ML20197B701

Amends 123 & 121 to Licenses DPR-80 & DPR-82,respectively, Revise Combined TS for DCPP Unit 1 & 2 to Change Surveillance Frequencies from Once Every 18 Months to Once Per Refueling Interval

ML20197B701
Person / Time
Site:	Diablo Canyon
Issue date:	02/27/1998
From:	Steven Bloom NRC (Affiliation Not Assigned)
To:
Shared Package
ML20197B706	List: ML20197B701 ML20197B709
References
NUDOCS 9803110363
Download: ML20197B701 (26)

Text

- _ _ _ _ _ _ _ _ _ _ - _ _ _ - _ - _ _ _ _ _ _ _ - _

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t UNITED STATES g

,j NUCLEAR REGULATORY COMMISSION g

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PACIFIC GAS AND ELECTRIC COMPANY DOCKET NO. 50-275 DIABLO CANYON NUCLEAR POWER PLANT. UNIT NO. 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.123 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 May 14, 1997, as supplemented by letter dated October 9, 1997, 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 (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:

9803110363 980227 DR ADOCK 050002 5

-2 (2)

.T dLnical Soecifications 1

The Technical Specifications contained in Appendix A and the Environmental Protection Plan contained in Appendix B, as revised through Amendment No.123. are hereby incor)or ated in the license.

Pacific Gas and Electric Company s1all 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 issuance:

February 27, 1998

v er:g gj

• t UNITE 3 STATES.

j NUCLEAR REGULATORY COMMISSION s

t WASHINGTON. D.C. 3086H001

\\*...,/

I PACIFIC GAS AND ELECTRIC COMPANY DOCKET NO. 50-323 DIABLO CANYON NUCLEAR POWER PLANT. UNIT NO. 2 AMENDMENT TO FACILITY OPERATING llCENSE Amendment No.121 License No. DPR-82 1.

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

A.

The application for amendment by Pacific Gas and Electric Company (the licensee) dated May 14. 1997 as supplemented by letter dated October 9. 1997, 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 1:

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 rc.tulations:

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:

a

2 2

(2)

Technical Soecifications The Technical Specificatiois contained in Appendix A and the Environmental Protection Plan contained 'n Appendix B. as revised through Amendment No. 121. are hereby incoryorated in the license.

Pacific Gas and Electric Company s1all operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan, except where otherwise stated in specific license conditicis.

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

)

's Steven D. Bloom. Project Manager Project Directorate IV 2 Division of Reactor Projects Ill/IV Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical Specifications Date of issuance: February 27, 1998

l j

ATTACHMENT TO LICENSE AMENDMENTS AMENDMENT NO.123 TO FACILITY OPERAT!NG LICENSE NO OPR-80 AND AMENDMENT NO.121 TO FACILITY OPERATING LICENSE NO DPR 82 QQCEf.T NOS. 50 275 AND 50 323 Revise Appendix A Technical Specifications by removing the pages identified below and inserting the enclosed pages.

The tavised pages are identified b Amendment number and contain marninal lines indicating the areas of change.y The corresponding overleaf pages are also provided to maintain document completeness.

REMOVE INSERT 3/4 2-17 3/4 2-17 3/4 3 33 3/4 3 33 1

3/4 3 39 o/4 3 39 3/4 3 47 3/4 3 47 3/4 3 49 3/4 3 49 3/4 3-53 3/4 3 53 3/4 4 10a 3/4 4 10a 3/4 4-18 3/4 4-18 3/4 4 36 3/4 4-36 B 3/4 3-3c B 3/4 3 3c B 3/4 3 3d B 3/4 3 3d B 3/4 4 16 B 3/4 4-16

POWER DISTRIBUTION LIMITS LIMITING CONDITION FOR OPERATION 6CllDfMContinued) b.

Within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> of initially being outside the above limits, verify through incore flux mapping and RCS total flow rate comparison that the combination of R and RCS total flow rate cre restored to within i

the above limits, or reduce THERMAL POWER to less than 5% of RATED l

THERMAL POWER within the next 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />, c.

Identify and correct the cause of the <

of limit condition prior to increasing THERMAL POWER above the rt 4 THERMAL POWER limit required by ACTION a.2 and/or b.,

abov, subsequent POWER OPERATION l

may proceed provided that the combination of R and indicated RCS i

total flow rate are demonstrated, through incore flux mapping and RCS total flow rate comaarison, to be within the region of acceptable operation shown on rigure 3.2-3a for Unit 1 and Figure 3.2 3b for Unit 2 prior to exceeding the following THERMAL POWER levels:

1. A nominal 50% of RATED THERMAL POWER,

2. A nominal 75% of RATED THERMAL POWER, and

3. Within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> of attaining greater than or equal to 95% of RA1ED THERMAL POWER.

SURVEILLANCE REQUIREMENTS 4.2.3.1 The provisions of Specification 4.0.4 are not applicable.

4.2.3,2 The combination of indicated RCS total flow rate and R shall be I

determined to be within the region of acceptable operation of Figure 3.2 3a for Unit 1 and Figure 3.2 3b for Unit 2-a.

Prior to operation above 75% of RATED THERMAL POWER after each fuel loading, and b.

At least once per 31 Effective Full Power Days.

4.2.3.3 The indicated RCS total flow rate shall be verified to be within the region of acceptable operation of Figure 3.2 3a for Unit 1 and Figure 3.2 3b for Unit 2 at least on'ce per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> when the value of R, obtained per Specification 4.2.3.2. is assumed to exist.

4.2.3.4 The RCS total flow rate indicators shall be subjected to a CHANNEL CAllBRAT10N at least once per REFUELING INTERVAL.

l 4.2.3.5 The RCS total flow rate shall be determined by measurement at least once per REFUELING INTERVAL.

[

DIABLO CANYON - UNITS 1 & 2 3/4 2 l' Unit 1 - Amendment M,123 Unit 2 - Amendment W.121

_ POWER DISTRIBUTION LIMITS i

t 3/4.2.4 OUADRANT POWER TILT RATIO IIMITING CONDITION FOR OPERATION i

3.2.4 THE QUADRANT POWER TILT RATIO sha11 not exceed 1.02.

]

APPLICA81LITY:

MODE 1 AB0VE 50% OF RATED THERMAL POWER *.

j ACTION:

a.

With the QUADRANT POWER TILT RATIO de'termined to exceed 1.02 bu less than or equal to 1.09:

1,,

1 ate the QUADRANT POWER TILT RATIO at least once per hour 2

j a)

The QUADRANT POWER TILT RATIO is reduced t6 within its limit, or b)

THERHAL PCWER is reduced to less than 50% of RATED THERMA POWER.

2.

Within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> either:

a)

Reduce the QUADRANT POWER TILT RATIO to within its limit, i

i or b)

Reduce THERMAL POWER at least 35 from RATED THF.RMAL POW for each 1% of indicated QUADRANT POWER TILT RATIO in excess of I and similarly reduce the Power Range Neutron Flux-High Trip setpoints within the next 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.

3.

Verify that the QUADRANT POWER TILT RATIO is within its limit 4

within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> after exceeding the limit or reduce THERMAL POWER to less than 50% of RATED THERMAL POWER within the next 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> and reduce the Power Range Neutron Flux-High Trip tetpoints to less than or equal to 55% of RATED THERMAL POWER j

within the next 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />; and 4.

Identify and correct the cause of the out-of-limit condition prior to increasing THERMAL POWER; subsequent POWER OPERATION above 50% of RATED THERMAL POWER may proceed provided that the 4

QUADRANT POWER TILT RATIO is verified within its limit at least once per hour for 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> or until verified acceptable at 955 or greater RATED THERMAL POWER.

b.

With tiie QUADRANT POWER TILT RATIO determined to exceed 1.09 due to misalignment of either a shutdown or control rod:

1.

Calculate the QUADRANT POWER TILT RATIP at least once per hour until either:

i OSee Special Test Exceptions Specification 3.10.2 DIABLO CANYON - UNITS 1 & 2 3/4 2-18 Amendment Nos. 37 and 36 l

j Effective at end of Unit 1 Cycle 3

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W TABLE 4.3-2 (Continued) 9

'3 ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION m:

SURVEILLANCE REQUIREMENTS

}

E TRIP Q

ACTUATING CHANNEL DEVli MODES FOR

[

~

CHANNEL 0PERA-OPERA-MASTER SLAVE WHIG 1 CHANNEL CALI-TIONAL TIONAl ACTUATION RELAY RELAY St'RVEILLANCE !

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

3. Containment Isolation i

M a.

PhaseA' Isolatian l

1) Manual N.A.

N.A.

N.A.

R24 3.A.

N.A.

N.A.

1. 2. 3. 4 Y

2) Automatic Actuation N.A.

N.A.

N.A.

N.A.

M(1)

M(1)

R

1. 2. 3. 4 O

Logic and Actuation i

Relays l

c_,__

Li

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

2 b.

Phase "B' Isolation j

^

N~

1) Manial N.A.

N.A.

N.A.

R24 N.A.

N.A.

N.A.

1. 2. 3. 4

2) AL matic Actuation N.A.

N.A.

N.A.

N.A.

M(1)

M(1)

R 1.2.3.4' 4

@Rg logic and Actuation Relays 3

na

3) Containment S

R24 0

N.A.

N.A.

N.A.

N.A 1.2.3.4 Pressure-High-High j

i c.

Containment Ventilation

+

{33 Isolation i

oi

1) Automatic Actuation N.A.

N.A.

N.A.

N.A.

M(1)

M(1)

R

1. 2. 3. 4 o

Logic and Actuation

)

Relays m"

j lglg l

m;

2) Deleted

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

l3;3

3) Safety injection l

m;

4) Containment Ventilation l

3;3 Exhaust Radiation-High

m; (RM-41A and 448)

S 02 4 Q

N.A.

N.A.

N.A.

N.A.

1 2. 3. 4 l 12%

j$is i

--50 f

f

S TAK E 4.3-2 (Continued)

C 5

EEIKEtTD SAFETY F M11RES AC11RTION_ SYSTEM INSTRIEMIMIM SUML LLANCE REWIREENTS n>

1 5

TRIP ACTIRTING OMNNEL DEVICE IGES F(R l

iii OWOIEL OPERA-OPERA-INSTER SLAVE WIDI 1

Q OW8EL CALI-TIONAL TIONU.

ACTIRTI(El RELAY HELAY SLRVEILLANCE i

[ RBICTI(EIAL WIT DECK _.

MATIM TEST TEST LOGIC TEST 1EST IEiL IS KGUIRED

• 4. Steam'Line Isolation a.

Manual N.A.

N.A.

N.A.

R24 N.A.

N.A.

N.A.

1. 2. 3 b.

Automatic Actuation Logic N.A.

N.A.

N.A.

N.A.

W'8 W

R

1. 2. 3 arul Actuation Relays e

c. Contairment Pressure-S R24 Q

N.A.

N.A.

N.A.

N.A.

1, 2. 3 l

High-High

[

d.

Steam Line Pressure-Low S-R24 Q

N.A.

N.A.

N.A.

N.A.

1. 2. 3 l

e.

Negative Steam Line S

R24 0

N.A.

N.A.

N.A.

N.A.

3" l'

Pressure Rate-High El 5. Turbine Trip and Feechster Isolation a.

Automatic Actuation M.A.

N.A.

N.A.

N.A.

W" W"

R 1, 2 N

Logic and Actuation Relays kk b.

Steam Generatcr Water S

R24 Q

N.A.

N.A.

N.A.

N.A.

1. 2 l

aa Level-High-High 22 a a 6. Auxiliary Feedwater N.A.

N.A.

'1. 2. 3 a.

Manual.

N.A.

N.A.

N.A.

R N.a.

E.r.

YI

b. Automatic Actuation N.A.

N.A.

N.A.

N.A.

W" W"

R

1. 2. 3

$j Logic and Actuation Relays

~

~

33

c. Steam Generator Water

{*

Level-Low-low

1) Steam Generator S:

R24 0

N.A.

N.A.

N.A.

N.A.'

1. 2. 3" l

Water Level-Low-Low

2) RCS Loop AT Equivalent N.A.

R24 Q N.A. N.A. N.A. N 4.

1. 2

,-gg to Power i-.-.---...- I

~' TABLE 4.3-3 RADIATION MONITORING INSTRUMENTATION FOR PLANT OPERATIONS SURVEILLANCE REQUIREMENTS-S CHANNEL M00ES FOR WHICH 3; CHANNEL CHANNEL-FUNCTIONAL SURVEILLANCE 5 CHECK CALIBRATION TEST IS REQUIRED n35 1. Fuel Handling Building a. Storage Area-1)' Spent Fuel Pool S R 0 E 2) New Fuel Storage S R 0 b. Gaseous Activity Fuel Handling Building S R Q-Ventilation Mode Change (*' 2. Control Room Ventilatior Mode Change S R 0 All 3. Containment a. Gaseous Activity 1) Deleted 2) RCS Leakage S R 0 1.2.3.4 gg 3) Containment Venti-S R24 0 6 l lation Isolation ) (RH-44A or 448) l g J e b. Particulate Activity 1) Containment Venti-S R24 0 6 l lation Isolation (RM-44A or 448) ccg3 2) RCS Leakage S R 0 1.2.3.4 m-

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

[k (*) .The requirements for Fuel Handling Building Ventilation Mode Change are applicable following gg installation of RM-45A and 458. RR Ea l3l3 03E3

INSTRUMENTATION MOVABLE INCORE DETECTORS LIMITING CONDITION FOR OPERATION 3.1.3.2 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. APPLICABillTY: When the Novable Incore Detection System is used fort Recalibration of the Excore Neutron Flux Detection System, or a. b. Monitoring the QUADRANT POWER TILT RATIO, or Measurw.it of F,", F,(Z) and F,. c. EllDH: l 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 SURVElllANCE REQUIREMENTS 4.3.3.2 The Movable Incore Detection System shall be demonstrated OPERABLE at least once per 24 hours by nomalizing each detector output when required fer: Reca11bration of the Excore Neutron Flux Detection System, or a. b. Monitoring the QUADRANT p0WER TILT RATIO, or Neasurement of F,', F (Z) and F,. c. L DIABLO CANYON - UNITS 1 & 2 3/4 3-40 Unit 1 - Amendment No. M )f3 (Nextpageis3/43-44) Unit 2 - Amendment No. 64 '10 l

J11STAUMENTAT10N REMOTE SHUTDOWN INSTRUMENTATION AND CONTROLS LIMITING CONDITION FOR OPERATION 3.3.3.5 The remote shutdown monitoring instrumentation and control functions shown in Table 3.3 9 shall be OPERABLE. APPLICABILITY: MODES 1. 2 and 3. ACTION: a. With less than the minimum required Function (s) of Table 3.3-9 operable, restore the inoperable Function (s) to OPERABLE status within 30 days or be in HOT SHUTDOWN within the next 12 hours, b. The provisions of Specification 3.0.4 are not applicable. Se)arate entr Ta>1e 3.3 9. y into Action a. is allowed for each Function in c. SURVElltANCE REQUIREMENTS 4.3.3.5.1 Each remote shutdown monitoring instrumentation channel shall be demonstrated OPERABLE by performance of the CHANNEL CHECK and CHANNEL CAllBRATION at the frequencies shown in Table 4.3 6. 4.3.3.5.2 Verify each required control circuit and control transfer switch is capable of performing the intended function at least once every REFUELING INTERVAL. DIABLO CANYON - UNITS 1 & 2 3/4 3 47 Unit 1 - Amendment 94.123-- Unit 2 - Amendment 93.121

TABLE 3.3-9 REMOTE SHUTDOWN MONITOR NG INSTRIMENTATION AND CONTROLS REQUIRED I READ 0UT/ CONTROL NUMBER OF INSTRUMENT / CONTROL FUNCTION LOCATION CHANNELS 1. Reactor Trip Breaker Indication Reactor Trip henker 1/ trip breaker 2. Pressuriser Pressure Hot shutdown Panel 1 3. Pressurizar Level Hot shutdown Pane'l 1 4. Steam Generator Pressure Hot Shutdown Panel 1/sta. gen. 5. Steam Generator Wide Range Water Hot Shutdown Penel 1/sta, gen. Level 6. Condensate Storage Tank Water Hot shutdown Panel 1 Level 7. Auxiliary Feedwater Flow Hot Shutdown Panel 1/sta. gen. l 8. Charging Flow Hot Shutdcwn Panel 1 9. RCS Loop 1 Temperature Dedicated Shutdown Hot and Cold Leg Indication Panel Temperature Indication

30. Auxiliary Feedwater Flow Control

- AFW Pump, and Associated Valves Hot Shutdown Panel any 2 of 3 AFW j - Transfer Switches 4 kV Switchgear pumps 11. Charging Flow Control - Centrifugal Charging Pump Hot Shutdown Panel 2 of 2 pumps - Transfer Switch 4 kV Switchgear 22. Component Cooling Water Control - Component Cooling Water Pump Hot $hutdown Panel any 2 of 3 CCW - Transfer $ witch 4 kV Switchgear pumps

13. Auxiliary Saltwater Control

- Auxiliary Saltwater Pump Hot Shutdown Panel 2 of 2 pumps - Transfer Switch 4 kV Switchgear 14. Emergency Diesel Generator Control - EDG Start EDG Local Control Panel 3 of 3 EDGs DIABLO CANYON - UNITS 1 & 2 3/4 3-48 Amendment Nos. 94 and 93

TABLE 4.3 6 REMOTE SHUTDOWN MONITORING INSTRUMENTAfl0N SURVEILLANCE REQUIREMENTS CHANNEL CHANNEL INSTRUMENT CE CAllBRATION 1. Reactor Trip Breaker Indication N.A. N.A. L .2. Pressurizer Pressure M R24-l 3. Pressurizer Level M R24 l 4. Steam Generator Wide Range Water Level M R24 l S. Steam Generator Pressure M R24 l 6. Condensate Storage Tank Water Level M R24 l 7. Auxiliary Feedwater Flow M R24 l 8. Charging Flow M R24 l 9. RCS Loop 1 Temperature indication M R24 l l i OIABLO CANYON - UNITS 2 & 2 3/4 3 49 Unit 1 - Amendment 94.123 Unit 2 Amendment 93.121 j

INSTRUMENTATION ACCIDENT MOMITORING INSTRUMENTATION LIMITING CONDITION FOR OPERATION z I 3.3.3.6 The accident monitoring instrumentation channels shown in Table i 3.3-10 shall be OPERABLE. l APPLICABILITY: MODES 1, 2 and 3. I &C110H: ) a. With the number of OPERABLE accident monitoring instrumentation j channels less than the Required Number of Channels shown in l 1 Table 3.3-10, restore the inoperable channel (s) to OPERABLE status 1 within 7 days or be in at least NOT SHUTDOWN within the next 12 hours. b. With the number of OPERABLE accident monitoring instrumentation i channels except the containment recirculation sump level-narrow ] range, the main steam line radiation monitor, the containment area radiation monitor-high range, and the plant vent radiation monitor-l 1 high range less than the Minimum Channels OPERABLE requirements of J Table 3.3-10, restore the inoperable channel (s) to OPERABLE status within 48 hours or be in at least HOT SHUTD0WN within the next 12 hours. c. With the number of OPERABLE channels for the containment recirculation sump levtl-narrow range less than the Minimum Channels 1 OPERABLE requirement of Table 3.3-10, restore the inoperable channel to 00ERABLE status within 30 days or be in at least HOT SHUTDOWN l within the next 12 hours. d. With the number of OPERABLE channels for the main steam line I radiation monitor, or the containment area radiation monitor-high 3 range or the plant vent radiation monitor-high range less than the i Minimum Channels OPEP4BLE requirements of Table 3.3-10, initiate the preplanned alternate method of monitoring the appropriate i parameter (s )with'.n 72 hours and either restore the inoperable l channel (s) to OPERABLE status within 7 days or prepare and submit a Special Report to the Commission pursuant to specification 6.g.2 within 14 days that provides actians taken, cause of the inoperability and plans and schedule for restoring the channels to OPERABLE status, e. The provisions of specification 3.0.4 are not applicable. DIABLO CANYON - UNITS 1 & 2 3/4 3-50 Unit 1 - Amendment No.103 j Unit 2 - Amendment No.102 i a ____-____.-----*,,-c-- ,.i. m,.m 2 nw-., y-r-'w- -n - - - + - - -- -y

s TreLE 4.3-7 l ACCIDENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS 5 CHANNEL CHANNEL 5 INSTRUMENT CHECK CALIBRATION O 1. Containment Pressure M R24 [ 2. Reactor Coolant Outlet Temperature - T,,,, (Wide Range) M R24 l E 3. Reactor Coolant Inlet Temperature - T,,,,(Wide Range) M R24 l d 4. Reactor Coolant Pressure - Wide Range M R24 l [ 5. Pressurizer Water Level M R24 l m 6. Steam Line Pressure M R24 l 7. Steam Generator Water Level - Narrow Range M R24 l 8. Refueling Water Storage Tank Water Level M R24 l 9. Containment Reactor Cavity Supp Level-Wide Range M R24 l z o S

10. Containment Recirculation Sump Level-Narrow Range M

R24 l

11. Auxiliary Feedwater Flow Rate M

R24 l

12. Reactor Coolant System Subcoolino Margin Monitor M

R24 l

13. PORV Position Indicator M

R24 l

14. PORV Block Valve Position Indicator M

R24 l

15. Safety Valve Position Indicator M

R24 l 16. In Core Thermocouples M R24 l gg

17. Main Steam Line Radiation Monitor M

R24 l

18. Containment Area Radiation Monitor-High Range M

R24* l m-

19. Plant Vent Radiation Monitor-High Range M

R kk 20. Reactor Vessel Level Indication System M R24 l RR RR aa7

• CHANNEL CALIBRATION may consist of an electronic calibration of the channel, nat including the detector.

FE for range decades above 10 R/h and a one point calibration check of the detector below 10 R/h with an installed or portable gamma source. .. -... =

9 THIS PAGE INTENTIONALLY SLANK i DIABLO CANYON - UNITS 1 & 2 3/4 3-54 Unit 1 - Amendment No. H,120 Unit 2 - Amendment No. H,118 ~.

REACTOR COOLANT SYSTEM SURVEILLANCE REQUIREMENTS 4.4.4.1 In addition to the requirements of Specification 4.0.5, each PORV shall be demonstrated CPERABLE by: I Operating the PORV through one complete cycle of full travel during a. iDDES 3 or 4 with the block valves closed at least once per 18 l months, and 8 b. Performing a CHANNEL CAllBRATION of the actuation instrumentation at least once per REFUELING INTERVAL. iI l 4.4.4.2 In addition to the requirements of Specification 4.0.5. each block valve shall be demonstrated OPERABLE at least nnce per 92 days by o>erating the valve through one com)lete cycle of full travel unless the blocc valve is closed in order to meet tie requirements of ACTION b, or c. in Specification 3.4.4. 4.4.4.3 The safety-related nitrogen sup OPERABLE at least once per 18 months by: ply for the PORVs shall be demonstrated Isolating and venting the normal air supply, and a. b. Verifying that any leakage of the Class 1 Backup Nitrogen System is within its limits, and Operating the PORVs through one complete cycle of full travel. c. DIABLO CANYON - UNITS 1 & 2 3/4 4-10a Unit 1 - Amendment 27.81.103,123 Unit 2 - Amendment 25.80.102.121

i. j l j o TABLE 4.4-7 i 1 l E STEAM GENERA.;R TUSE WSPECTION [ 9 i z o IST SAMPLE INSPECTION 2ND SAMPLE INSPECTION 3RD SAMPLE INSPECTION f z t Semple Sire Result Action Required Remalt Action Required Result Action Required C* l A mwwmum of C-1 None N. A. N. A. N. A. N. A. I 5 S Tubes per. w S. G. e. C-2 Plug defective tubes C-1 None N. A. N. A. { e, and inspect addit Plug defect % tubes C-1 None 2S tubes in this S. G. C-2 and inspect additional C-2 Plug defective tubes I 4S tubes in this S. G. Perform acten for i, C-3 C-3 result of fu 4 ws Perform actio.' for a C-3 C-3 result of first N. A. N. A. t i f "w C-3 Inspect all tubes in All other i this S. G. plus de-S. G.s are None N. A. N. A. fective tubes and C-1 I mspect 25 tubes in S me S. G.s l each other S. G-Perform act% for N. A. N. A. C-2 but no C-2 result of second semple { Notificats to NRC S. G. are pursuant to $50.72 C-3 (b)(2) of 10 CFR Additionel Iw all tubes in Part 50 S. G. is C-3 each S. G. and plug l. defective tubes. Notificaten to NRC N. A. N. A. pursuant to 650.72 (b)(2) of 10 CFR Part 50 S - 3 "s '"during an ins,"ection"a*" d ~ "" ia '*' "ad *ad a i' '** """*" d ~ 5'a"* ia=" cad n i 4

~ REACTOR COOLANT SYSTEM 3/4.4.6 REACTOR COOLANT SYSTEM LEAKAGE LEAKAGE DETECTION SYSTEMS LIMITING CONDITION FOR OPERATION 3.4.6.1 The following Reactor Coolant System Leakage Detection Systems shall be OPERABLE: a. The Containment Atmosphere Particulate Radioactivity Monitoring

System, b.

The Containment Structure Sumps and the Reactor Cavity Sump Level and Flow Monitoring System, and c. Either the Containment fan Cooler Collection Monitoring System or the Containment Atmosphere Gaseous Radioactivity Monitoring System. APPLICABILI1f: MODES 1, 2, 3 and 4. ACTION: l With only two of the above required Leakage Detection Systems OPERABLE, operation may continue for up to 30 days provided grab samples of the containment atmosphere are obtained and analyzed at least once per 24 hours when the required Gaseous and/or Particulate Radioactivity Monitoring System is inoperable: otherwise, be in at least HOT STANDBY within the next 6 hours and in COLD SHUTDOWN within the following 30 hours. SURVElllANCE RE0VIREMENTS 4.4.6.1 The Leakage Detection Systems shall be demonstrated OPERABLE by: a. Containment Atmosphere Particulate and Gaseous (if being used) Monitoring System oerformance of CHANNEL CHECK, CHANNEL CAllBRATION and CHANNEL FUNCTIONAL TEST at the frequencies specified in Table 4.3 3, b. Containment Structure Sumps and the Reactor Cavity Sump Level and Flow Monitoring System oerfe mance of CHANNEL CALIBRATION at least once per REFUELING INTERV'., and l c. Containment Fan Cooler Collection Monitoring System (if beinn used) - performance of CHANNEL FUNCTIONAL TEST at least once per REFUELING INTERVAL. l l l l l 1 DIABLO CANYON UNITS 1 & 2 3/4 4 18 Unit 1 - Amendment No.123 l Unit 2 - Amendment No.121 . -...~ --.

REAtTOR C00LANT 3111 3 DVIRPRES$URE PROTECTION SYSTDt3 LIMfTING CONDITION FOR OPERATION 3.4.g 3 The following Overpressure Protection Systems shall be OPERA 8LE: Two Class I power-operated relief valves (PORVs) w!th a lift setting a. of less than or equal to 435 psig, or I b. TheReactorCoolantSystem(RCS)depressurizedwithanRCSventof greater than or equal to 2.07 square inches. APPL 1tABILLTY: MODE 4 when the temperature of any RCS cold leg is less than or equal to 2LO'F, MODE 5 and MODE 6 wit? the reactor vessel head on and the l vessel head closure bolts not fully e. tensioned. Ell @ With one Class 1 PORV inoperable in MODE 4, restore the inoperable a. PORY to OPERABLE status within 7 days or depressurize and vent the RCS through an RCS vent of greater than or equal to 2.07 square inches vent within the next 8 hours, b. With one Class 1 PORV inoperable in MODES 5 or 6 with the reactor vessel head on and the vessel head closure bolts not fully detensioned, restore the inoperable PORV to operable status within 24 hours or depressurize and vent the RCS througi an RCS vent t,f greater than or equal to 2.07 square inches within the next 8 hours. With both PORVs inoperable, depressurize and vent the RCS through an c. RCS vent of greater than or equal to 2.07 square inches vent within 8

hours, d.

In the event either the PORVs or the RCS vent are used to mitigate an RCS pressure transient, a special Report shall be prepared and submitted to U.e Commission pursuant to Specification 6.g.2 within 30 days. The report shall describe the circumstances initiating the transient, the effect of the PORVs or vent on the transient, and any correct;ve action necessary to prevent recurrence. DIABLD CANYON - UNITS 1 & 2 3/4 4-35 Unit 1 - Amendment No. Mr61.100 Unit 2 - Amendment No. Mr60,99

4 i REACTOR COOLANT SYSTEM SURVEILLANCE REOUIREMENTS 4.4.9.3.1 Each Class 1 PORV shall be demonstrated OPERABLE by: a. Performance of a CHANNEL OPERATIONAL TEST on the PORV actuation channel, but excluding valve operation. at least once per 31 days: b. Performance of a CHANNEL CAllBRATION on the PORV actuation channel at l least once per REFUELING INTERVAL: and c. Verifying the PORV isolation valve is open at least once per 72 hours when the PORV is being used for overpressure protection. 4.4.9.3.2' The RCS vent shall be verified to be open when the vent is being used for overpressure protection at least once per 31 days when the pathway is provided by a valve (s) that is locked, sealed. or otherwise secured in the open position; otherwise verify the vent pathway every 12 hours. l DIABLO CANYON - UNITS 1 & 2 3/4 4-36 Unit 1 - Amendment SI.103.123 Unit 2 Amendment 80.102.121

i INSTRtMINTATION l ) Ba5ES 3 /4.3.3. 5 REMTESMtJTDOWNINSTRUMENTATION(Continued) In these MODES, the facility is already suberitical and in a condition of reduced RC5 energy. Under these conditions, considerable time is available to restore necessary instrument control functions if control rosa instruments or i controls become unavailable. ACTIONS Action a. i Action a. addresses the situation where one or more required Functions (instrument or control) of the Remote Shutdown Instrumentation and Controls i are inoperable. This includes any Function listed in Table 3.3-9, as well as r the control and transfer switches. The Required Action (Action a.) is to restore the required Function to OPERABLE status within 30 days. The Allowed Outage Time (A0T) is based on operating experience and the low probability of an event that would require evacuation of the control room. l If the Required Action and associated A0T of Action a is not met, the unit must be brought to a MODE in which the LCD does not apply. To achieve this status, the unit must be brought to MODE 4 within 12 hours. The A0Ts are reasonable, based on operating experience, to reach the required unit conditions from full power conditions in an orderly manner and without challenging unit systems. 1 Action b. Action b. excludes the MODE change restriction of TS 3.0.4. This exception allows entry into an applicable MODE while relying on the ACTIONS even though the ACTIONS may eventually require a unit shutdown. This exception is accept'dble due to the low probability of an event requiring remote shutdown and because the equipment can generally be repaired during operation without significant risk of spurious trip. Action c. Action c. t,s been added to the ACTIONS to clarify the application of A0'i rules. Sep rate Condition entry is allowed for each Function listed on Table 3.3-9. The A0T(s) of the inoperable channel (s) of a Function will be tracked separately for each Function starting from the time the Condition was entered for that Function. DIABLO CANYON - UNITS I & 2 8 3/4 3-3b Amendment Nos. 94 and 93

INSTRUMENTATION BASES 3/4.3.3.5 REMOTE SHUTDOWf TRUMENTATION (Continued) SURVEILLANCE REQUIREMENTS SR 4.3.3.5.1 Performance of the CHANNEL CHECK once every 31 days ensures that a gross failure of instrumentation has not occurred. A CHANNEL CHECK is a com)arison of the parameter indicated on one channel to a similar parameter on otler channels. It 1s based on the assumption that instrument channels monitoring the same parameter should read approximately the same value. Significant deviations between the two instrument channels could be an indication of excessive instrument drift in one of the channels or of something even more serious. CHANNEL CHECK will detect gross channel failure: thus, it is key to verifying that the instrumentation continues to operate properly between each l CHANNEL CAllBRAT10N. Agreement criteria are determined by the unit staff based on a combination of the channel instrument uncertainties including indica. tion and readability. If the channels are within the match criteria it is an indication that the channels are OPERABLE. If the channels are normally off scale during times when Surveillance is required, the CHANNEL CHECK will verify only that they are off scale in the same direction. Offscale low current loop channels are verified to be reading at the bottom of the range and not failed downscale. The frequency of 31 days is based upon operating experience which demonstrates that channel failure is rare. CHANNEL CAllBRATION is a complete check of the instrument loop and the sensor. The test verifies that the channel responds to measured parameters with the necessary range and accuracy. The frequency of once per REFUELING INTERVAL is base upon operating l experience-and consistency with the typical industry refueling cycle. SR 4.3.3.5.2 SR 4.3.3.5.2 verifies each required Remote Shutdown Instrumentation and Controls control circuit and transfer switch >erforms the intended function. This verification is performed from the hot slutdown panel and at other locations for certain control transfer switches, as a>propriate. This will ensure that if the control room becomes inaccessible, tie unit can be placed and maintained in MODE 3 from the hot shutdown panel and the local control stations. The once per REFUEllNG INTERVAL Frequency is based on the need to perform this l Surveillance under the conditions that ap>1y during a plant outage and the potential for an unplanned transient if tie Surveillance were performed with the reactor at power. (However, this Surveillance is not required to be DIABLO CANYON - UNITS 1 & 2 B 3/4 3 3c Unit 1 - Amendment No. 94.123 ~ Unit 2 - Amendment No. 92.121

INSTRUMENTATION BtSES 3/4.3 3.5 REMOTE SHUTDOWN INSTRUMENTATION (Contdaued) performed only during a unit outage.) Operating axn'.ience demonstrates that remote shutdown control channels usually pass the durveillance test when performed at the once per REFUELING INTERVAL frequency. l NOTE: A surveillance of the reactor trip breaker OPERABILITY is not recuired as part of the SURVEILLANCE REQUIREMENT for 4.3.3.S.2 since a TRIP ACTUATING' DEVICE OPERATIONAL TEST of the reactor trip breakers is performed as part of the SURVEILLANCE REQUIREMENT for TS 3/4.3.1 (See Table 4.3-1 Item 21 and Note 10). REFFRENCES 1. 10 CFR 50. Appendix A. GDC 19, 3/4.3.3.6 ACCIDENT MONITORING INSTRUMENTATION The OPERABILITY of the accident monitoring instrumentation ensures that sufficient information is available on selected )lant parameters to monitor and I assess these variables following an accident. T1e normal plant instrument channels specified are suitable for use as post-accident instruments. This capability is consistent with the recommendations of Regulatory Guide 1.97. Revision 3. " Instrumentation for Light Water-Cooled Nuclear Power Plants to Assess Plant Conditions During and Following an Accident." May 1983, and NUREG 0737 " Clarification of TMI Action Plan Requirements." November 1980. 3/4.3 3.7 DELETED DIABLO CANYON - UNITS 1 & 2 B 3/4 3 3d Unit 1 - Amendment 94-MG.123 Unit 2 - Amendment 93-148,121 u a

INSTRUMENTAT!DN ~ ~ ~~~~ ~ ~~~~~ BASES 3/4.3.3.9 RADI0 ACTIVE Lf 001D EFFLUENT MONITORING INSTRtMENTATI*ON Section relocated to MCP, DIABLO CANYON - UNITS 1 & 2 8 3/4 3-4 Amendment Nos. 64 & 66 75 & 74

REACTOR COOLANT SYSTEM BASES ,f PRES $URE/ TEMPERATURE LIMITS (Continued) heatup rates when the 1/4T flaw is considered. Therefore, both cases have to be analyzed in order to assure th:t at ar.y coolant temperature the lower value of the allowable pressure calculamd for steady-state and finite heatup rates is obtained. The second portion of the heatup analysis concerns the calculation of pressure-temperature limitations for the case in which a 1/4T deep outside surface flaw is assumed. Unlike the situation at the vessel inside surface, the thermal gradients established at the outside surface during heatup produce stresses which are tensile ih nature and thus tend to reinforce any pressure stresses present. These thermal stresses, of course, are dependent on both the rate of heatup and the time (or coolant temperature) along the heatup ramp. Furthermore, since the thermal stres es at ths outside are tensile and increase Wth increasing heatup rate, a lower bound curve cannot be defined. Rather, each heatup rate of interest must be analyzed on an individual basis. Following the generation of pressure-temperature curves for both the steady-state and finite heatup rate situations, the final limit curves are produced as follows. point comparison of the steady-state and finite heatup rate data.A composite cu At any given temperature, the allowable pressure is taken to be the lesser of the three values taken from the curves under consideration. The use of the composite curve is necessary to set conservative heatup l limitations because it is possible for conditions to exist such that over the course of the heatup ramp the controlling condition switches from the inside to the outside and the pressure limit must at all times be based on analysis of the most critical criterion. LOW TEMPERATURE OVEURESSURE PROTECTION The OPERABILITY of both Class 1 PORVs or e.n RCS vent opening of at least 2.07 square inches ensures that the RC3 will be protected from pressure transients that could exceed the limits of Appendix G to 10 CFR Part 50 when operating at low temperatures. Low temperature is defined as less than or equal to the reactor coolant temperature corresponding to a reactor vessel wall temperature of RT 90'F, where RT is evaluated at the beltline location (1/4T), whichis+ controlling in Ee Appendix G Pressure-Temperature (60*F/hr heatup) limits. This definition is consistent with Branch Technical Position RSS 5-2, and defines the LTOP enable temperature of 270'F, applicable through 12 EFPY. DIABLO CANYON - UNITS 1 & 2 B 3/4 4-15 Unit 1 - Amendment No. Sh98.100 Unit 2 - Amendment No. 8b97,99

l REACTOR COOLANT SYSTEM BASES LOW TEMPERA 1URE OVERPRESSURE PROTECTION (Continued) OPERABILITY of the PORVs for LTOP use requires a lift settino of less than or equal to 435 psig. This setpoint ensures that either Clt. 1 PORV has adequate relieving capability to protect the RCS from overpressurization for all anticipated transients concurrent with any single active failure. The ~ limiting transient for LTOP is a mass injection event based on the combined ECCS injection line flow from one centrifugal charging pump and the positive displacement pump, into a water-sold RCS, with letdown isolated. The 435 psig setpoint was determined for this event based on a PORV stroke time less than - or equal to 3.5' seconds, reactor service less than or equal to 12 EFPY, and administrative controls on RCP operation, charging pump operability. and the i ECCS injection flow path. The instrument uncertainties are not included in the Technical Specification setpoints. Uncertaintie:, associated with LTOP instrumentation were determined in accordance with the guidance provided in WCAP 14040 NP,A. An allowance for the pressure uncertainty is provided by administrative controls as discussed above. The Maximum Allowed PORV Setpoint for the LTOPs will be modified. if required, based on the results of examinations of the reactor vessel material irradiation surveillance specimens-performed as required by 10 CFR Part 50. A)pendix H. The surveillance specimen withdrawal schedule is maintained in tie FSAR Update. 1 DIABLO CANYON - UNITS 1 & 2 B 3/4 4-16 Unit 1 Amendment 98-MO.123 Unit 2 - Amendment 9;u)9.121 ..}}