying the correct position of each electrical and/or mechanical position stop for the following ECCS throttle valves:
l 1)
Within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months following completion of each valve stroking opera-tion or maintenance on the valve when the ECCS subsystems are re-l quired to be OPERABLE, and 2)
At least once per 18 months.
Charging Injection Safety Injection l
Throttle Valves Throttle Valves 8810A 8822A 8810B 8822B 8810C 8822C 8810D 8822D h.
By performing a flow balance test, during shutdown, following comple-tion of modifications to the ECCS subsystems that alter the subsystem flow characteristics and verifying that:
For Unit 1 Cycle 5 1)
For centrifugal charging pump lines, with a single pump running:
I a)
The sum of the injection line flow rates, excluding the j
highest flow rate, is greater than or equal to 346 gpm, 1
and b)
The total pump flow rate is less than or equal to 550 gpm.
2)
For safety injection pump lines, with a single pump running:
a)
The sum of the injection line flow rates, excluding the highest flow rate, is greater than or equal to 463 gpm, and b)
The total pump flow rate is less than or equal to 650 gpm.
For Unit 1 Cycle 6 and after, and Unit 2 Cycle 5 and after:
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, and DI ABLO CANYON - UNITS 1 & 2 3/4 5-6 Amendment Nos.
65 & 64,72 8 71
CONTAINMENT SYSIEMS 3/4.6.2 DEPRESSURIZATION AND COOLING SYSTEMS CONTAINMENT SPRAY SYSTEM LIMITING CONDITION 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: MODES 1, 2, 3 and 4.
ACTION:
With one Containment Spray System inoperable, restore the inoperable Spray 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 inoperable Spray System to OPERABLE status within s
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 4.6.2.1 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, 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 psid when 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 its correct position on a Phase "B" Isolation test signal, and 2)
Verifying that each spray pump starts automatically on a Phase "B" Isolation test signal, d.
AY,leasb once per 10 years by performing an air or smoke flow test i
through each spray header and verifying each spray nozzle is unobstructed.
DIABLO CANYON - UNITS 1 & 2 3/4 6-11 Unit 1 - Amendment No.102 Unit 2 - Amendment No.101
I CCNTAINMENT SYSTEMS SPRAY ADDITIVE SYSTEM LIMITING CONDITION FOR OPERATION 3.6.2.2 The Spray Additive System shall be OPERABLE with:
a.
A spray additive tank with a contained volume of between 2025 and 4000 gallons of between 30 and 32% by weight NaOH solution, and b.
Two spray additive eductors each capable of adding NaOH solution from the chemical additive tank to a Containment Spray System pump flow.
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 STAND 2Y 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 REQUIREMENTS 4.6.2.2 The Spray Additive System shall be demonstrated OPERABLE:
a.
At least once per 31 days by verifying that each valve (manual, l
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 '.ank, and 2)
Verifying the concentration of the NaOH solution by chemical analysis.
c.
At least once per 18 months by verifying that each automatic valve in the flow path actuates to its correct position on a Containment Spray actuatjon test signal; and I
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
CONTAINMENT SYSTEMS 3/4.6.4 COMBUSTIBLE GAS CONTROL HYDRDGEN ANALYZERS / MONITORS LIMITING CONDITION FOR OPERATION 3.6.4.1 Two independent containment hydrogen analyzers / monitors shall be OPERABLE.
APPLICABILITY:
MODES 1 and 2.
ACTION:
a.
With one hydrogen analyzer / monitor inoperable, restore the inoperable analyzer / monitor 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 .
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 HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .
SURVEILLANCE REQUIREMENTS 4.6.4.1 Each hydrogen analyzer / monitor shall be demonstrated OPERABLE at least once per 92 days by performing a CHANNEL CALIBRATION using a zero and span gas.
1 DIABLO CANYON - UNITS 1 & 2 3/4 6-17 Amendment Nos. 73 & 72
CONTAINMENT SYSTEMS ELECTRIC HYDROGEN RECOMBINERS l
LIMITING CONDITION FOR OPERATION 3.6.4.2 Two independent Hydrogen Recombiner Systems shall be OPERABLE.
APPLICABILITY: MODES I 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 b.
At least once each refueling interval by:
l 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 cennections, deposits of foreign materials,etc.),and 3)
Verifying the integrity of all heater electrical circuits by l
performing a resistance to ground test following the above required functional test.
The resistance to ground for any I
heater phase shall be greater than or equal to 10,000 ohms.
DIABLO CANYON - UhlTS 1 & 2 3/4 6-18 Unit 1 - Amendment No. 73,102 Unit 2 - Amendment No. 72,101
TABLE 3.7-2 i
i i
STEAM LINE SAFETY VALVES PER LOOP i
LIFT SETTING (t 1%)*
ORIFICE SIZE 1065 psig 4.515 inches l
1078 psig 4.515 inches 1090 psig 4.515 inches, i
1103 psig 4.515 inches 1115 psig 4.515 inches
The lift setting pressure shall correspond to ambient conditions of the valve at nominal operating temperature and pressure.
t t
DIABLO CANYON - UNITS 1 1,2 3/4 7-3
I
=
PLANT SYSTEMS AUXILIARY FEEDWATER SYSTEM LIMITING CONDITION FOR OPERATION 3.7.1.2 At least three steam generator auxiliary feedwater pumps and associated flow paths shall be OPERABLE with:
Two motor-driven auxiliary feedwater pumps, each capable of being a.
powered from separate vital busses, and b.
One steam turbine-driven auxiliary feedwater pump capable of being powered from two OPERABLE and redundant steam supply sources.
APPLICABILITY: MODES 1, 2 and 3.
ACTION:
With one auxiliary feedwater pump inoperable, restore the required a.
auxiliary feedwater pumps to OPERABLE status within 72 hou.s 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 two auxiliary feedwater pumps inoperable, 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 HOT SHUTDOWN within the following 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .
With three auxiliary feedwater pumps inoperable, immediately initiate c.
corrective action to restore at least one auxiliary feedwater pump to OPERABLE status as soon as possible.
SURVEILLANCE REQUIREMENTS 4.7.1.2.1 Each auxiliary feedwater pump shall be demonstrated OPERABLE:
a.
At least once per 31 days by:
l 1)
Deleted.
I DIABLO CANYON - UNITS 1 & 2 3/4 7-4 Unit 1 - Amendment No. 62,102 Unit 2 - Amendment No. 61,101
3 PLANT SYSTEMS SURVEILLANCE REQUIREMENTS i
(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.
i 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.
I c.
At least once per 18 months by verifying that each auxiliary l
feedwater pump starts and valve opens
as designed automatically upon s
receipt of an Auxiliary Feedwater Actuation test signal.
i
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. GB,102 Unit 2 - Amendment No. 61,101
PLANT SYSTEMS AUXILIARY FEEDWATER SOURCE LIMITING CONDITION FOR OPERATION 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 capable of being aligned to the AFW pump suction.
APPLICABILITY: MODES 1, 2 and 3.
ACTION:
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 .
i b.
With an FWST usable volume less than 57,922 gallons for one Unit i
operation and 115,844 gallons for two Unit operation, or with the 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 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 cycle once per quarter.
DIABLO CANYON - UNITS 1 & 2 3/4 7-6 Amendment Nos. 75 & 74
3/4.10 SPECIAL TEST EXCEPTIONS 3/4.10.1 SHUTDOWN MARGIN LIMITING CONDITION FOR OPERATION 3.10.1 The SHUTDOWN MARGIN requirement of Specification 3.1.1.1 may be suspended for measurement of control rod worth and shutdown margin provided reactivity equivalent to at least the highest estimated control rod worth is available for trip insertion from OPERABLE control rod (s).
APPLICABILITY:
MODE 2.
ACTION:
a.
With any full-length control rod not fully inserted and with less than the above reactivity equivalent available for the trip insertion immediately initiate and continue boration at greater s
than or equal to 30 gpm of a solution containing greater than or equal to 7,000 ppm boron or its equivalent until the SHUTDOWN MARGIN required by Specification 3.1.1.1 is restored.
b.
With all full-length control rods fully inserted and the reactor subcritical by less than the above reactivity equivalent, immediately initiate and continue boration at greater than or equal to 30 gpm of a solution containing greater than or equal to 7,000 ppm boron or its equivalent until the SHUTDOWN MARGIN required by Specification 3.1.1.1 is restored.
SURVEILLANCE RE0VIREMENTS 4.10.1.1 The position of each full-length control rod either partially or fully withdrawn shall be determined at least once per 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months .
4.10.1.2 Each full-length control rod not fully inserted shall be demonstrated capable of full insertion when tripped from at least the 50%
withdrawn position within 7 days prior to reducing the SHUTDOWN MARGIN to less I
than the limits of Specification 3.1.1.1.
DIABLO CANYON - UNITS 1 & 2 3/4 10-1 Unit 1 - Amendment No. 53-74,102 Unit 2 - Amendment No. M,101
SPECIAL TEST EXCEPTIONS 3/4.10.2 GROUP HEIGHT, INSERTI0A AND POWER DISTRIBUTION LIMITS LIMITING CONDITION FOR OPERATION 3.10.2 The group height, insertion and power distribution limits of Specifica-tions 3.1.3.1, 3.1.3.5, 3.1.3.6, 3.2.1, and 3.2.4 may be suspended during the performance of PHYSICS TESTS provided:
a.
The THERMAL POWER is maintained less than or equal to 85% of RATED THERMAL POWER, and b.
The limits of Specifications 3.2.2 and 3.2.3 are maintained and deter-l mined at the frequencies specified in Specification 4.10.2.2 below.
APPLICABILITY:
MODE 1.
ACTION:
With any of the limits of Specifications 3.2.2 or 3.2.3 being exceeded while l
the requirements of Specifications 3.1.3.1, 3.1.3.5, 3.1.3.6, 3.2.1 and 3.2.4 are suspended, either:
a.
Reduce THERMAL POWER sufficient to satisfy the ACTION requirements of Specifications 3.2.2 and 3.2.3, or l
b.
Be in HOT STANDBY within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .
SURVEILLANCE REQUIREMENTS 4.10.2.1 The THERMAL POWER shall be determined to be less than or equal to 85%
of RATED THERMAL POWER at least once per hour during PHYSICS TESTS.
4.10.2.2 The requirements of the below listed specifications shall be performed at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months during PHYSICS TESTS:
a.
Specifications 4.2.2.2 and 4.2.2.3, and l
b.
Specification 4.2.3.2.
DIABLO CANYON - UNITS 1 & 2 3/4 10-2 Amendment Nos. 37 & 36, 71 & 70
RADI0 ACTIVE EFFLUENTS GAS STORAGE TANKS LINITING 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 10 curies noble gases (considered as Xe-133 equivalent).
APPLICABILITY: At all times.
ACTION:
a.
With the quantity of radioactive material in any gas decay tank 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 s
this condition in the next Annual Radioactive Effluent Release Report, pursuant to Specification 6.9.1.6.
b.
The provisions of Specification 3.0.3 are not applicable.
3.11.3 Deleted 3.11.4 Deleted SURVEILLANCE RE0VIREMENTS 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 7 days when radioactive materials are being added to the tank and at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months during primary coolant system degassing operations.
4.11.3 Deleted 4.11.4 Deleted DIABLO CAYON - UNITS 1 & 2 3/4 11-3 Unit 1 - Amendment No. 94,102 Unit 2 - Amendment No. 99,101

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