Text

Amends 120 & 118 to Licenses DPR-80 & DPR-82,respectively, Authorizing Removal of Ten Sections from TS & Relocating Requirements to Equipment Control Guidelines
	ML20203M427
Person / Time
Site:	Diablo Canyon
Issue date:	02/03/1998
From:	Steven Bloom; NRC (Affiliation Not Assigned)
To:	;
Shared Package
ML20203M429	List: ML20203M427; ML20203M432;
References
	NUDOCS 9803060394
	Download: ML20203M427 (48)
	v • d • e

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I

[p uaybl UNITED STATES g

g NUCLEAR REGULATORY COMMISSION t

WASHINGTON, D.C. 30666-0001 A

'49.... +,6 PACIFIC GAS AND ELECTR!C COMPANY QOCKET NO. 50 275 DIABLO CANYON NUCLEAR POWER PLANT. UNIT NO. 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 120 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 October 4. 1995, as supplemented by letters dated July 17, 1996, August 20, 1996, and June 2, 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 7 0 visions 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 a urity or to the health and safety of the public; and l-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 ai indicated in the attachment to this license amendment.

and paragraph 2

2) of Facility Operating License No. OPR-80 is hereby amended to rear.

follows:

9803060394 980203 PDR ADOCK 05000275 PDR P

a L

L' - (2)

Tec.hnical Soecifications The Technical Specifications contained in Appendix A and the Environmental Protection Plan contained in Appendix B, as revised through Amendment No. 120, are hereby incorporated in the license.

Pacific Gas and Electric Company shall operate the facility in

)

accordance with the Technical Specifications and the rnvironmental Protection Plan, except where otherwise stated in specific license conditions.

In addition, the license is amended to add paragraph 2.C(12) to Facility Operating License No. DPR-80 as follows:*

(12) Additional Cone tions The Additional Conditions contained in Appendix D. as revised through Amendment No. 120, are hereby incorporates into this license.

Pacific Gas and Electric Company shall operate the facility in accordance with the Additional Conditions.

3.

The license amendment is effective as of its date of issuance to be implemerted within 90 days of issuance, implementation of the license amendment shall include the relocation of certain technical specification requirements to the appropriate licensee controlled document as described in the licensee's application dated October 4 1995, as supplemented by letters dated July 17, 1996. August 20, 1996, and June 2, 1997, and evaluated in the staff's safety evaluation attached to this amendment.

F0, THE NUCLEAR REGULATORY COMMISSICN s

-Steven D. Bloom Project Manager Project Directorate IV-2 Division of Reactor Projects III/IV Office of Nuclear Reactor Regulation Attachments:

1.

Changes to the Technical Specifications 2.

Pages 8 and 9 to License 3.

Appendix D AdditionaiConditions Date of issuance:

February 3. 1998

Pages 8 and 9 are attached, for convenience, for the composite license to reflect this change.

_a

8 (8)

Control of Heavy loads (SSER 27.Section IV 6)

Prior to startup following the first refueling outage. the licens?e shall submit commitments necessary to implement changes and modifications as required to satisfy the guidelines of Section 5.1.2 through 5.1.6 of NUREG-0612 (Phase II:

9-month responses to the NkC Generic Letter dated December 22, 1980).

(9)

Emeraency Preoaredness (SSER 27.Section IV 3)

In the event that the NRC finds that the lack of progress in completion of the procedures in the Federal Emergency Management Agency's final rule, 44 CFR Part 350, is an indication that a major substantive oroblem exists in achieving or maintaining an adequate state of preparedness the provisions of 10 CFR Section 50.54(s)(2) will apply.

(10) Masonry Walls (SSER-27.Section IV 4: Safety Evaluation of November 2. 1984)

Prior to start-up following the first refueling outage, the licensee shall (1) evaluate the differences in margins between the staff criteria as set forth in the Standard Review Plan and the criteria used by the licensee, and (2) provide justification acceptable to the staff for those cases where differences exist between the staff's and the licensee's criteria.

(11) Snent Fuel 9001 Modification The licensee is authorized to modify the spent fuel pool as described in the application dated October 30, 1985 (LAP. 85-13) as supplemented.

Amendment No. 8 issued on May 30, 1986 and stayed by the U.S. Court of Appeals for the Ninth Circuit pending completion of NRC hearings is hereby reinstated.

Prior to final conversion to the modified rack design, fuel may be stored. 6 aeded, in either the modified storage racks described in Technical Specification 5.6.1.1 or in the unmodified storage racks (or both) which are designed and shall be maintained with a nominal 21-inch center-to-center distance between fuel assemblies placed in the storage racks.

(12) Additional Conditions The Additional Conditions contained in Appendix D. as revised through Amendment No. 120. are hereby incorporated into this license.

Pacific Gas and Electric Company shall operate the facility in accordance with the Additional Conditions.

D.

Exemotion Exemption from certain requirements of Appendix J to 10 CFR Part 50 is described in the Office of Nuclear Reactor Regulation's Safety Evaluation Report. Supplement No. 9.

This exem) tion is authorized by law and will not endanger life or property or tie common defense and security and is otherwise in the public interest. Therefore. this exemption, previously granted in Facility Operating License No. DPR-76.

is hereby reaffirmed.

The facility will operate, to the extent authorized herein in conformity with the application, as amended. the provisions of the Act, and the regulations of the Commission.

Amendment No. e2.120

I 9

j E.

Physical Protection The licensee shall fully implement and maintain in effect all provisions of the Commission approved physical security, guard training and qualification. and safeguards contingency plans including amendments made pursuant to provisions of the Miscellaneous Amendments and Search Requirements revisions to 10 CFR 73.55 (51 FR 27817 and 27822) and to the authority of 10 CFR 50,90 and 10 CFR 50.54(p).

The plans, which contain Safeguards Information protected under 10 CFR 73.21 are entitled:

"Diablo Canyon Power Plant, Units 1 and 2 Physical Security Plan " with revisions submitted through March 4, 1988; "Diablo Canyon Power Plant. Units 1 and 2 Security Force Training and Qualification Plan " with revisions submitted through ^must 16, 1985; and "Diablo Canyon Power P1 nt, Units 1 and 2 Safe m s Contingency Plan," with revisions submitted through November 9, b l.

Changes made in accordance with 10 CFR 73.55 shall be implemented in accordance with the schedule set forth therein.

F.

Antitrust Pacific Gas and Electric Company shall comply with the antitrust conditions in Appendix C to this license.

G.

Reoortina PG&E shall report any violations of the requirements contained in Sections 2.C(3) through 2.C(10). 2.E and 2.F. of this License within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

Initial notification shall be made in accordance with the provisions of 10 CFR 50.72 with written follow-up in accordance with the procedures described in 10 CFR 50.73 (b), (c), (d) and (e).

H.

Financial Protection PG&E shall have and maintain financial protection of such type and in such amounts as the Commission shall require in accordance with Section 170 of the Atomic Energy Act of 1954, as amended, to cover public liability claims.

I.

_., of License This License is effective as of the date of issuance and shall expire at midnight on September 22, 2021.

FOR THE NUCLEAR REGULATORY COMMISSION Original signed by:

Edson G. Case for Harold R. Denton. Director Office of Nuclear Reactor Regulation Attachments:

1.

Appendix A - Technical Specifications 2.

Appendix B - Environmental Protection Plan 3.

Appendix C - Antitrust Conditions 4

Appendix 0 - Additional Conditions l

Date of Issuance:

November 2. 1984 Amendment No. 32.75.97.120

. a ADoendix D i

1 ADDITIONAL CONDITIONS FACILITY OPERATING LICENSE NO. DPR-80 Pacific Gas & Electric Com the schedules noted below:pany shall comply with the following conditions on Amendment Implementation

. Number Additional Condition Date 120 The licensee is authorized to relocate The amendment certain technical specifications shall be requirements to the equipment control implemented guidelines (ECGS) as referenced in the within 90 days Updated Final Safety Analysis Report.

of its issuance.

Implementation of these amendments shall include relocation of these technical specification requirements to the ECGS as described in the licensee's application dated October 4. 1995, as-supplemented by letters dated July 17, 1996. August 20, 1996, and June 2,1997, and evaluated in the staff's safety evaluation dated February 3. 1998, l

Amendment No. 120 i

I

[jono lt UNITED STATES i

j NUCLEAR REGULATORY COMMISSION

'2 WASHINGTON, D.C. 3066H001

$9.....,[

PACIFIC GAS AND ELECTRIC COMPANY DOCKET NO. 50-3T DIABLO CANYON NUCLEAR POWER PLANT. UNIT NO 2 AMENDMENT TO FAClllTY OPERATING LICENSE Amendment No. 118 License No. DPR 82 1.

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

A.

The application--for amendment by Pacific Gas and Electric Company (the licensee) dated October 4, 1995, as supplemented by letters dated July 17, 1996, August 20. 1996, and June 2. 1997, complies l-with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's_ regulations set fortn 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 (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:

.-.---_--._--.._.~.-.--.------.n._-

1 I

2 a -

' ( 2)-

Technical SDecifications-4 The Technical Specifications contained in Appendix A and the Environmental Protection Plan contained in Appendix 8. as revised.

4 ~

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.

4 l'

In-addition, the license is amended to add paragraph 2.C(12) to Facility i

Operating License No-DPR 82 as follows:

(11)--Additional Conditions 1-The Additional Conditions contained in Appendix D. as revised through Amendment No. 118. are hereby incorporated into this license.

Pacific Gas and Electric Company shall operate the 4

facility in accordance with the Additional Conditions.

3.

The license. amendment is effective as of its date of issuance to be

-implemented within-90 days of issuance.

Implementation of the license amendment shall include the relocation of.certain technical-specification requirements to the appropriate licensee-controlled document as described in-the licensee's application dated October 4 1.995. as supplemented by letters dated July 17, 1996. August 20, 1996.

and June 2. 1997, and evaluated in the staff's safety evaluation attached to this amendment.

4 FOR THE NUCLEAR REGULATORY. COMMISSION 2

Steven D. Bloom. Project Manager Project Directorate IV-2 Division of Reactor Projects III/IV Office of Nuclear Reactor Regulation Attachments:

1.

Changes to the Technical Specifications 2.

Pages 6 and 7 to License 3.

Appendix D Additional Conditions c -

Date of Issuance:

February 3. 1998

Pages 6 and 7 are attached, for convenience, for the compositt. license to reflect this change.

I

I 6

(10)

Pioeway Structure DE and DDE Analysis (SSER 32. Section 4) 4 Prior to start-up following the first refueling outage PG&E shall complete a confirmatory analysis for the pipeway structure to further demonstrate the adequacy of the pipeway structure for load combinations that include the acsign earthquake (DE) and double design earthquake (DDE).

(11) Additional Conditions The Additional Conditions contained in Appendix D. as revised through Amendment No. 118, are hereby incorporated into this license.

Pacific Gas and Electric Company shall operate the facihty in accordance with the Additional Conditions.

D.

Exemotion (SSER 31. Section 6.2 6)

An exemption from certain requirements of Appendix J to 10 CFR Part 50 is described in the Office of Nuclear Reactor Regulation's Safety Evaluation Report, Supplement No. 9.

This exem) tion is authorized by law and will not endanger life or property cr t1e common defense and security and is otherwise in the public interest, Therefore, this exemption previously granted in Facility Operating License No. DPR 81 pursuant to 10 CFR 50.12 is hereby reaffirmed. The facility will operate, with the exemption authorized, in conformity with the application as amended, the provisions of the Act, and the regulations of the Commission.

E.

Physical Protection (SSER 31 and SSER 321 PG&E shall fully implement and maintain in effect all provisions of the Commission-approved physical security guard training and qualification, andsafeguardscontingencyplans,inciudingamendmentsmadepursuantto the authority of 10 CIR 50.54(p) and 10 CFR 50.90.

These plans, which contain Safeguards Information as described in 10 CFR 73.21, are entitled:

"Diablo Canyon Power Piant Physical Security Plan." with revisions submitted through August 30, 1984: "Diablo Canyon Power Plant Guard Training and Qualification Plan," with revisions submitted through August 29, 1984: and "Diablo Canyon Power Plant Safeguards Contingency Plan," with revisions submitted through August 29. 1984.

F.

Antitrust PG&E shall comply with the antitrust conditions in Appendix C to this license.

Amendment No. 118

i i

7 I

G.

ReDortina Except as otherwise provided in the Technical Specifications or Environmental Protection Plan, the licensee shall report any violations of the requirements contained in Section 2.C of this license in the following manner:

initial notification shall be made within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months to the NRC Operations Center via the Emergency Notification System with written followup within thirty days in accordance with the procedures described in 10 CFR 50.73(b), (c), and (e).

H.

Financial Protettion PG&E shall have and maintain financial protection of such type and in such amounts as the Commission shall require in accordance with Section 170 of the Atomic Energy Act of 1954, as amended, to cover public liability claims.

I, Term of License This License is effective as of the date of issuance and shall expire at midnight on April 26, 2025.

FOR THE NUCLEAR REGULATORY COMMISSION Original signed by:

Harold R. Denton Harold R. Denton, Director Office of Nuclear Reactor Regulation Attachments:

1.

Appendix A - Technical Specifications (NUREG-1151) 2.

Appendix B - Environmental Protection Plan 3.

Appendix C Antitrust Conditions 4

Appendix D - Additional Conditions l

Date of Issuance: August 26, 1985 Amendment No. %,118

Anoendix D ADDITIONAL CONDITIONS FACILITY OPERATING LICENSE NO DPR 82 Pacific Gas & Electric Company shall comply with the following conditions on the schedules noted below:

Amendment Implementation Number Additional Condition Date 118 The licensee is authorized to relocate The amendment certain technical specifications shall be requirements to the equipment control implemented guidelines (ECGS) as referenced in the within 90 days Updated Final Safety Analysis Report.

of its issuance.

Implementation of these amendments shall include relocation of these technical specification requirements to the ECGS as described in the licensee's application dated October 4, 1995, as supplemented by letters dated July 17. 1996. August 20, 1996, and June 2. 1997, and evaluated in the staff's safety evaluation dated February 3, 1998.

Amendment No. 118 9

ATTACHMENT TO LICENSE AMENDMENiS AMENDMENT NO 120 TO FACILITY OPERATING LICENSE NO. DPR-80 AND AMENDMENT NO. 118 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 iv iv v1 vi vii vil 1x 1x xi xi x1v xiv xv1 xv1 1-2 1-2 3/4 1-8 3/4 1-8 3/4 1-16 3/4 1 16 3/4 1-18 3/4 1-18 3/4 1-19 3/4 1-20 3/4 3-40 3/4 3-40 3/4 3-41 3/4 3-42 3/4 3-43 3/4 3-44 3/4 3-44*

3/4 3-54 3/4 3-54 3/4 3 59 3/4 3-59*

3/4 3-60 3/4 6-1 3/4 6 1 3/4 6-2 3/4 6-3 3/4 6-4 3/4 6-9 3/4 6-9 3/4 8-19 3/4 8-20 3/4 8-21

No changes were made to these pages; reissued to become one-sided pages.

REMOVE INSERT B 3/4 3-3 B 3/4 3-3 B 3/4 3 3d B 3/4 3 3d B 3/4 3-5 B 3/4 3-5 B 3/4 6-1 B 3/4 6 1 B 3/4 6-2 B 3/4 6-2 B 3/4 8-3a B 3/4 8-3a B 3/4 8 3b

I i

.lN,p[f SAFETY LIMITS AND LIMITING SAFETY SYSTEM SETTINGS SECTION g

4 i

2.1 SAFETY LIMITS 2.1.1 REACTOR C0RE.....................................................

2-1 2.1.2 REACTOR COOLANT SYSTEMPRESSURE..................................

2-1 FIGURE 2.1-1 REACTOR CORE SAFETYLIMIT..................................

2-2 2.2 LIMITING SAFETY SYSTEM SETTINGS 4

s, 2.2.1 REACTOR TRIP SYSTEM INSTRUMENTATION SETP0!NTS....................

2-3 TABLE 2.2-1 REACTOR TRIP SYSTEM INSTRUMENTATION TRIP SETP0!NTS 2-4 BASES I

SECTION Pgg 2.1 SAFETY LIMITS i

2.1.1 REACTOR C0RE.....................................................

B 2-1 i

)

2.1. 2 REACTOR COOLANT SYSTEM PRESSURE..................................

B 2-2 2.2 LIMITING SAFETY SYSTEM SETTINGS 2.2.1 REACTOR TRIP SYSTEM INSTRUMENTATION SETP0!NTS.....................

8 2-3 l

1 t

DIABLO CANYON - UNITS 1 & 2 111 Amendment Nos. 60 and 59 l

INDEX llMITING CONDITIONS FOR OPERATION AND SURVElllANCE-REQUIREMENTS SECTIOS PAGE 3/4.0 APPLICABILITY..............................................

3/4 0 1 3/4.1 REACTIVITY CONTROL SYSTEMS 3/4.I.1-BORATION CONTROL Shutdown Margin - T,,, greater than 201'F...............

3/4 1-1 Shutoown Margin.- T,,,less than or equal to 200*F......

3/4 1-3 Moderator Temperature Coefficient..........,...........

3/4 1-4 Minimum Temperature for Criticality.....................

3/4 1 6 3/4.1.2 B0 RATION SYSTEMS Flow Path - Shutdown....................................

3/4 1-7 i

Charging Pump - Shutdown...............................

3/4 1 10 Charging pu.1ps Operating..............................

3/4 1 11 Borated Water Source - Shutdown..................

3/4 1-12 Borated Water Sources - 0perating.......................

3/4 1-13 3/4.1.3 MOVABLE CONTROL ASSEMBLIES Group He1ght................................

3/4 1-15 TABLE 3.1-1 ACCIDENT ANALYSES REQUIRING REEVALUATION IN THE EVENT OF AN INOPERABLE FULL-LENGTH R0D..................

3/4 1-17 Position-Indication Systems - Operating.................

3/4 1-18 i

Shutdown Rod Insertion Limit............................

3/4 1-21 Control Rod Insertion Limits............................

3/4 1-22 t

i l

DIABLO CANYON - UNITS 1 & 2 iv Unit 1 - Amendment No.120 Unit 2 - Amendment No.118

l.9E LIMITING CONDITIONS FOR OPERATION AND SURVFILLANCE REQUIREMENTS SECTION f,ggg 3/4.2 POWER DISTRIBUTION LIMITS 3/4.2.1 AXIAL FLUX DIFFERENCE..................................

3/4 2-1 3/4.2.2 NEAT FLUX HOT CHANNEL FACTOR-F (2)....

3/4 2-5 0

l 3/4.2.3 RCS FLOW RATE AND HUCLEAR ENTHALPY RISE HOT CHANNEL FACT 0R.....................................

3/4 2-13 FIGURF 3.2-3a RCS TOTAL FLOWRATE VER$U$ R (UNIT 1)..............

3/4 2-14 FIGURE 3.2-3'a RCS TOTAL FLOWRATE VERVs$ R (UNIT 2)..............

3/4 2-15 3/4.2.4 QUADRANT POWER TILT RAT 10...............'...............

3/4 2-13 3/4.2.5 DNB PARAMETERS.........................................

3/4 2-21 TABLE 3.2-1 DNB PARAMETERS............o........................

3/4 2-22 3/4.3 INSTRUMENTATION 3/4.3.1 RE ACTOR T RI P SYSTEM INSTRUMENTAT10N....................

3/4 3-1 TABLE 3.3-1 R E ACTOR TRI P SYSTEM I NSTRUMENTATION.................

3/4 3-2 TABLE 3.3-2 REACTOR TRIP $YSTEM INSTRUMENTATION RESPONS'i TIMES..

3/4 3-8 TABLE 4.3-1 REACTOR TRIP SYSTEM INSTRUMENTATION SURVEILLANCE REQUIREMENTS........................................

3/4 3-10 3/4.3.2 ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION........................................

3/4 3-14 TABLE 3.3-3 ENGINEERED SAFETY FEATURES ACTUATION SYSTEM IGTRUMENTAT10N.....................................

3/4 3-15 1

DIABLO CANYON - UKITS 1 &,2 v

Amendment Nos. ff & 51 71 & 70

LND.E.1 llMITING CONDITIONS FOR OPERATION AND SURVElltANCE REQUIREMENTS SECTION P_Ag 3/4.3 INSTRUMENTATION (continued)

TABLE 3.3-4 ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION TRIP SETP0lNTS...............

3/4 3 23 TABLE 3.3-5 ENGINEERED SAFETY FEATURES RESPONSE TIMES.............

3/4 3-28 TABLE 4.3 2 ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION SURVEILLANCE REQUIREMENTS............

3/4 3-32 3/4.3 3 MONITORING INSTRUMENTATION Radiation Monitoring for Plant Operatns............ 3/4 3 36 TABLE 3.3-6 RADIATION MONITORING INSTRUMENTATION FUR PLANT OPERATIONS 3/4 3 37 TABLE 4.3-3 RADIATION MONITORING INSTRUMENTATION FOR PLANT OPERATIONS SURVEILLANCE REQUIREMENTS.

3/4 3 39 Movable Incore Detectors........

3/4 3-40 I

TABLE 3.3 7 DELETED I

TABLE 4.3-4 DELETED I

Meteorological Instrumentation...................

3/4 3-44 TABLE 3.3 8 METEOROLOGICAL MONITORING INSTRUMENTATION.............

3/4 3-45 TABLE 4.3-5 METEOROLOGICAL MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS.......................

3/4 3-46 Remote Shutdown Instrumentation and Controls.

3/4 3-47 TABLE 3.3-9 REMOTE SHUTDOWN MONITORING INSTRUMENTATION AND CONTROLS...........

3/4 3-48 TABLE 4.3-6 REMOTE SHUTDOWN MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS....

3/4 3-49 Accident Monitoring Instrumentation...

3/4 3-50 TABLE 3.3-10 ACCIDENT MONITORING INSTRUMENTATION......

3/4 3-52 TABLE 4.3-7 ACCIDENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS.......

3/4 3-53 DJABLO CANYON - UNITS 1 & 2 vi Unit 1 - Amendment No. o W Unit 2 - Amendment No. 93

INDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE RE0VIREMENTS SECTION EAE 3/4.3 INSTRUMENTATION fcontinued)

Explosive Gas Monitoring Instrumentation.................

3/4 3-59 3/4.3.4 DELETED l

3/4.4 REACTOR COOLANT SYSTEM 3/4.4.1 REACTOR COOLANT LOOPS AND COOLANT CIRCULATION Startup and Power O 3/4 4-1 Hot Standby........peration..............................

3/4 4-2 Hot Shutdown.............................................

3/4 4-3 Cold Shutdown - Loops F111ed.............................

3/4 4-5 Cold Shutdown - Loops Not Fi11ed................,........

3/4 4-6 3/4.4.2 SAFElf VALVES 0perating................................................

3/4 4-8 3/4.4.3 PRESSURIZER..............................................

3/4 4-9 i

3/4.4.4 RELIEF VALVES...........................................

3/4 4-10 3/4.4.5 STEAM GENERATORS.....................

3/4 4-11 DIABLO CANYON - UNITS 1 & 2 vii Unit 1 - Amendment No. 57,75,00,120 Unit 2 - Amendment No. 55,74,07,116 i

_________J

INDIX LIMITING CONDI710NS FOR OPERATION AND SURVEILLANCE REQUIREMENT $

SECTION EME 3/4.4 REACTOR COOLANT SYSTEM fcontinued)

TABLE 4.4-1 MINIMUM NUMBER OF STEAM GENERATORS TO BE INSPECTED DURING INSERVICE INSPECTION................

3/4 4-16.

TABLE 4.4-2 STEAM GENERATOR TU8E INSPECTION.......................

3/4 4-17 3/4.4.6 REACTOR COOLANT SYSTEM LEAKAGE Leakage Detection Systems.............................

3/4 4-18 Operati onal Leakage................................... 3/4 4-19 TABLE 3.4-1 REACTOR C0OLANT SYSTEM PRESSURE ISOLATION VALVES......

3/4 4-21 3/4.4.8 SPECIFIC ACTIVITY.....................................

3/4 4-25 FIGURE 3.4-1 DOSE EQUIVALENT I-131 REACTOR COOLANT SPECIFIC ACTIVITY LIMIT VERSUS PERCENT OF RATED THERMAL POWER WITH THE REACTOR COOLANT SPECIFIC ACTIVITY

> 1 pCI/ GRAM DOSE EQUIVALENT I-131....................

3/4 4-27 TABLE 4.4-4 REACTOR COOLANT SPECIFIC ACTIVITY SAMPLE AND ANALYSIS PR0 GRAM..................................

3/4 4-28 3/4.4.9 PRESSURE / TEMPERATURE LIMITS..........................

3/4 4-30 FIGURE 3.4-2 REACTOR COOLANT SYSTEM HEATUP LIMITATIONS -

APPLICABLE UP TO 12 EFPY.............................

3/4 4-31 i

FIGURE 3.4-3 REACTOR COOLANT SYSTEM C00LDOWN LIMITATIONS -

APPLICABLE UP TO 12 EFPY.............................

3/4 4-32 l

Overpressure Protection Systems......................

3/4 4-35 t

DIABLO CANYON - UNITS 1 & 2 viii Unit 1 - Amendment No. 64 48,100 T

Unit 2 - Amendment No. 63 97,99 7

INDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE RE0V[REMENTS SECTION PEE 3/4.5 EMERGENCY CORE COOLING SYSTEMS 3/4.5.1 ACCUMULATORS..............................................

3/4 5-1 3/4.5.2 ECCS SUBSYSTEMS - T., GREATER THAN OR EQUAL TO 350*F......

3/4 5-3 3/4.5.3 ECCS SUBSYSTEMS - T., LESS THAN 350'F.....................

3/4 5-7 3/4.5.4 DELETED 3/4.5.5 REFUELING WATER STORAGE TANK..............................

3/4 5-11 3/4.6 ~0NTAINMENT SYSTEMS 3/4.6.1 CONTAINMENT Containment Integrity.....................................

3/4 6-1 l

Containment Air Locks.....................................

3/4 6 I n t e rn al. Pre s s u re......................................... 3/4 6-/

Air Temperature...........................................

3/4 6-8 Containment Ventilation System............................

3/4 6-10 3/4.6.2 DEPRESSUT!ZATION AND COOLING SYSTEMS Containment. Spray System..................................

3/4 6-11 Spray Additive System.....................................

3/4 6-12 Containment Cooling System................................

3/4 6-13 3/4.6.3 CONTAINMENT-ISOLATION VALVES..............................

3/4 6-15 3/4.6.4 COMBUSTIBLE GAS CONTROL Hydrogen Analyzers / Monitors.............................. 3/4 6-17 El ectri c Hydrogen Recombiners............................. 3/4 6-18 DIABLO CANYON - UNITS 1 & 2 ix Unit 1 - Amendment No, M,120 Unit 2 - Amendment No. M,118

i INDEX i

'g LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE RE0UIREMENTS SECTION R&GE 3/4.7 PLANT SYSTEMS 3/4.7.1 TURBINE CYCLE Safety Va1ves...........................................

3/4 7-1 TABLE 3.7-1 MAXIMUM ALLOWABLE POWER RANGE NEUTRON FLUX HIGH SETPOINT WITH INOPEkABLE STEAM LINE SAFETY VALVES.......

3/4 7-2 TABLE 3.7-2 STEAM LINE SAFETY VALVES PER L00P.......................

3/4 7-3 Auxiliary Feedwater System..............................

3/4 7-4 Auxiliary Feedwater Source..............................

3/4 7-6 Specific Activity.......................................

3/4 7-7 TABLE 4.7-1 SECONDARY COOLANT SYSTEM SPECIFIC ACTIVITY SAMPLE AND ANALYSIS PR0 GRAM.............................

3/4 7-8 Main Steam Line Isolation Va1ves........................

3/4 7-9 Steam Generator 10% Atmospheric _ Dump Valves............. 3/4 7-9a Main Feedwater Regulating Bypass and Isolation Valves... 3/4 7-9b 3/4.7.2 DELETED g

3/4.7.3 VITAL COMPONENT COOLING WATER SYSTEM....................

3/4 7-11 3/4.7.4 AUXILIARY SALTWATER SYSTEM..............................

3/4 7-12 3/4.7.5 CONTROL ROOM VENTILATION 'YSTEM.........................

3/4 7-13 3/4.7.6 AUXILIARY BUILDING SAFEGUARDS AIR FILTRATION SYSTEM.....

3/4 7-16 3/4.7.7 DELETED l

3/4.7.8 DELETED I

DIABLO CANYON - UNITS 1 1 2 x

Unit 1 - Amendment S5,75,77,106 Unit 2 - Amendment 55,7',75, 105

+

-r

INDEX LlHITING CONDITIONS FOR OPERAT!^N AND SURVEllLANCE REQUIREMENTS SECTION igg 1 3/4,7 PLANT SYSTEMS (continued) 3/4.7.11 DELETED 3/4.7.12 ULTIMATE HEAT SINK..............

3/4 7-39 3/4.7.13 DELETED 3/4.8 ELECTRICAL POWER SYSTEMS 3/4.8.1 A.C. SOURCES Operating......

3/4 8-1 TABLE 4.8 1 DIESEL GENERATOR TEST SCHEDULE.....................

3/4 8-8 TABLE 4.8-2a LOAD SE0VENCING TIMERS - ESF TIMERS..................

3/4 8 9 TABLE 4.8-2b LOAD SEQUENCING TIMERS - AUTO TRANSFER TIMERS........

3/4 8-10 5hutdown................................................

3/4 8-11 3/4.8.2 ONSITE POWER DISTRIBUTION Operating,............................................

3/4 8 Shutdown................................................

3/4 8-14 3/4.8.3

'D.C. SOURCES Operating..................................

3/4 8-15 TABLE 4.8-3 BATTERY SURVEILLANCE REQUIREMENTS...................

3/4 8-17

!hutdown.......................................

3/4 8-18

-3/4.8.4 DELETED l

l l

DIABLO CANYON - UNITS 1 & 2 xi Unit 1 - Amendment 55.75.79.106120 Unit 2 - Amendment 55. ".78.105.118

IIEfl LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE RE0VIREMENTS

$ECTION E&E 3/4.9 REFUELING OPERATIONS 3/4.9.1 BORON CONCENTRATION.......................................

3/4 9-1 3/4.9.2 INSTRUMENTATION...........................................

3/4 9-2 3/4.9.3 DECAY TIME................................................

3/4 9-3 3/4.9.4 CONTAINMENT PENETRA110NS..................................

3/4 9-4 3/4.9.5 COMMUNICATIONS............................................

3/4 9 5 3/4.9.6 MANIPULATOR CRANE.........................................

3/4 9-6 3/4.9.7 CRANE TRAVEL - FUEL HANDLING BUILDING.....................

3/4 9-7 3/4.9.8 RESIDUAL HEAT REMOVAL AND COOLANT CIRCULATION High Water Leve1..........................................

3/4 9-8 Low Water Level...........................................

3/4 9-9 3/4.9.9 CONTAINMENT VENTILATION ISOLATION SYSTEM..................

3/4 9-10 3/4.9.lQ WATER LEVEL - REACTOR VESSEL F u e l A s s e mbl i e s........................................... 3/4 9-11 1

Control Rods..............................................

3/4 9-lla 3/4.9.11 WATER LEVEL - SPENT FUEL P00L.............................

3/4 9-12 3/4.9.12 FUEL HAhDLING BUILDING VENTILATION SYSTEM.................

3/4 9-13 3/4.9.13 SPENT FUEL SHIPPIC CASK M0VEMENT.........................

3/4 9-15 FIGURE 3.9-1 UNITS 1 AND 2 SPENT FUEL POOL LAYOUT.................

3/4 9-16 3/4.9.14 SPENT FUEL ASSEMBLY STORAGE 5pe nt Fu el Pool Reg i on 2.................................. 3/4 9-17 FIGURE 3.9-2 MINIMUM REQUIRED ASSEMBLY DISCHARGE BURNUP AS A FUNCTION OF INITIAL ENRICHMENT AND PELLET DI AMETER TO PERMIT STORAGE IN REGION 2............... 3/4 9-18 Spent Fuel Pool Boron Concentration.,..................... 3/4 9-19 Spent Fuel Pool Reg i on 1.................................. 3/4 9-20 FIGURE 3.9-3 MINIMUM REC'llRED ASSEMBLY DISCHARGE BURNUP AS A FUNCTION uF INITIAL ENRICHMFNT (NO IFBA) TO PERMIT STORAGE IN fEGION 1...........................

3/4 9-22

}]_LJO SPECTAL TEST EXCEPTIONS 3/4.10.1 SHUTDOWN MARGIN...........................................

3/4 10-1 3/4.10.2 GROUP HEIGHT, INSERTION AND POWER DISTRIBUTION LIMITS.....

3/4 10-2 3/4.10.3 PHYSICS TESTS.............................................

3/4 10-3 3/4.10.4 POSITION INDICATION SYSTEM - SHUTD0WN.....................

3/4 10-4 DIABLD CANYON - UNITS I & 2 xit Unit 1 - Amendment B97M.104 Unit 2 - Amendment B8vM,103 l

u_________----________-_-----

INDEX LIMITING CONDITIONS FOR OPERATION AND SURVLILLANCE REQUIREMENTS SECTION h

3/4.11 RADIDACTIVE EFFLUENTS 3/4.11.1 LIQUID EFFLUENTS Liquid Holdup Tanks......................................

3/4 11-1 3/4.11.2 GASEOUS EFFLUENTS Explosive Gas Mixture.....'...............................

3/4 11-2 Gas Storage Tanks........................................

3/4 11-3 e

.L DIABLO CANYON - UNITS 1 & 2 xiii Amendment Nos.67 and 66

INDEX BASES SECTION PAE 3/4.0 APPLICABILITY..............................................

B 3/4 0-1 3/4.1 REAClIVITY CONTROL SYSTEMS 3/4.1.1 BORATION CONTR0L.........................................

B 3/4 1-1 1

3/4.1.2 BORATION SYSTEMS.........................................

B 3/4 1-2 3/4.1.3 MOVABLE P!NTROL ASSEMBLIES...............................

B 3/4 1-3

]/4.2 POWER DISTRIBUTION LIMITS..................................

B 3/4 2-1 3/4.2.1 AXIAL FLUX DIFFERENCE....................................

B 3/4 2-1 3/4.2.2 and 3/4.2.3 HEAT FLUX HOT CHANNEL FACTOR, and RCS FLOW RATE AND NUCLEAR ENTHALPY RISE HOT CHANNEL FACTOR........

B 3/4 2-2 3/4.2.4 QUADRANT POWER TILT RATI0................................

B 3/4 2-5 3/4.2.5 DNB PARAMETERS...........................................

B 3/4 2-6 1

3/4.5 INSTRUMENTATION 4

3/4.3.1 and 3/4.3.2 REACTOR TRIP SYSTEM and ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION................

B 3/4 3-1 3/4.3.3 MONITORING INSTRUMENTATION...............................

B 3/4 3-2 3/4.3.4 DELETED g

3/4.4 REACTOR COOLANT SYSTEM 3/4.4.1 REACTOR COOLANT LOOPS AND COOLANT CIRCULATION............

B 3/4 4-1 3/4.4.2 SAFETY VALVES............................................

B 3/4 4-1 3/4.4.3 PRESSURIZER..............................................

B 3/4 4-2 3/4.4.4 RELIEF VALVES............................................

B 3/4 4-2 3/4.4.5 STEAM GENERATORS.........................................

B 3/4 4-2 DIABLO CANYON - UNITS 1 & 2 xiv Unit 1 - Amendment No. +B,120 Unit 2 - Amendment No. M,118

111D11 BASES 1ECIIDit P.ag 3/4.4.6 REACTOR COOLANT SYSTEM LEAKAGE..........................

8 3/4 4-3 3/4.4.8 SPECIFIC 1.CTIVITY.......................................

B 3/4 4-5 3/4.4.9 PRES!URE/TEMPERATURELIMITS.............................

8 3/4 4-7 t

3/4.5 EMERGENCY CORE COOLING SYSTEMS 3/4.5.1 ACCUMULt.T0RS............................................

B 3/4 5-1 3/4.5.2 and 3/4.5.3 ECCS SUBSYSTEMS.............................

B 3/4 5-1 3/4.5.4 DELETED I

l 3/4.5.5 REFUELING WATER STORAGE TANK............................

8 3/4 5-3 J

DIABLO CANYON - UNI 15 1 & 2 xv Unit 1 - Amendment No. 54-98,103 Unit 2 - Amendment No. 6hW,102

a

INDEX BASES

$ECTION

emf,

)]4.6 CONTAINMENT SYSTEMS 3/'.6.1 C 0NT A I NM Eit T........................................... B 3 / 4 6 - 1 3/4.6.2 DEPRESSURIZATION AND COOLING SYSTEMS.................. B 3/4 6-3 3/4.6.3 CONTAINMENT ISOLATION VALVES..........................

B 3/4 6-4 3/4.6.4 COMBUSTIBLE GAS CONTR0L............................... B 3/4 6-4

/3 7 PLANT SYSTEMS 3/4.7.1 TURBINE CYCLE......................................... B 3/4 7-1 S/4.7.2 STEAM GENERATOR PRESSURE / TEMPERATURE LIMITATION....... B 3/4 7-3 3/4.7.3 VITAL COMPONENT COOLING WATER SYSTEM..................

B 3/4 7-3 3/4.7./

AUXILIARY SALTWATER SYSTEN............................ B 3/4 7-3 3/4.7.5 CONTROL ROOM VENTILATION SYSTEM....................... B 3/4 7-3 3/4.7.6 AUXILIARY BUILDING SAFEGUARDS AIR FILTRATION SYSTEM... B 3/4 7-4 3/4.7.7 SNUBBERS.............................................. B 3/4 7-4 3/4.7.8 SEALED SOURCE CONTAMINATION........................... B 3/4 7-6 3/4.7.11 AREA TEMPERATURE MONITORING........................... B 3/4 7-7 3/4.7.12 ULTIMATE HEAT SINK................................... B 3/4 7-7 3/4.7.13 FLOOD PROTECT 10N...................................... B 3/4 7-8 2L4.8 ELECTRICAL POWER SYSTEMS 3/" 8.1, 3/4.8.2..nd 3/4.8.3 A.C. SOURCES, D.C. SOURCES, and DNSITE POWER DISTRIBUTION...........................

B 3/4 8-1 3/4.8.4 DELETED DIABLO CANYON - UNITS 1 & 2 xvi Unit 1 - Amendment No. M,120 Unit 2 - Amendment No. M,118

1.0 Dtr1 NIT 10NS The defined terms of this section appear in capitelized type and are applicable throughout these Technical Specifications.

Ell 2i 1.i ACTION shall be that part of a Specification which prescribes remedial measures required under designated conditions.

ACTUATION LOGIC TEST 3.2 An ACTUATION LOGIC TEST shall be the application of various simulated input combinations in conjunction with each possible interlock logic state and verifi.

cation of the required logic output. The ACTUATION LOGIC TEST shall include a et,.tinuity check, as a minimum of output devices.

C @NNEL OPERATIONAL TEST 1.3 A C%NNEL OPERATIONAL TEST shall be the injection of a simulated signal into the channel as close to the sensor as practicable to verify OPERABILITY of 61erm.

interlock and/or trip functions. The CMNNEL OPERATIONAL TEST shall include adjustments, as necessary. of the alarm. interlock and/or trip setpoints such that the setpoints are within the iequired range and accuracy.

Ar1A_ FLUX DirrERENCE 1.4 AX1AL FLUX DIFFERENCE shall be the difference in normalized flux signals between the t'op and bottom halves of a two section excore neutron detector, s

CHANNEL CALIBRATION 1.5 A CHANN CAllBRATION shall be the adjustment, as necessary, of the channel such that it responds within the required range and accuracy to known values of input.

The CHANNEL CAllBuT10N shall encompass the entire channel including the sensors and alarm, interlock ano/or trip functions and may be performed by any series of sequential, overlapping or total channel steps such that the entire channel is calibrated.

CHANNELCHE(3 1.6 A CHANNEL CHECK shall be the qualitative essessment of channel behavior during operation by observation. This determination shall include. where possible.

comparison of the channel indication and/or status with other indications and/or status derived from independent instrument channels measuring the same paraneter.

DIABLO CANYON UNITS 1 & 2 11 A:adei N:is. 84 and 83 5

DirlNITIONS CHANNEL FUNCTIONAL TEST 1.7 A CHANNEL FUNCTIONAL TEST shall be:

a.

Analog channels the injection of a simulated signal into the channel as close to the sensor as practicable to verify OPERABILITY including alarm and/or trip functions, or b.

B1 stable channels - the injection of a simulated signal into the sensor to verify OPERABILITY including alarm and/or trip functions.

c.

Digital channelt the injection of a simulated signal into the channel as close to the sensor input to the process racks as practical to verify OPERABILITY including alarm and/or trip functions.

CONTAINMENT INTEGRITY 1.8 CONTAINMENT INTEGRITY shall exist when:

a.

All penetrations required to be closed during accident conditions are either:

1.

Capable of being closed by an OPERABLE containment automatic isolation valve system, or 2.

Closed by manual valves, blind flanges, or deactivated automatic valves secured in their closed positions.,except for valves that are open under administrative control as permitted by Specification 3.6.3.

b.

All equipment hatches are closed and sealed, c.

Each air lock is in compliance with the requirements of Specification 3.6.1.3, d.

The containment leakage rates as determined by Surveillance Requirement 4.6.1.1.c are within the limits listed in the Bases for Specification 3.6.1.1, and e.

The sealing mechanism associated with each penetration (e.g., welds, bellows or 0 rings) is OPERABLE.

CONTROLLED LEAKAGE 1.9 CONTROLLED LEAKAGE shall be that seal water flow supplied to the reactor coolant pump seals.

CORE ALTERATIONS 1.10 CORE ALTERATIONS shall be the movement or manipulation of any fuel, sources, or reactivity control components within the reactor vessel with the vessel head removed and fuel in the vessel.

Suspension of CORE ALTERATIONS shall not preclude completion of movement of a component to a safe conservative position.

DIABLO CANYON - UNITS 1 & 2 1-2 Unit 1 Amendment No. 46.73.83.120 Unit 2 - Amendment No 'E.72.83.118

_ REACTIVITY CONTROL $Y$TEMS 3/4.1.2 50 RAT 10N SYSTEMS TLOW PATH - $NUTDOWN LIMITING CONDITION FOR OPERATION 3.1.2.1 As a minimum, one of the following boron injection flow paths shall be OPERABLE with motor-operated valves required to change position and pumps required to operate for boron in DPERABLE emergency power source:jection capable of being poweidd from an A flow path from the boric acid tanks via a boric acid transfer pump a.

and charging pump to the Reactor Coolant System if the boric acid storage tank in Specification 3.1.2.5a. is OPERABLE, or b.

The flow path from the refueling water storage tank via a charging pump to the Reactor Coolant System if the refueling water storage

. tank in Specification 3.1.2.5b. is OPERABLE.

APPLICABILITY: MODE 5 5 and 6.

ACTION:

With none of the above flow paths OPERABLE or capable of being powered from an DPERABLE emergency power source, suspend all operat.ons involving CORE ALTERATJDNS or positive reactivity changes.

5URVEILLANCE REQUIREMENTS 4.1.2.1 At least one of the above required flow paths shall be demonstrated OPERABLE:

At least once per 7 days by verifying that the temperature of the flow a.

path is creater than or equal to 65 F when a flow path from the boric acid tanks is used, and b.

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 securled in position, is in its correct position.

1 DIABLD CANYDN - UNITS 1 & 2 3/4 1-7 Amendment Nos. 53 & 52, 72 & 7

i

'?

THIS PAGE INTENTIONALLY BLANK DIABLO CANYON - UNITS 1 & 2 3/4 1-8 Unit 1 - Amendment No. 52,72,1^^,120 Unit 2 - Amendment No. 52,71,00,118 1

WW g:$-fJ 5

REACTIVITY CONTROL SYSTEMS 3/4.1.3 MOVABLE CONTROL ASSEMBLIES GROUP HEIGHT 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: MDDES 1* and 2".

g ACTION:

E With one or more full-length rods 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 I hour 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 misali ned from its height by more than i 12 steps (indicated pos tion), POWER broup demand PERATION may continue provided that within 1 hour:

1.

The rod is restored to OPERABLE status within 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 1 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 confire 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 ;

$ee Special Test Exceptions Specifications 3.10.2 and 3.10.3.

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

REACTIVITY CONTROL SYSTEMS llMITING CONDITION FOR OPERATION ACTION (Continued) c)

A power distribution map is obtained from the movable within their limits wil(hin 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months ; andincore detectors and F Z) d)

The 1HERMAL 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 NeLtron Flux Trip Setsoint is reduced to less than or equal to 8S% of RATED THERMAL POWER.

c.

With more than one rod trippable but inoserable due to causes other than addressed by ACTION a above. POWER OPERATION may continue 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 ino)erable rods are aligned to within i 12 steps of the inopera)le rods while maintaining the rod sequence and insertion limits of Specification 3.1.3.6.

The THERMAL POWER level -hall 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 misa11gned from its group demand )osition by more than t 12 steps (indicated position), be in HOT STAiDBY within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

SURVElllANCE 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 )ositions 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 lod 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 determined to be OPERABLE by movement of at least 10 steps in any one direction at least once per 92 days.

4.1.3.1.3 Prior to reactor criticality, verify that the rod drop time of the full length shutdown and control rods is 52.7 seconds from be of stationary _ gripper coil voltage to dashpot entry, with T, ginning of decay

=541*F. and all ay reactor coolant pumps operating:

a.

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

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

DIABLO CANYON - UNITS 1 & 2 3/4 1-16 Unit 1 - Amendment No. '5.102.120 Unit 2 Amendment No. 41.101,118

TA.BLE 3.1-1 a.

ACCIDENT ANALYSES REQUIRING REEVALVATION IN THE EVENT 6F AN INOPERABLE Fut.L-LENGTH ROD Rod Clust7r Control Assembly Insertion Characteristics Rod Cluster Control Assembly Misalignment loss Of Reactor Coolant From Small Ruptured Pipes Or From Cracks In Large Pipes Which Actuates The Emergency Core Cooling System Single Rod Cluster Control Assembly Withdrawal At Full Power J

Major Reactor Coolant System Pipe Ruptures (Loss Of Coolant Accident)

Major Secondary System Pipe Rupture Rupture of a Control Bod Drive Mechanism Housing (Rod cluster Control Assembly Ejection) 4 J

4 4

2 DIABLO CANYON - UNITS 1 & 2 3/4-1-17

REACTIVITY CONTROL SYSTEMS POSITION INDICATION SYSTEMS - OPERATING LIMITING CONDITION FOR OPERATION 3.1.3.2 The Digital Rod Position Indication System and the Demand Position Indication System shall be OPERABLE and capable of determining the control rod positions within i 12 steps.

APPLICABILITY:

MODES 1 and 2.

ACTION:

a.

With a maximum of one digital rod position indicator per bank inoperable either:

1.

Determine the position of the nonindicating rod (s) indirectly by the movable incore detectors at least once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months and immediately after any motion of the nonindicating rod which exceeds 24 steps in one direction since the last determination of the rod's position or 2.

Reduce THERMAL POWER to less than 50% of RATED THERMAL POWER within 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months , b.

With a maximum of one demand position indicator per bank inoperable either:

1.

Verify that all digital rod position indicators for the affected bank are OPERABLE and that the most withdrawn rod and the least withdrawn rod of the bank are within a maximum of 12 steps of each other at least once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months , or 2.

Reduce THERMAL POWER to less than 50% of RATED THERMAL POWER within 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months .

SURVEILLANCE REQUIREMENTS 4.1.3.2-Each digital rod position indicator shall be determined to be

-0PERABLE by verifying that the Demand Position Indication System and the Digital Rod Position Indication System agree within 12 steps 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 compare the Demand Position Indication System and the Digital Rod Position Indication System at least once per 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

4.1.3.3 Each of the required digital rod position indicator (s) shall be l

determined to be OPERABLE by verifying that the digital rod position indicators agree with the demand position indicators within 12 ste)s when exercised over the full range of rod travel at least once each REFJELING INTERVAL.

120

.DIABLO CANYON UNITS 1 & 2 3/4 1 18 Unit 1 Amendment No. W.118 l

(Next page is 3/4 1-21)

Unit 2 - Amendment No. M.

R TABLE W RADIATIM MRllIORifIE 11tSTRWENTATIOlt FOR PLA_N_I_jPERAIIONS6 S

CNMEL MODES FOR Witr B

CNWIEL CNWIEL FUNCTIONRL SURTEILLANCE 5

CHECK-CALIBRAT10ll TEST

_.15 REEUIRED E

y 1.

Fuel Handling Building Storage Area a.

I)

Spent Fuel Pool 5

R q

E 2)

IIew Fuel Storage 5

R q

4 b.

Gaseous Activity I

Fuel Handling Building S

R q

Ventilation Mode Change

~

2.

Control Room Ventilation Mode Change 5

R q

All 3.

Containment a.

Gaseous Activity 1)

Deleted l

2)

RCS Leakage 5

R

~

Q 1, 2, 3, 4 w1 3)

Containment Venti-S R

q 6

w lation Isolation

~

d.

(IUC-44A or 448)

S R

q 6

l b.

Particulate Activity 1)

Containment Venti-S R

q 6

lation Isolation (lui-44A or 448) 2)

RCS Leakage 5

R 4

1, 2, 3, 4 l

gg " *With fuel in the spent fuel pool or new fuel storage vault.

EN The requirements for Fuel Handling Building Ventilation Mode Change are appilcable following

~~

installation of Igl-45A and 458.

El 22 na

-28

INSTRUMENTaI10N MOVABLE INCORE DETECTORS LIMITING CONDITION FOR OPERATION 1

3.3.3.2 The Movable Incore Detection System shall be OPERABLE with:

a.

At least 75% of the detector thimbles, b.

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

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

APPLICABILITY: When the Movable Incore Detection System is used for:

a.

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

Monitoring the QUADRANT POWER TILT RATIO, or Measurement of F$,

F,(Z) and F,y.

c.

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.

SURVEILLANCE RE0VIREMENTS 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.

Recalibrution of the Excore Neutron Flux Detection System, er b.

Monitoring the QUADRANT POWER TILT RATIO, or Measurement of FA, F,(Z) and F,y.

c.

DIABLO CANYON - UNITS 1 & 2 3/4 3-40 Unit 1 - Amendment No. 65,120 (Next page is 3/4 3-44) Unit 2 - Amendment No. 64,118 l

l,-

INSTRUMENTATg METEOR 0 LOGICAL INSTRUMENTATION 1

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

APPLICABILITY:

At all times.

ACTION:

i With one or more required meteorological monitoring channels inoperable s.

for more than 7 days, prepare and submit a Special Report to the Commission pursuant to Specification 6.9.2 within the next 10 days outlining the cause of the malfunction and the plans for restoring the channel (s) to OPERABLE status.

b.

The provisions of Specification 3.0.3 are not applicable.

l 3

i j

$URVEILLANCI REQUIREMENT 3 4.3.3.4 Each of the above meteorological monitoring instrumentation channels shall be demonstrated OPERABLt by the perfonnance of the CHANNEL CHECK and CHANNEL CALIBRATION at the frequencies shown in Table 4.3-5.

4 i

i 1

'The meteorological monitoring instrumentation channels are common to both units.

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

,,y,

~

[

{

TABLE 4.3-7 l

w g

ACCIDENT MONITORING INSTRUDENTATION SURVEILLANCE REQUIROGITS o

9g CHANNEL CHANNEL

}

g INSTRUMENT CHECK CAtIBRATION j

1.

Containment Pressure M

R j

2.

Reactor Coolant Outlet Temperature - T I"

I* * )

I hot U

3.

Reactor Coolant Inlet Temperature - T I"I" "*

I I

cold 4.

Reactor Coolant Pressure - Wide Range M

R I

m 5.

Pressurizer Water Level M

R i

{

6.

Steam Line Pressure M

R 7.

Steam Generator Water Level - Narrow Range M

R j

8.

Refueling Water Storage Tank Water Level M

R D

9.

Containment Reactor Cavity Sump Level-Wide Range M

R I

f

[

10. Containment Recirculation Sump Level-Marrow Range M

R I

l

11. Auxiliary Feeduster Flow Rate M

R t

12. Reactor Coolant Systen Subcooling Margin Monitor M

R l

l

13. PORY Position Indicator M

R l

14. PORY Block Valve Position Indicator M

R t

15. Safety Valve Position Indicator M

R l

16.

In Core Thermocouples M

R

17. Main Steam Line Radiation Monitor M

R

18. Containment Area Radiation Moniter-High Range M

R*

19.

Plant Vent Radiation Monitor-High Range M

R 20.

Reactor Vessel Level Indication System M

R f

CHANNEL CALIBRATION may consist of an electronic calibration of the channel, not including the detector, i

for range decades above 10 R/h and a one point ca11bration check of the detector below 10 R/h with an installed or portable gamma source.

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DIABLO CANYON - UNITS 1 & 2 3/4 3-54 Unit 1 - Amendment No. H,120 Unit 2 - Amendment No. H,118

INSTRUMENTATION EXPLOS!VE GAS EFFLUENT MONITORING INSTRUMENTATION LIMITING CONDITION FOR OPERATION 3.3.3.9 Deleted 3.3.3.10 The explosive gas monitoring instrumentation channels (ANR 75 or ANR 76)its of Specification 3.11.2.5 are not exceeded.shall be OPERABLE with their Ala the lim APPLICABILITY:

During GASE0US RADWASTE SYSTEM operation.

ACTION:

a.

With an explosive gas monitoring instrumentation channel (ANRi 5 or ANR 76) Alarm / Trip Setpoint less conservative than requiret ey the above specification, declare the channel inoperable and follow action b below.

b.

With only one OPERABLE explosive gas monitoring instrumentation channel, operation of this system may continue for up to 14 days.

After 14 days or with no channels OPIRABLE, operation of this system may continue provided grab samples are collected at least once per 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months and analyzed within the following 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months , c.

The provisions of Specificction 3.0.3 are not applicable.

SURVEILLANCE REQUIREMENTS 4.3.3.9 Deleted 4.3.3.10.1 Each explosive gas monitoring instrumentation channel shall be demonstrated OPERABLE by performance of a daily CHANNEt CHECK and a monthly CHANNEL FUNCTIONAL TEST.

4.3.3.10.2 Each explosive gas monitoring instrumentetton channel shall be demonstrated OPERABLE by performance of a quarterly CHANNEL CALIBRATION. The CHANNEL CALIBRATION shall include the use of standard gas samples containing a nominal a.

Two volume percent oxygen, balance nittogen, and b.

Four volume percent oxygen, balance nitrogen.

DIABLO CANYON - UNITS 1 & 2 3/4 3-59 Amendment Nos. 67 and 66 1

3/4.6 CONTAINMENT SYSTEMS 3/4.6.1 CONTAINMENT CONTAINMENT INTEGRITY LIMITING CONDITION FOR OPERATION 3.6.1.1 CONTAINMENT INTEGRITY shall be maintained.

APPLICABILITY:

MODES 1, 2, 3, and 4.

ACTION:

Without CONTAINMENT INTEGRITY, restore CONTAINMENT INTEGRITY within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 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 .

SURVElltANCE REQUIREMENTS 4.6.1.1 CONTAINMENT INTEGRITY shall be demonstrated:

a, At least once per 31 days by verifying that all penetrations

not capable of being closed by OPERABLE containment automatic isolation valves and required to be closed during accident conditions are closed by valves, blind flanges, or deactivated automatic valves secured in their positions, except for valves that are open under administrative control as permitted by Specification 3.6.3, b.

By verifying that each containment air lock is in compliance with the requirements of Specification 3.6.1.3: and

=c.

By performing containment leakage rate testing, except for containment air lock testing, in accordance with the Containment Leakage Rate-Testing Program.

Except valves, blind flanges, and deactivated automatic valves which are located inside the containment and are locked, sealed, or otherwise secured in the closed )osition. These penetrations shall be verified closed during each COLD SHUT)0WN except such verification need not be performed more often than once per-92 days.

DIABLO CANYON UNITS 1 & 2 3/4 6-1 Unit 1 A,nendment No. 4-40,120 Next page is 3/4 6 5 Unit 2 - Amendment No. M-M9,118 4

j

l TNIS PAGE INTENTIONALLY BLANK 9

DIABLO CANYON - UNITS 1 L 2

- 3/4 6-9 Unit 1 - Amendment Ni.120 Unit 2 - Amendment No.118 s

CONTAINENT $Y$TEMS CONTAINMENT VENTILATION SYSTEM LIMITING CONDITION FOR OPERATION j

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 tis purne supply and/or exhaust isolation valves open or with the vacuum / pressure relief ' solation valves open up to 50' shall be limited to 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.

ACTION:

With a containment purge supply and/or exhautt 3;olation valve open or the vacuum / pressure relief isolation valves opt n r;, 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 isolate the penetration (s) within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months ; otherwise, 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 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

SURVEILLANCE REQUIREMENTS 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 per 18 months.

DIABLO CANYON - UNITS 1 & 2 3/4 6-10 E

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i e' INSTRUMENTATiGN l

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aASES 3/4.3.3.3 DELETED l

3/4/s.3.4 NETEORotorICAL. INSTRUMENTATION The OPERA 8ILITY of the meteorolo sufficient meteorological data is ava<pical instrumentation ensures that 1able for estimating potential radiation doses to the pubile as a result of routine or accidental release of radioactive materials to the atmosphere. This capability is required to evaluate the need for initiating protective measures to protect the health and safety of the public and is consistent with the recommendations of Regulatory Guide 1.23, 'Onsite Meteorological Programs,' February 1972.

3/4.3.3.5 REMOTE SHUTDOWN INSTRUMENTATigN BACKGROUND The Remote Shutdown Instrumentation and Controls provide the control room operator with sufficient instrumentation and controls to place and maintain the unit in a safe shutdown condition from a location other than the control room.

This capability is necessary to protect against the possibility that the control room becomes inaccessible. A safe shutdown condition is defined as MODE 3.

With the unit in MODE 3, the Auxiliary feedwater (AFW)

System and the steam generator (SG) safety valves can be used to remove core decay heat and meet all safety requirements.

The long term supply of water for the AFW System allows extended operation in MODE 3 from outside the control room until such a time that either control is transferred back to the control room or a cooldown is initiated.

In the event that the control room becomes inaccessible, the operat. ors can establish control at the remote shutdown panel (hot shutdown panel), and place and maintain tho' unit in MODE 3.

Not all controls and necessary transfer switches are located at the hot shutdown panel.

Some controls and transfer switches will have to be operated locally at the switchgear, motor control panels, or other local stations. The unit automatically reaches MODE 3 following a unit shutdown and can be maintained safely in MODE 3 for an extended period of time.

The OPERABILITY of the remote shutdown control and instrumentation functions ensures there is sufficient infomation available on selected unit parameters to place and maintain the unit in MODE 3 shocid the control room

>ecome inaccessible.

l l

l DIABLO CANYON - UNITS 1 & 3 83/43-3 Unit 1 - Amendment No. 94,120 Unit 2 - Anndment No. 94,118 l

iktDtMfWTATION 2

RAlft 3/4.1.1.5 REMDTE RWiffDOW!LlR$.11LMERIA110H (Continued)

C APPLICABLE SAFETY ANALYSES The Remote shutdown Instrumentatica and Controls provides equipment at a>propriate locottens outside the control room with a capabilit sgut down and I.alntain the unit in a safe condition in MODE 3. y to promptly The criter13 Governing the design and specific system requirements of t!O Fe)ott thetcown Instrumentation and controls are located in 10 CFR 50, 4 peadix Et Gbl 19.

LCO The Remote Shutdown Instrumentation and Controls LC0 3rovides the OPERABILITY requirements of the instrumentation and contro's necessary to place and maintain the unit in MODE 3 from a location other than the control The instrumentation and controls required a M listed in Table 3.3-9 in room.

the accompanying LCO.

The controls, instrumentation, and transfer switches are required for:

Reactor trip indication; RCS pressure control; Decay heat removal via the AFW System and the SG safety valves; RCS inventory control via charging flow; and e

Safety support systems for the above Functions, including auxiliary saltwater, component cooling water, and emergency diesel generators.

A remote shutdown function is OPERABLE if all required instrument and control channels for that function listed in Table 3.3-9 are OPERABLE.-

The remote shutdown instrument and control circuits covered by this LC0 do not need to be energized to be considered OPERABLE. This LC0 is intended to c:ssure the instruments and control circuits will be OPERABLE if unit conditions require that a remote shutdown be performed.

APPLICABILITY The Remote shvidown Instrumentation and Controls LCO is applicable in MODIS 1, t,in MODE 3 for an extended period of time from a location oth and 3. This is required so that the unit can be placed and maintained the control room until either control is transferred back to the control room or a cooldown is initiated. This LC0 is not applicable in MODE 4, 5, or 6.

DIABLO CANYON - UNITS 1 & I 5 3/4 3-3a Amendment Nos. 94 and 93

,,n.

--n-

,e,.,_

7 INSTRUMENTATION

+

BASES 3/4.3.3.5 REMOTE SHUTDOWN INSTRUMENTATION (Continued) performed only during a unit outage.)lly pass the Suivetilance test when Operating experience demonstrates that remote shutdown control f.hannels usua performed at the 18 month frequency.

NOTE: A surveillance of the reactor trip breaker OPERABILITY is not required as part of the SURVEILLANCE REQUIREMENT for 4.3.3.5.2 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).

REFERENCES 1.

10 CFR 50, Appendix A, GDC 19, 3/4.3.3.6 ACCIDENT M0KITORING INSTRUMENTATION The OPERABILITY of the accident monitoring instrumentation ensures that l

sufficient information is available on selected plant parameters to monitor and assess these variables following an accident. The 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 l

DIABLO CANYON - UNITS 1 & 2 B 3/4 3-3d Unit 1 - Amendment No. 94,120 Unit 2 - Amendment No. 98,118

Basts l

3/4.1.3.9 RADIDACTIVE L1001D EFFlufNT MONITORING INSTRtMENTATI'ON Section relocated to RMCP.

l 1

DIABLO CANYO11 - UN115 1 & 2 8 3/4 3-4 Amendment Nos. H & H 75 & 74 i

__m

____m____.__

O' INSTRUMENTATION RASES 3/4.3.3.10 EXPLOSIVE GAS MONITORING INSTRUMENTATION The ex losive gas instrumentation is provided for monitoring (and contro111

~the concentrations of potentially explosive gas mixtures in the GASEOUS ASTE SYSTEM.

3/4.3.4 DELETED I

I 1

l DIABLO CANYON - UNITS 1 & 2 B 3/4 3-5 Unit 1 - Amendment No. 4h47,120 Unit 2 Amendment No. 4h44,118 J

e 3L4.6 CONTAINMENT SYSTEMS BASES 3/4.6.1 CONTAINMENT 3/4.6.1.1 CONTAINMENT INTEGRITY CONTAINMENT INTEGRITY ensures that the release of radioactive materials from the containment atmosphere will be restricted to those leakage paths and associated leak rates assumed in the safety analyses. This restriction in conjunction with-the leakage rate limitation, will limit the SITE BOUNDARY radiation doses to within the dose guideline values of 10 CFR Part 100 during accident conditions.

l The-limitations on containment leakage rates specified in the' Containment Leakage Rate Testing Program ensure that the total containment leakage volume l

will not exceed the value assumed in the safety analyses at the peak accident pressure, P.

As an added conservatism, the measured overall integrated leakage rath is further limited to less than or equal to 0.75 L during l

performanceoftheperiodictesttoaccountforpossibledegradItionofthe i

containment leakage barriers between leakage tests.

The surveillance testing for measuring leakage rates as s ecified in the Containment Leakage Rate Testing Program is consistent with Re ulctory Guide 1.163 dated September 1995, and the requirements of Option B o 10 CFR Part 50 Appendix J.

3/4.6.1 2 DELETED l

3/4.6.1 3 CONTAINMENT AIR LOCKS The limitations on closure and leak rate for the containment air locks are required to meet the restrictions on CONTAINMENT INTEGRITY and containment leak rate.

Surveillance testing of the air lock seals provide assurance that the overall air lock leakage will not become excessive due to seal damage during the intervals between air lock leakage tests.

214 6.114 1NTERNAL PRESSURE The limitations on containment internal pressure ensure that: _-(1) the containment structure is prevented from exceeding its design negative pressure differential with respect to the outside atmosphere of 3.5 psig, and (2) the

-containment peak pressure does not exceed the design pressure of 47 psig during.

LOCA conditions.

The maximum peak pressure expected to be obtained from a LOCA event is less than 47 psig, which is the maximum design pressure of containment. This includes the limit of 1.2 psig for initial positive containment pressure.

The total pressure is less than design pressure and is consistent with the safety analyses.

DIABLO CANYON - UNITS 1 & 2 B 3/4 6 1 Unit 1 - Amendment No. 65.9f.110,120 Unit 2 Amendment No. 64.98.109.118 i

CONTAIMENT SYSTEMS RASES 3/4.6.1.5 AIR TEMPERATURE The limitations on contninnent average air temperature ensure that the overall containment average air temperature does not exceed the initial temperature condition assumed in the safety analysis for a LOCA.

3/4.6.1.6 DELETED 3/4.6.1.7 CON Use of the containment purge lines is restricted to two of the three following lines (1) a supply line 2 an exhaust line of the purge system, thevacuum/pressurerelieflin(e)toensurethattheSITEBOUNDARYdose and (3 guidel)nes of 10 CFR Part 100 would not be exceeded in the event of a loss-of-i coolant accident during containment purging operations.

The vacuum relief valves must be blocked to open no more than 50' because these/ pressure valves have not yet been qualified to close under accident conditions.

Operation will be limited to 200 hours0.00231 days 0.0556 hours 3.306878e-4 weeks 7.61e-5 months during a calendar year. The 200-hour limit shall not become effective until after initial criticality. The total time the Containment Purge during MODES 1, 2, 3, and 4 in a c(vent) System isolation valves may be open alendar year is a function of anticipated need and operating experience.

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DIABLO CANYON --UNITS 1 & 2 B 3/4 6-2 Unit 1 - Amendment No. 66,-120 Unit 2 - Amendment No. 64,118

o' ELECTRICAL POWER SY$fEMS sasts A.C. Sources. D.C. Sources. and DN11Tt POWER DISTRIaUTi g (Continued) will not be more than 0.040 below the manufacturer's full charge specific gravity and that the overall capability of the battery will be maintai.wd withinanacceptablelimit;and(4)2.07 volts,ensuresthebattery'scapability the allowable value for an individual cell's float voltage, greater than to perform its des gn function.

The OPERABILITY of the A.C. electrical power sources requires maintainin a supply of fuel oil to support the operation of the emergency diesel genera g tors. The stored fuel oil supports the function of the A.C. power sources to provide power for the operation of emergency systems and engineered safety fea-tures ([$F) during and following the shutdown of the reactor in the event that offsite power sources are not available. The specified fuel oil quantity is based on the calculated fuel oil consumption necessary to su of the emergency power soerce to y r ' the minimum required [pport the operation

$F systems.

Operation of minimum ESF systems 16 required to mitigate a design basis acci-in one unit and those minimum required systems for a concurrent dont (LOCA)fe shutdown in the remaininfi unit (both units initially in Mode 1 non-LOCA sa i

operation)of minimum CSF systems.The fuel oil consumption <

s calculated for a period of 7 days operation.

This requirement provides a sufficient operating period within which offsite power can be restored and/or additional fuel can be delivered to the site.

The diesel fuel oil stmas system consists of two common tanks with a nominal capacity of 40,000 gailons each and six emergency diesel generator l

(EDG) fuel oil day tanks with a nominal capacity of 550 gallons each. The fuel oil maintained in each day tank is used for the start and the initial operation of the associated EDG. Additional fuel oil is transferred from the storage tanks via the diesel fuel oil storage and transfer system to replenish the day tanks as required. The design incorporates sufficient redundancy so that a malfunction of either an active or a passive component will not 1spair the ability of the system to supply fuel oil.

Two redundant fuel oil transfer pumps supply fuel oil to EDG day tanks from either storage tank. One pump is adequate to supply the six EDGs operat-ing at full load. Each EDG day tank has two separate redundant transfer pump start-stop level switches. ' Each level switch automatically starts a transfer pump and opens the supply header solenoid valve corresponding to the respective transfer pump, 0-1 or 0-2.

In addition, high and low level alarms are provided on each day tank and activate alarms both locally and in the control room.

DIABLO CANYON - UNITS 1-& 2 8 3/4-8 Amendment Nos. O O 0. 44 O. 74 e 7 7; & 78.-06+M, 93 & 92

[LECTRICAL POWER SYSTEMS BASES A.C. Sources. D.C. Sources, and DNSITE POWER DISTRIBUTION (Continued)

The Technical Specifications required minimum fuel oil in each EDG day tank is a contained quantity sufficient for EDG operation at full load for a nominal one-hour period. One hour is adequate time for an operator to take corrective action to restore the fuel oil supply to the affected day tank. The EDG day tank 31-day surveillance frequency is adequate to assure that a sufficient supply of fuel oil is available, since the transfer pumps auto-starts are at a level above the Technical Specification's minimum contained volume. Therefore normal EDG operation will not result in day tank levels belowtheTechnicalSpecificationsminimumrequiredvolume. Additional assurance of su?ficient day tank contained volume is provided by a low level alarm.

For pro)er operation of the EDGs, it is necessary to ensure the proper quality of tie fuel oil.

Regulatory Guide 1.137, ' Fuel 011 Systems for Standby Diesel Generators,' Revision 1, October 1979, as supplemented by ANSI N195-1976, addresses the recommended fuel oil practices. The surveillance frequencies of Technical Specifications 4.8.1.1.2d. and 4.8.1.1.3b. for chcking and removing accumulated water from the day tank and main storage tank, respectively, are established by Regulatory Guide 1.137. Revision 1.

The Surveill s ce Requirements of Technical Specification 4.8.1.1.3e.1) for draining the fuel stored in the fuel oil storage tanks, removing accumulated sediment, and tank cleaning are in accordance with the reconnendations of pegulatory Guide 1.137. Revision 1.

Surveillance Requirements for the assurance of fuel oil quality are in accordance with the ASTM Standards specified in Technical Specification 4.8.1.1.3.

The Surveillance Requirements applicable to diesel generator fuel oil storage requires cleaning the fuel oil storage tanks on a 10-year frequency.

Cond1cting this surveillance requires the tank to be taken out of service.

For this infrequent event, the inventory in the remaining tank is sufficient to support operation of the emergency diesel generator to power the minimum required loads to maintain safe conditions for a time period of 4 days, considering one unit in Mode 1 through 6 operation and one unit in Mode 6 operation with at least 23 feet of water above t;ie reactor vessel flange or with the reactor defueled.

3/4.8.4 DELETED l

DIABLO CANYON - UNITS 1 1 2 B 3/4 8-3a Unit 1 - Amendr.ent No. 40,74,05.03,120 Unit 2 - Amendment No. -1S,73,85,02.118

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