ML20092D995

Amends 67 & 66 to Licenses DPR-80 & DPR-82,respectively, Relocating Procedural Details of RETS or PCP & Implementing Programmatic Controls

ML20092D995
Person / Time
Site:	Diablo Canyon
Issue date:	01/22/1992
From:	Quay T Office of Nuclear Reactor Regulation
To:
Shared Package
ML20092D998	List: ML20092D995 ML20092E002
References
NUDOCS 9202140397
Download: ML20092D995 (47)

Text

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UNITED STATES

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2-WASHINGTON, D.C 20$55 pf PACIFIC GAS AND ELECTRIC COMPANY DIABLO CANYON NUCLEAR POWER PLANT, UNIT NO. I 1

DOCKET NO. 50-275 AMENDMENT TO FACILITY OPERATING LICENSE l

Amendment No. 67 License No. DPR-80

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-1.

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

A.

The application for amendment by Pacific Gas & Electric Company (the licensee) dated May 23, 1991, complies with the standards and rec;uire-ments of. the Atomic Energy Act of 1954, as amended (the Act), anc the Commission's regulations set forth in 10 CFR Chapter I; B.

The facility will operate in conformity _ with the applicatior, the provisions of the' Act, and the regulations'of the Comission;

._ C.

There-is reasonable assurance-(i) that the activitier authorized by this amendment can be conducted without endangering the health and

. safety of. the public, and (ii) that such activities will be -

corducted in compliance with the Comission's regulations; D.

The issuance of this amendrent 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 chaages to the Technical

~

Specifications as' indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility

• 0perating License No. DPR-80 is hereby amended to read as follows:

9202140397 920122 PDR ADOCK 05000275-

P-PDR

2 (2) Technical _ Specifications

-The Technical Specifications contained in Appendix A and the Environnental Protection Plar. contained in Appendix B, as revised through Amendment No. 67

. are hereby incorperated in the license.

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

3.

This license arendment becomes effective as of the date of its issuance and is to be fully implemented within 90 days of its issuance.

FOR THE NUCLEAR REGULATOPY COMMISSION f

Theodore R. Quay, Director Project Directorate V Division of Reactor Pmfects III/IV/V Office of Nuclear Reactor Regulation

Attachment:

Changes to the Techrical Specifications Date of Issuar.ce:

January 22, 1992

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. UNITED STATES -

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NUCLEAR REGULATORY COMMISSION 3-s-

WASHING TON, D. C,20$56 b,

L PACIFIC GAS AND ELECTRIC COMPANY DIABLO CANYON NUCLEAR POWER PLANT, UNIT NO. 2 DOCKET NO. 50-323 AJjENDMENT TO FACILITY OPERATING LICENSE I

Amer /n nt No. 66-License No. DPR - 1. - - The Nuclear Regulatory Comission (the Commission) has fobnd that:

A.

. The application for; amendment-by Pacific Gas & Electric Company (the.

licensee). dated May ?3,1991, complies with-the standards and require-s

~

ments~ of the Atomic Energy Act of 1954, as amended-(the Act),

a and the Comission's regulations-set forth in -10 CFR Chapter I;'

B.

Theifacility will operate in confomity with the application, the provisions of'the Act, and the-reculations 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 amendstent will not be: inimical to the common idefense 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 reqilirements-have

.been satisfied.

l 2.- - Mcordingly, 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 arended to read as follows:

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Technical Specifications The Technical Specifications contained in Appendix A ard the Environrental Protection Plan contained in Appendix B, as revised through Amendment No. 66

, are hereby incorporated in the license.

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

3.

This license amendment becomes effective as of the date of its issuance and is to be fully implemented within 90 days of its issuance.

FOR THE NUCLEAR REGULATORY C0ftilSSION Y.

oh &

Theodore R. Quay Director Project Directorate V Division of Reactor Projects III/IV/V Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical Specifications Date of Issuance:

January 22, 1992 i

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ATTACHMENT TO LICENSE AMEN 0 MENT NOS. 67 AND 66 FACILITY OPERATING LICENSE N05. DPR-80 AND DPR-82 DOCKET N05. 50-275 AND 50-323 Revise Appendix A-Technical Specifications by removing the pages identified below and inserting the enclosed pages. The revised pages are identified by the captioned amendment number and contain marginal lines indicating the area of change. Overleaf pages are also included, as appropriate.

REMOVE PAGE INSERT PAGE 11

-11 vii vii xiii xiii xviii xviii xxii '

xxii xxiii xxiii 1-3 1-3 5 1-5 1-6 1-6 1-7a 3/4-3-25 3/4 3-25

-3/4 3 3/4 3-37 3/4 3-59 3/4 3-59 3/4 3-60 3/4 3-60 3/4 3-61 thru 3/4 3-69 3/4-11-l' 3/4 11-1 3/4 11-2 3/4 11-2 3/4 11-3 3/4 11-3 3/4 11-4 thru 3/4 11-18 3/412-1 thru 3/412-13 3/4 12-1 B3/4 3-4 B3/4 3-4 B3/4 3-5 B3/4-3-5 B3/4_11-1 thru B3/4 11-8 B3/4 11-1 B3/4 12-1 thru B3/4 12 B3/4 12-1 6-15a 6-15a 6-15b

.6-17 6-17 6-18 6-18 6-19 6 6-20 6-20 21 6-21 6-22 6-22 6-23 6-23 6-24 6-25

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DEFINITIONS' SECTION PAGE 1.0 DEFINITIONS 1.1 ACT!0N...........................................................

1-1.

1.2 -ACTUATION LOGIC TEST.............................................

1-1 1.3 ANALOG-CHANNEL OPERATIONAL TEST..................................

1-1 1.4 AX I AL F LUX DI F F E RENCE.............................. ;.............

1-1 1.5 CHANNEL CALIBRAT10N..............................................

1-1 1.6 CHANNEL CHECK.....................................................

1-1 S

-1.7 CHANNEL FUNCTIONAL TEST..........................................

1-2 1.8 CONTAINMENT INTEGRITY............................................

1-2 1.9 CONTROLLED LEAKAGE...............................................

1-2 1.10 CORE ALTERATIONS.................................................

1-2 1.11 DOSE EQUIVALENT I-131............................................

1-3 1.12 E - AVERAGE DISINTEGRATION ENERGY................................

1-3 1;13 ENGINEERED SAFETY FEATURES RESPONSE TIME.........................

1-3 1.14 ENVIRONMENTAL RADIOLOGICAL MONITORING PROCEDURE..................

1-3 1.15-FREQUENCYLN0TATION..........................

1-3 1.16 GASE0US RA0 WASTE SYSTEM..........................................

1-3 1.17 IDENTIFIED LEAKAGE...............................................

14 1.18 MASTER RELAY TEST................................................

1-4 1.19= MEMBER (S) 0F THE PUBLIC..........................................

14

'1.20 0FFSITE DOSE CALCULATION PROCEDURE...............................

1-4

1. 21 O P E RAB L E - O P E RAB I L I TY...........................................

1-4 1~22 OPERATIONAL ~ MODE - M00E..........................................

1-5

1.23 PHYSICS TESTS....................................................

1*5 1.24 PRESCURE BOUNDARY LEAKAGE........................................

1-5 1.25 PROCESS CONTROL PR0 GRAM..........................................

1-5

- 1. 2 6 P U RG E - P U RG I NG..................................................

1-5 1.27 QUADRANT POWER TILT RAT!0........................................

1-5 1.28 RATED THERMAL P0WER..............................................

1-5 1,29 REACTOR TRIP SYSTEM RESPONSE TIME................................

1-6 1.30 EEPORTABLE EVENT.................................................

1-6 DIABLO CANYON - UNITS 1 & 2 i

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s INDEX

" DEFINITIONS-

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SECTION-

- PAGE DEFINITIONS (Continued)-

l'.31 SHUTDOWN MARGIN..................................................

1-6--

1.32 SITE B00NDARY....................................................

156

1. 3 3 S L AVE R E LAY. T E ST.................................................

1-6

' I.~ 34 r Del eted i

1.35 SOURCE CHECK............................................_.........

1-6 1.36 STAGGERED TEST BASIS.............................................

1-6 1.37 THERMAL P0WER.................................................... 7 1,38 TRIP ACTUATING DEVICE OPERATIONAL TEST..........................,

11-7 1.39 UNIDENTIFIED: LEAKAGE.............................................

1-7

-l'401 UNRESTRICTED AREA................................................

1 --

t 11.41 VENTILATION' EXHAUST TREATMENT SYSTEM.............................-

1-7 11.42 VENTING........_..................................................-

1-7 J1.43? CORE OPERATING-LIMITS REP 0RT.....................................

1-7

-1.44' RADIOLOGICAL MONITORING'~AND CONTROLS PR0 GRAM..................... 7a l

- TABLE"1.1 FREQUENCY-NOTATION.........................................

1-8 TABLE-1.2 OPERATIONAL =M0 DES........................................... 9

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E DIABLO CANYON - UNITS 1 & 2 i i Amendment Nos. 67 and 66

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INDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION Page 3/4.3 INSTRUMENTATION (continued)

Chlorine Detection Systems...............................

3/4 3-54 Fire Detection Instrumentation..........................

3/4 3-55 TABLE 3.3-11 FIRE DETECTION INSTRUMENTS..........................

3/4 3-56 Explosive Gas Monitoring Instrumentation................

3/4 3-59 3/4.3.4 TURBINE OVERSPEED PROTECTION............................

3/4 3-60 3/4.4 REACTOR'C00LANT SYSTEM 3/4.4.1 REACTOR COOLANT LOOPS AND COOLANT CIRCULATION

Startup and Power 0peration.............................

3/4 4-1 Hot Standby...............................

3/4 4-2 Hot Shetdown......................

3/4 4-3 Col d Shutdown - Loops F ill ed............................

3/4 4-5 Cold-Shutdown - Loops Not F111ed........................

3/4 4-6 3/4.4.2

= SAFETY VALVES Shutdown................................................

3/4 4-7

-0perating................................................

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

3/4 4-9 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 Amendment Nos.67 and 66

INDEX t!MITING CONDITIONS FOR OPERATION AND SURVE!LLANCE REQUIREMENTS SECTION PAGE 3/4.4 REACTOR COOLANT SYSTEM (continued)

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

3/4 4-16 Tali 4.4-2 STEAM GENERATOR TUBE INSPECTION......................

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

3/4 4-18 Operational Leakage.....................................

3/4 4-19

-TABLE 3.4-1 REACTOR COOLANT SYSTEM PRESSURE ISOLATION VALVES.....

3/4 4-21 3/4.4.7 CHEMISTRY...............................................

3/4 4-22 TABLE 3.4-2 REACTOR COOLANT SYSTEM CHEMISTRY LIMITS..............

3/4 4-23 TABLE 4.4-3 REACTOR COOLANT SYSTEM CHEMISTRY LIMITS 3URVEILLANCE REQUIREMENTS...............................

3/4 4-24 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 DDSE EQUIVALENT I-131......................

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

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

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

APPLICABLE UP TO 8 EFPY................................

3/4 4-J1 l

FIGURE 3.4-3 REACTOR COOLANT SYSTEM C00LDOWN LIMITATIONS -

APPLICABLE UP TO 8 EFPY................................

3/4 4-32 Pressurizer.............................................

3/4 4-34

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

3/4 4-35

-3/4.4.10' STRUCTURAL INTEGRITY....................................

3/4 4-37

~3/4.4.11 REACTOR VESSEL P.EAD VENTS...............................

3/4 4-38 l

DIABLO CANYON - UNITS 1 & 2 viii Amendment Nos.54 and 53 hg lls l4 90 J

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INDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION

,P_ age a

3/4.11 -RADI0 ACTIVE 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 J

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

INDEX BASES' SECTION :

g 3/4.0 APPLICABILITY.............................................

B 3/4 0-1 Jf4.1 REACTIVITY CONTROL SYSTEMS 3/4.1.1 BORATION CONTR0L.........................................

B 3/4 1-1 3/4.1.2 BORATION SYSTEMS.........................................

B 3/4 1-2 3/4.1.3 M3VABLE CONTROL ASSEMBLIES...............................

B 3/4 1-3 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-Fi.UX 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

}/4.3 INSTRUMFNTATION-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. TURBINE OVERSPEED PROTECTION.............................

B 3/4 3-5 l

~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 Amendment Nos.12and 10 JAN 3 0198)

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INDEX-

' OASES L

SECTION:

PAGE 3/4.9 REFUP.!NG OPERATIONS 3/4.9.1 BORON CONCENTRATION.....................................

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

B 3/4 9-1 3/4.9.3 OECAY-TIME..............................................

B 3/4 9-1

_3/4.9.4-CONTAINMENT PENETRATIONS................................

B 3/4-9-1 3/4.9.5 COMMUNICATIONS..........................................

B_3/4 9-1 3/4.9.6 MANIPULATOR-CRANE.......................................

B 3/4 9-1 3/4.9.7 CRANE. TRAVEL - FUEL-HANDLING BUILDING...................

B 3/4 9-2 3/4.9.8 RESIDUAL HEAT REMOVAL AND COOLANT CIRCULATION...........

B 3/4 9-2

3/4.9.9 CONTAINMENT _ VENTILATION ISOLATION SYSTEM................

B 3/4 9-2 3/4.9.10 and 3/4.9.11 l WATER LEVEL - REACTOR VESSEL and SPENT FUEL P00L....................................................

B 3/4 9-2 3/4.9.12 FUEL HANDLING BUILOING VENTILATION SYSTEM...............-

B 3/4 9-3 3/4.9.13 SPENT FUEL SHIPPING CASK M0VEMENT.......................

B 3/4 9-3 3/4.10 SPECIAL TEST EXCEPTIONS-3/4.10.1 -SHUTDOWN MARGIN.........................................

B 3/4 10-1 3/4.10.2..GR3UP HEIGHT, INSFRTION, AND POWER DISTRIBUTION LIMITS..................................................

B 3/4 10-1 J

3/4.10.3 PHYSICS TESTS...........................................

8 3/4-10 3/4.10.4 -POSITION INDICATION SYSTEM - SHUTDOWN...................

B 3/4.10.DIABLO CANYON - UNITS 1 & 2 xvii

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4 INDEX

-BASES SECTION

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PAGE 3/4.11 RADI0 ACTIVE EFFLUENTS 3/4.11.1 LIQUID EFFLUENTS.........................................

B 3/4 11-1 3/4.11.2 GASE0US EFFLUENTS........................................

B 3/4 11-1 DIABLO CANYON - UNITS 1 & 2 xviii Amendment Nos.67 and 66 l

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INDEX ADMINISTRATIVE CONTROLS L-

$ECTION PAGE-a6.1 RESPONSIBILITY....................................................-

61 6.2' 0RGANIZATION 6.2.1 0FFSITE.........................................................

6-1 1

6.2.21 PLANT STAFF.....................................................

6-1 TABLE 6.2-1 MINIMUM SHIFT CREW COMPOSITION............................

6-4 6.2.3 ONSITElSAFETYREVIEWGROUP(OSRG)

Function........................................................

6-6 l

Composition.....................................................

6-6 Responsibilities................................................

6-6 6.2.4. SHIFT TECHNICAL ADVIS0R.........................................

6-6 6.3 PLANT STAFF QUALIFICATIONS........................................

6-6 6.4 TRAINI_NG..........................................................

6-7

.6.5 -REVIEW AND AUDIT 9

6.5.1 PLANT' STAFF REVIEW COMMITTEE (PSRC)

Function........................................................

6-7

-Composition.....................................................

6-7.

Alternates......................................................-

6-7 Meeting Frequency...............................................

6-7

._ Quorum..........................................................

6-7 1 Responsibilities................................................

6-8 Records.........................................................

6-9 DIABLO CANYON - UNITS 1 & 2 xxi AMEh0 MENT NOS. 29 & 28

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INDEX-ADMINISTRATIVE CONTROLS I

- SECTION' -

PAGE

_6.5" REVIEW AND AUDIT (Continued) _

6.5.2 GENERAL OFFICE NUCLEAR PLANT _ REVIEW AND AUDIT COMMITTEE (GONPRAC)~

Function........................................................

6 Composition....................................................

6-10 A l t e rn a t e s.....................................................

6 ;

Consultants....................................................

6-10 Meeting Frequency..............................................

6 -Quorum.........................................................

6-10

. Review.........................................................

6-10

. Audits.........................................................

6 i Records........................................................

6-12

- 6. 6 - RE PORTAB L E EV ENT ACT I 0 N.......................................... -

6-12 6.7 SAFETY LIMIT V10LAT10N...........................................

6-13

6. 8 ' P ROC ED URE S AND P R0G RAMS.........................................

6-13

- 6.9 REPORTING REQUIREMENTS 6.9,1-~ ROUTINE REP 0RTS................................................

6-16 S ta rt u p R e po rt s................................................

6-16 Annual Reports.................................................

6-16 7

Annual Radiol _ogical-Environmental Operating Report.............

6-17 Semiannual ' Radioactive Effl uent.Rel ea se Report.................

_6-18 Monthly Ope ra ti n g Repo rt.......................................

6-18 CORE 0PERAT ING L IMI TS R EP0 RT...................................

5-18 6.9.2 SPECIAL REP 0RTS................................................

6-19

' 6.10 R ECO R D R ETE NT I O N................................................

6-19 6.11 RADIATION PROTECTION PR0GPAM....................................

6-21 6.12 HIGH RADIATIDN AREA.............................................-

6-21 DIABLO' CANYON UNITS 1 & 2 xxii Amendment Nos.67 and 66

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INDEX ADMINISTRATIVE CONTROLS SECTION PAGE 6.13 PROCESS CONTROL PROGRAM (PCP)...................................

6-22 6.14 RADIOLOGICAL MONITORING AND CONTROLS PROGRAM (RMCP), OFFSITE DOSE CALCULATION PROCEDURE (ODCP) and ENVIRONMENTAL RAD 10E6 DICAL MONITORING PROCEDURE (ERMP)......................................

6-23 e

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

I DEFINITIONS DOSE EQUIVALENT I-131 1.11 DOSE EQUIVALENT I-131 shall be that concentration of I-131 (microcuries/ gram) which alone would produce the same thyroid dose as the quantity and iso-topic mixture of I-131, I-132, I-133, I-134, and 1-135 actually present.

The thyroid dose conversion factors used for this calculation shall be those listed in Table III of TID-14844, " Calculation of Distance Factors for Power and Test Reactor Sites," or Table E ' of NRC Regulatory Guide 1.109,_ Revision 1, October 1977.

E - AVERAGE DISINTEGRATION ENERGY 1.12 E shall be the average (weighted in proportion to the concentration of each radionuclide in the sample) of the sum of the average beta and gamma energies per disintegration (MeV/d) for the radionuclides in the sample.

ENGINEERED SAFETY FEATURES RESPONSE TIME 1.13 The ENGINEERED SAFETY FEATURES (ESF) RESPONSE TIME shall be that time interval from when the monitored parameter exceeds its ESF actuation Setpoint at the channel sensor until the ESF equipment is capable of performing its safety function (i.e., the valves travel to their required positions, pump dis-charge pressures reach their required values, etc.). Times shall include diesel' generator starting and sequence loading delays where applicable.

ENV'RONMENTAL RADIOLOGICAL MONITORING PROCEDURE 1.14 The ENVIRONMENTAL RADIOLOGICAL MONITORING PROCEDURE (ERMP) shall contain a description of sample locations, types of sample locations, methods and frequency of analysis, and reporting requirements.

FREQUENCY NOTATION 1.15 The FREQUENCY NOTATION specified for the performance of Surveillance Requirements shall correspond to the intervals defined in Table 1.1.

GASE0US RADWASTE SYSTEM 1.16 A GASE0US RADWASTE SYSTEM shall be any system designed and installed to reduce radioactive gaseous effluents by collecting Reactor Coolant System offgases from the Reactor Coolant System and providing for delay or holdup for the purpose of reducing the total radioactivity prior to release to the environment.

DIABLO CANYON - UNITS 1 & 2 1-3 AMENDMENT N05. 67 AND 66

-DEFIN!TIONS IDENTIFIED LEAKh0E 1.17 IDENTIFIED LEAKAGE shali vez Leakage, except CONTR0Lt[D LEAKAGE, into closed systems, such a.

as pump seal or valve packing leaks that are captured and conducted to a sump or collecting tank, or b.

Leakage into the containment atmosphere from sources that are both specifically located and known either not to interfere with the operation of Leakage Detection Systems or not to be PRES $URE BOUNDARY LIAKAGE, or Reac+or Coolant System leakage through a steam generator to c.

the Secondary Coolant System.

MA5fER RELAY TEST 1.18 A MASTER RELAY TES1 shall be the energization of each master relay and verification of OPERABILITY of each relay.

The MASTER RELAY TEST shall include a continuity check of each associated slave relay.

MEMBER (S) 0F THE PUBllr 1.19 MEMBER (S) 0F THE PUBLI shall include 611 persons who are not occupationally associated with the plant.

This category does not include employees of the licensee, its contractors, or vendors.

Also excluded from this cate-Oory are persons who enter the site to service equipment or to mak; deliveries.

This category does include persora who v$c portions of the site for recreational occupational, or otner purposes not associated with the plant.

OFFSITE DOSE CALCULATION PROCEDURE 1.20 The 0FFSITE DOSE CALCULATION PROCEDURE (ODCP) sna11 contain the methodology and parameters used in the calculation of offsite doses due to radioactive gaseous and liquid effluents ai,d in the calculation of gaseous and 11gaid effluent monitoring Alarm / Trip Setpoints.

OPERABLE - OPERABILITY 1.21 A system subsystem, train, component or device shall be OPERABLE or have OPERABilfTYwhenitiscapableofperformingitsspecifiedfunction(s) and when all necesqary attendant instrumentation, controls, electric power, cooling or seal water, lubrication or other auxiliary equipment that are required for the rystem, subsystem, train, component or device to perform its function (s) are also capable of performing their related support function (;).

OlABLO LANYON - UNITS 1 & 2 1-4 I

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DE.clN1110NS OPERATIONAL H0DE - MODE 1.22AnOPERATIONALMODE(i.e.Ivitycondition,powerlevelandaveragereactor H0DE) shall correspond to any one inclusi a combination of core react coolant temperature specified in Table 1.2.

PHYSICS TESTS 1.23 PHYSICS TESTS shall be those tests performed to measure the fundamental

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nuclear...aracteristics of the reactor core and related instrumentation 1

and (1) described in Chapter 14.0 of the FSAR, (2) authorized under the provisions of 10 CFR 50.59, or (3) otherwise approved by the Commission.

PRESSURE BOUNDARY LEAKAGE 1.24 PRESSURE BOUNDARY LEAKAGE shall be leakage, except steam generator tube leaka0e through a non-isolable fault in a Reactor Coolant System component body,plpewallorvesselwall.

PROCESS CONTROL PROGRAM 1.25 The PROCESS CONTROL PROGRAM (PCP) shall contain the current formulas, sam-pling, analyses, tests, and determinations to be me.de to ensure that pro-cessing and packaging of solid radioactive wastes based on demonstrated processing of actual or simulated wet solid wastes will be accomplished in such a way as to assure compliance with 10 CFR Parts 20, 61, and 71 and Federal and State regulations, burial ground requirements, and other re-quirements governing the disposal of solid radioactive waste.

PURGE - PURGING 1.26 PURGE or PURGING shall be the controlled process of discharging air or gas from a confinement to maintain temperature, pressure, humidity,

';oncentration or other operating condition, in sach a manner that replacement air or gas is required to purify the confinement.

QUADRANT POWER TILT RATIO 1.27 QUADRANT POWER TILT RATIO shall be the ratio of the maximum upper excore detector calibrated output to the average of the upper excore &tector calibrated outputs, or the ratio of the maximum lower excore detector calibrated output to the average of the lower excore detector calibrated outputs, whichever i.

eater.

With one excore detector inoperable, the remaining three detectors shall be used for computing the average.

RATED THERMAL POWER 1.28 RATED THERHAL POWER shall be a total reactor core heat transfer rate to the reactor coolant of 3338 MWt for Unit 1 and 3411 Mdt for Unit 2.

DIABLO CANYON - UNITS 1 & 2 1-5 AMENDMENT N05.67 AND 66

DEFINITIONS REACTOR TRIP SYSTEM RESPONSE TIME 1.29 The REACTOR TRIP SYSTEM RESPONSE TIME shall be the time interval from when the monitorto ptr arater cxceeds its trip setpoint at the channel sensor until loss of stationary gripper coil voltage.

REPORTABLE EVENT 1.30 A REPORTABLE EVENT shall be any of those conditions specified in Section 50.73 of 10 CFR Part 50.

SHUTDOWN MARGIN 1.31 SHUTDOWN MARGIN sr 11 be the instantaneous amount of reactivity by which the reactor is suberitical or would be subcritical from its present condition assuming all full length rod cluster assemblies (shutdown and control) are fully inserted except for the single rod cluster assembly of highest reactivity worth which is assumed to be fully withdrawn.

SITE BOUNDARY 1.32 511E BOUNDARY shall be that line as shown in Figure 5.1-3.

SLAVE RELAY TEST 1.33 A SLAVE RELAY TEST shall be the energization of each slave relay and verification of OPERABILITY of each relay..The SLAVE RELAY TEST shall includc a continuity check, as a minimum, of associated testable actuation devices.

1.34 Deleted SOURCE CHECK 1.35 A SOURCE CHECK shall be the qualitative assessment of channe? response when the channel sensor is exposed to a source of increased radioactivity.

STAGGERED TEST BASIS 1,16 A STAGGERED TEST BASIS shall consist of:

a.

A. test. schedule for n systems, subsystems, trains or other designated components obtained by dividing the specified test interval into n equal subintervals, and

.b.

The testing of one system, subsystem, train or other designated component at the beginning of each subinterval.

1 DIABLO CANYON - UNITS 1 & 2 1-6 AMENDMENT NOS. 67 AND 66

DEFINITIONS RADIOLOGICAL MON!10 RING AND CONTROLS PROGRAh 1.44 The RADIOLOGICAL HONITORING AND CONTROLS PROGRAM (RMCP) shall contain (1) the Radinactive Effluent Controls and Radiological Environmental Monitoring Programs required by Section 6.8.4 and (2) 6escriptions of the information that should be included in the Annual Radiological Environmental Operating and Semiannual Radioactive Effluent Release Reports required by Specifications 6.9.1.5 and 6.9.1.6.

L DIABLO. CANYON - UNITS 1 & 2 1-la AMENDMinf NOS. 67 AND 66 w-

1-n -

j r

if i

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- o TABIE 3.3-4 (Continued) 5;*

L y

. ENGINEERED SAFETY. FEATURES Af idATION SYSTEN INSTRUNENTATION TRIP SETPOINTS ok 5, FUNCTIONAL' UNIT TRIP SETPOINT ALLOWABLE VALUES li

'E-l

~

3.

Containment Isolation (Continued) i e-5.

c.

Containment Ventilation Isolation i

d 1)

Automatic Actuation Logic

'N.A.

M.A.

~

p and Actuation Relays l

2)

Plant Vent Noble Gas Per the 00CP l..

I N

-Activity-High'(RM-14A 1-and 148)-

3)

Safety. Injection See Item 1. above for all Safety Injection Trip Setpoints 3j.

and Allowable Values.

w i

k I

4.

Steam Line Isolation w

4 i

e' a.

Manual N.A.

N.A.

f b.

Automatic Actuation Logic M.A.

N.A.

1 j-and Actuation Relays c.

Containment Pressure-High-High i 22 psig i 24 psig i

d.

Steam Flow'in Two Steam Lines-

< A function defined as-

< A function defined as

$k High-Tollows: A ap correspond-Tollows: A ap corresponding m

ing to 40% of full steam to 44% of full steam flow be-

)

{

j 8.gg flow between 0% and 20%

t e n 0% and 20% load and

~

eg icad and then a op increas-then a op increasing linearly j

j

' ing linearly to a op corre-to a op corresponding to z

j sponding to 110% of full 111.5% of full steam flow at o

steam flow at full load.

full load.

D Coincident With Either i

o, E

1)

T,yg-Low-Low,'or 1 543*F

> 540.2*

i M

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2). Steam Line Pressure-Low

't 600 psig 1 580 psig e

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~ _, _. _ -

f c

l TABLE 3.3-4 (Continued)

ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUNENTATION TRIP SETPCINTS 5

n E

FUNCTIONAL llNIT TRIP SETPOINT ALLOWROLE VALUES a

4 l

7 5.

Turbine Trip and Feedwater Isolation E

a.

Automatic Actuation Logic M.A.

N.A.

]

anr1 Actuation Relays b.

Steam Generator Water level-

< 67% of narrow range

< 685 of narrow range

[

High-High Tnstrument span each steam Tastroent span each steam senerator.

generator.

6.

Auxiliary Feedwater a.

Manual K. A.

N.A.

b.

Automatic Actuation Logic M.A.

M.A.

y and Actuation Relays 5

c.

Steam Generator

>7.2% of narrow range

>6.2% of narrow range Water Level-Lew-Low Instrument span each Tastrument spen ee..

steam generator.

steam generator.

f d.

Undervoltage - RCP 1 8050 volts 1 7335 volts D

e.

Safety Injection See Item 1. above for all Safety Injection Trip Setpoints l

P and Allowable Values.

CT o E.7 a

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TABLE 3.3-6_

.e.'

RADIATION MONITORING INSTRUMENTATION FOR PLANT OPERATIONS n

MINIMUM SE '

CHANNELS APPLICABLE ALARM / TRIP INSTRUMENT OPERABLE MODES SETPOINT ACTION

[

1.

Fuel Storage Area x

3 a.

Spent Fuel Pool 1

1 75 mR/hr 30 & 32**

[

b.

New Fuel Storage 1

1 15 mR/hr 30 & 32**

2.

Control Room Ventilation Mode Change 2***

All i 2 mR/hr 34 3.

Containment y

a.

Gasecus Activity T

1) Containment 1

6 Per the ODCP 33 0

Ventilation Isolation (RM-14A or 14B)

2) RCS Leakage 1

1, 2, 3, 4 N.A.

31 b.

Particulate Activity gg.

RCS Leakage 1

1,2,3,4 N.A.

31 E. g r

e*E T

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

• • With irradiated fuel in the spent fuel pool.

m

{

• • • 0ne channel for each normal intake to the Control Room Ventilation System (cospon to both units).

E

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c

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- - - ~ -.-- -

TAllf_3.3-6 (Continued)

ACTION $7ATEMENTS ACTION 30 -

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

Restore the inoperable monitors to OPERABLE status within 30 days or suspend all operations involving fuel movement in the fuel storage pool areas.

ACTION 31 -

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

The provisions of

$pecification 3.0.4 are not applicable.

A0 TION 32 -

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

ACTION 33 -

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

ACTION 34 -

With the number of OPERABLE channels less than required by the Minimum Channels OPERABLE requirement, within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> initiate and maintain operation of the Control Room Ventilatic5 System in a recirculation mode with the HEPA filter and charcoal adsorber bank in operation.

DIABLO CANYON - UNITS 1 & 2 3/4 3-38 Amendment Nos. 55 and 54 JUN 111990 4

INSTRUMENTATION EXPLOSIVE GAS EFFLUENT MONITORING INSTRUMENTATION LIMITING '0NDITION FOR OPERATION 3.3.3.9 Deleted 3.3.3.10 The explosive gas monitoring instrumentation channels (ANR-75 or ANR 76) shall be OPERABLE with their Alarm / Trip Setpoints set to ensure that the limits of Specification 3.11.2.5 are not exceeded.

APPLICABILITY:

During GASEOUS RA0 WASTE SYSTEM operation.

ACTION:

a.

With an explosive gas monitoring instrumentation channel (ANR-75 or ANR-76) Alarm / Trip Setpoint less conservative than required by 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 OPERABLE, operation of this system may continue provided grab samples are collected at least once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> and analyzed within the following 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> c.

The provisions of Specification 3.0.3 are not applicable.

SURVEILLANCEREQUIREMENTS 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 CHANNEL CHECK and d monthly CHANNEL FUNCTIONAL TEST.

4.3.3.10.2 Each explosive gas monitoring instrumentation 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 nitrogen, and b.

Four volume percent oxygen, balance nitrogen.

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

1 INSTRUMENTATION 3/4.3.4 TURBINE OVERSPEED PROTECTION LIMITING CONDITION FOR OPERATION 3.3.4.1 At-least one Turblot Overspeed Protection System shall be OPERABLE.

APPLICABILITY:

MODES 1, 2 and 3 (during turbine operation).

ACTION:

a.

With one stop valve or one control valve per high pressure turbine steam line inoperable or with one reheat stop valve or one reheat intercept valve per low pressure turbine steam line inoperable, restore the inoperable valve (s) to OPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />, or isolate the turbine from the steam supply within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.

b.

With the above required Turbine Overspeed Protection System otherwise inoperable, within-6 hours isolate the turbine from the steam supply.

i SURVEILLANCE REQUIREMENTS 4.3.4.1.1 The provisions of Specification 4.0.4 are not applicable.

4.3.4.1.2 The above required Turbine Overspeed Protection System shall be demonstrated OPERABLE:

a.

At least once per quarter by cycling and direct observation of the movement of each of the following valves through at least one complete cycle from the running position:

1)

Four high pressure _ turbine stop valves, 2)

Four high pressure turbine control valves, 3)

Six low pressure turbine reheat stop valves, and 4)

Six low pressure-turbine reheat intercept valves, b.

At least once per 18 months by' performance of a CHANNEL CAllBRATION on the Turbine Overspeed Protection Systems.

c.

At least once per 40. months by disassembling-at least one of each of the above valves and-performing a visual and surface inspection of valve seats, disks and stems and verifying no unacceptable flaws or corrosion.

DIABLO CANYON - UNITS 1 & 2 3/4 3-60 Amendment Nos. //andII

61 and 66 t

RADI0 ACTIVE EFFLUENTS LIQUID HOLDUP TANKS LIMITING CONDITION FOR OPERATION 3.11.1.1 - 3.11.1.3 Deleted 3.11.1.4 The quantity of radioactive material contained in any temporary l

outdoor tanks shall be limited to less than or equal to 10 curies, excluding tritium and dissolved or entrained noble gases.

APPLICABILITY:

At all times.

ACTION:

a.

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

b.

The provisions of Specification 3.0.3 are not applicable.

SURVEILLANCE REQUIREMENTS 4.11.1.1 - 4.11.1.3 Deleted 4.11.3.4 The quantity of radioactive material contained in each of the temporary outdoor tanks shall be determined to be within the above limit by analyzing a representative sample of the tank's contents at least once per 7 days when radioactive materials are being added to the tank.

l l

I DIABLO CANYON - UNITS 1 & 2 3/4 11-1 Amendment Nos. 67 and 66

RADIDACTIVE EFFLUENTS EXPLOSIVE GAS MIXTURE L1HITING CONDITION FOR OPERATION 3.11.2.1 - 3.11.2.4 Deleted 3.11.2.5 The concentration of oxygen in the GASEOUS RADWASTE SYSTEM shall be limited to less than or equal to 2% by volume whenever the hydrogen conceatra-tion exceeds 4% by "olume.

APPLICABILITY:

At all times.

ACTION:

a.

With the concentration of oxygen in the GASEOUS RADWASTE SYSTEM greater than 2% by volume but less than or equal 4% by volume, reduce the oxygen concentration to the above limits within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />.

b.

With the concentration of oxygen in the CASE 00$ RADWASTE SYSTEM greater than 4% by volume and the hydrogen concentration greater than 4% by volume, immediately suspend all additions of waste gases to the system and reduce the concentration of oxygen to less than or equal to 4% by volume, then take ACTION a., above.

c.

The provisions of Specification 3.0.3 are not applicable.

SURVEILLANCE REQUIREMENTS 4.11.2.1 - 4.11.2.4 Deleted 4.11.2.5 The concentration of hydrogen

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

i 1

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

DIABLO CANYON - UNITS 1 & 2 3/4 11-2 Amendment Nos. 67 and 66

.gu

,c.

n.

n-.

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.n,

-. ~,. -

~,

~,.m.n

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

APPLICABILITY:

At all times.

ACTION:

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

exceeding the above limit, immediately susp6ac all additions of radioactive material to the tank, within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> reduce the tank contents'to within the limit, and describe the events leading to this condition in the next Semiannual Radioactive Effluent Release Report, pursuant to Specification 6.9.1.6.

b.-

The provisions of Specification 3.0.3 are not applicable.

3.11.3 Deleted 3.11.4 Deleted SURVEILLANCE PEQUIREMENTS 4.11.2.6 The quantity of radioactive material contained in each gas decay tank shall be determined to be within the above limit at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> when radioactive materials are being added to the tank.

-4.11.3 Deleted 4.11.4 Deleted DIABLO CANYON - UNITS 1 & 2 3/4 11-3 Amendment Nos. 67 and 66

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3/4.12 Deleted in its entirety.

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INSTRUMENTATION BASES 3/4.3.3.3 $EISHICINSTRUMfNTATIOJ The OPERABILITY of the seismic instrumentation ensures that sufficient capability is available to promptly determine the magnitude of a seismic event and evaluate the response of those features important to safety.

This capability is required to permit comparison of the measured response to that used in the design basis for the facility to determine if plant shutdown is required pur-suant to Appendix A of 10 CFR Part 100.

The instrumentation is consistent with the recommendations of Regulatory Guide 1.12. " Instrumentation for Earthyakes."

3/4.3.3.4 HETEOROLOGICAL INSTRUMENTATION The OPERABILITY of the meteorological instrumentation ensures that sufficient meteorological data is available for estimating potential radiation doses to the public as a result of routine or accidental release of radioactive materials to the atmusphere.

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 INSTRUMENTATION The OPERABILITY of the remote shutdown instrumentation ensures that sufficient capability is available to permit shutdown and maintenance of HOT STANDBY of the facility from locations outside of the control room.

This capability is required in the event control room habitability is lost and 16 consistent with General Design Criterion 19 of 10 CFR Part 50.

3/4.3.3.6 ACCIDENT MONITORING INSTRUMENTATION, The OPERABILITY of the accident monitoring instrumentation ensures that 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 1903, and NUREG 0737, " Clarification of THI Action Plan Renuirements," November 1980.

3/4.3.3.7 _CHLORJNE DETECTION SYSTEMS The OPERABILITY of the Chlorine Detection System ensures that sufficient capability is available to promptly detect and initiate protective action in the event of an accidantal chlorine release.

This capability is required to protect control room personnel and is consistent with the recommendations of Regulatory Guide 1.95, " Protection of Nuclear Power Plant Control Room Operators Against an Accidental Chlorine Release," February 1975.

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

INSTRUMENTATION BASES 3/4.3.3.8 flRE DETECTION INSTRUMENTATION The OPEPABILITY of the detection instrumentation ensures that adequate warning capability is available for prompt detection of fires.

This capability is required in order to detect and locate fires in their early stages.

Prompt detection of flees will reduce the potential for damage to safety-related equipment and is an integral element in the overall facility Fire Protection Program.

In the event thet a portion of the fire detection instrumentation is inoperable, the establishment of frequent fire patrols in the affected areas is required to provide detection capability until the inoperable instrumenta-tion is restored to OPERABILITY.

Since the fire detectors installed in the plant are nonseismic, an inspection will be performed following a seismic event to detect any fires.

3/4.3.3.9 RADI0 ACTIVE LIQUID EFFLUENT MONITORIJ4G INSTRUMENTATION Section relocated to RMCP.

l l

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

!~L

INSTRUMENTATION BASES

)

3/4.3.3.10 EXPLOSIVE GAS MONITORING INSTRUMENTA110N l

The explosive gas instrumentation is provided for monitoring (and controlling) the concentrations of potentially explosive gas mixtures in the GASEOUS RADWASTE SYSTEM.

l 3/4.3.4 TURBINE OVERSPEE_0 PROTECTION

.This specification is provided to ensure that the turbine overspeed l

protection instrumentation and the turbine speed control valves are OPERABLE and will protect the turbine from excessive overspeed. Protection from turbine excessive overspeed is required since excessive overspeed of the turbine could r

generate potentially damaging missiles which could impact and damage safety related components, equipment or structures.

. The quarterly valve test frequency required by Specification 4.3.4.1.2a, is based on Otablo Canyon operating experience and the results of an evaluation documented in WCAP-11525, "Probabilistic Evaluation of Reduction in Turbine Valve Test frequency," June 1987.

The evaluation shows that for Diablo Canyon the probability of turbine missile generation is within the NRC acceptance criteria (letter from C. E. Rossi, USNRC, to J. A. Martin, Westinghouse, dated February-2,1987) for turbine valve test intervals up to seven months.

l' t

DIABLO CANYON - UN11S 1&2 B 3/4 3-5 Amendment Nos. $? and 47, 67 and 66 f

RADIDACTIVE EFFLUENTS BASES 3/4.11.1 LIQUID EFFLUENTS 3/4.11.1.1 -Relocated to RMCP.

3/4.11.1.2 Relocated to RMCP.

3/4.11.1.3 Relocated to RMCP.

i 3/4.11.1.4 LIQUID HOLDUP TANKS The tanks listed in this specification include all those outdoor radwaste l

tanks that are not surrounded by liners, dikes or walls capable of holding the tank contents and that do not have tank overflows and surrounding area drains connected to the Liquid Radwaste Treatment System.

Restricting the quantity of radioactive material contained in the specified tanks provides assurance that in the event of an uncontrolled release of the tank's contents, the resulting concentrations would be less than the limits of 10 CFR Part 20, Appendix B. Table II, Column 2, at the nearest potable water supply and the nearest surface water supply in an UNRESTRICTED AREA.

3/4.11.2 GASEOUS __ EFFLUENTS 3/4.11.2.1 Relcoated to RMCP.

3/4.11.2.2 Relocated to RMCP.

3/4.11.2.3 Relocated to RMCP.

3/4.11.2.4 Relocated to RMCP.

t 3/4.11.2.5 EXPLOSIVE GAS MIXTURE This specification is provided to ensure that the concentration of poten-tially explosive gas mixtures contained in the GASEOUS RADWASTE SYSTEM is main-tained below the flammability limits of hydrogen and oxygon.

Maintaining the concentration of hydrogen and oxygen below their flammability limits provides assurance that the-releases of radioactive materials will be controlled in conformance with the requirements of General Design Criterion 60 of Appendix A to 10 CFR Part 50.

3/4.11.2.6 GAS STORAGE TANKS

'The tanks included in this specification are those tanks for which the quantity of radioactivity contained is not limited directly or indirectly by another Technical Specification.

Restricting the quantity of radioactivity

+

contained _in each gas storage tank provides assurance that in the event of an uncontrolled release of the tank's contents, the resulting whole body exposure to a MEMBER OF THE PUBLIC at the nearest SITE BOUNDARY will not exceed 0.5 rem.

This is consistent with Standard Review Plan 11.3, Branch Technical Position-ETSB 11-5, " Postulated Radioactive Releases Due to a Waste Gas System Leak or Failure," in NUREG-0B00, July 1981.

3/4.11.3 Deleted 3/4.11.4 Deleted DIABLO CANYON - UNITS 1 & 2 8 3/4 11-1 Amendment Nos. 67 and 66

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i B 3/4.12 Deleted in its entirety.

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03/4 12 1 Amendment Nos.67 and 66

"\\ y A:v;M51ctilv[_ CONTROLS tR::[0Ut!$_ANOPROGRAMS(Continued) c.

Se:ondsey Water Cheetstry A program for monitoring of secondary water chemistry to inhibit steam generator tube degradation.

This program shall include:

1)

Identification of a sampling schedule for the critical variables and control points for these verlebles, 2)

Identification of the procedures used to measure the values of the critical variables, 3)

Identification of process sampling points, including monitoring the discharge of the condensate pumps for evidence of condenser in'10akapt, 4)

Frotecures for the recording and annagement of data, E)

Procedures defining corrective actions for all off control point chemistry fonditions, and

()

A procedure identifying:

(a) the authority responsibit for the interpretation of the cata, and (b) the sequence and timing of actinistrative events regwired to initiate corrective action, c.

[tj6voPethodforDetterininc$vbcoolinoMargin A program which will ensure the capability to accurately monitor the Reactor Coolant System subcooling margin.

This program shall in:1ude the following:

1)

Training of personnel, and 2)

Procedures for monitoring, e.

Postaccident $amplino A program which will ensure the capability to obtain and analyte reactor coolant, radioactive iodines and particulates in plant gaseous ef fluents, and contair. ment atmosphere samples under accident conditions.

The program shall include the following:

-1) training of personnel, Procedures for sampling and analysis, and Provisions for maintenance of sampling and analysis equipment.

DIABLO CANYON UNIT $ 1 & 2 6 15

gMINISTRATIVECONTROLS

_ PROCEDURES AND PROGRAMS (Continued) f.

Containment Polar and Turbine _Buildino Cranes A program which will ensure that:

1)thepositionofthecontain-mentpolarcranesprecludesjetimpingementfromapostulatedpipe rupture;and2)theoperationoftheturbinebuildingcranesis consistent with the restrictions associated with the current Hosgri seismic analysis of the turbine building.

This program shall include the following:

1)

Training of personnel, and 2)

Procedures for the containment polar and turbine building cranes operation, g.

Radioactive Effluent Controls Proaram A program shall be provided conforming with 10 CFR 50.36a for the control of radioactive effluents and for maintaining the doses to HEMBERS OF THE PUBLIC (1 0m radioactive effluents as low as reasonsbly achievable.

The program (1) shall be contained in the RMCP

2) shall be implemented by operating arocedures, and (3) shall(includeremedialactionstobetakenwienevertheprogram t

limits are exceeded.

The program shall include the following elements:

1)

Limitations on the operability of radioactive liquid and o

gaseous monitoring instrumentation including surveillance requirements and setpoint determination in accordance with the met!odology in the ODCP, 2)

Limitations on the concentrations of radioactive material released in liquid effluents to UNRESTRICTED AREA conforming to 10 CFR Part 20, Appendix B, Table II, Column 2, 3)

Honitoring, sampling, and analysis of radioactive liquid and gaseous effluents in accordance with 10 CFR 20.106 and with the methodology and parameters in the ODCP.

P

% 'tations on the annual and quarterly doses or dose c& itment to a MEMBER OF THE PUBLIC from radioactive materials it iquid effluents released from each unit to UNRESTRICTED C A conforming to Appendix ! to 10 CFR Part 50, 5)

De'.erminationofcumulativeandprojecteddosecontributions frts radioactive effluents for the current calendar quarter and cuirent calendar year in accordance with the methodology and par ameters in the ODCP at least every 31 days, DIABLO CANYON - UNITS A & 2 6-15a Amendment Nos.2J and 20, 67 and 66

ADMINISTRATIVE CONTROLS PROCEDURES AND PROGRAMS (Continued) 6)

Limitations on the operability and use of the liquid and gaseous effluent treatment systems to ensure that the appropriate portions of these systems are used to reduce releases of radioactivity when the projected doses in a 31 day period would exceed 2 percent of the guidelines for the annual dose or dose commitment conforming to Appendix 1 to 10 CFR Part 50, 7)

Limitations on the dose rate resulting from radioactive material released in gaseous effluents to area beyond the Si1E BOUNDARY cohforming to the doses associated with 10 CFR Part 20, Appendix B, Table II, Column 1,

(

8)

Limitations on the annual and quarterly air dosts resulting from noble gases released in gaseous effluents from each unit to areas beyond the SITE BOUNDARY conforming to Appendix 1 to 10 CFR part 50, 9)

Limitations on the annual and quarterly doses to MEMBERS OF THE PUBLIC from lodine-131, lodine-133, tritium, and all radionuclides in particulate form with half-lives greater than 8 days in gaseous effluents released from each unit to areas beyond the SITE BOUNDARY conforming to Appendix 1 to 10 CFR Part 50, and 10)

Limitations on the annual dose or dose commitment to any MEMBER Of THE PUBLIC due to releases of radioactivity and to radiation from uranium fuel cycle sources conforming to 40 CFR Part 190.

h.

R,adiological Environmental Monitoring Program A program shall be provided to monitor the radiation and radionuclides in the environs of the plant.

The program shall provide (1) representative measurements of radioactivity in the highest potential exposure pathways, and (2) verification of the accuracy of the effluent monitoring program and modeling of environmental exposure pathways.

The program shall (1) be contained in the RMCP, (2) conform to the guidance of Appendix I to 10 CFR Part 50, and (3) include the following:

1)

Monitoring, sampling, analysis, and reporting of radiation and radionuclides in the environment in accordance with the methodology and parameters in the ERMP, 2)

A Land Use Census to ensure that changes in the use of areas at and beyond the SITE BOUNDARY are identified and that modifications to the monitoring program are made if required by the results of this census, and 3)

Participation in a Interlaboratory Comparison Program to ensure that independent checks on the precision and accuracy of the measurements of radioactive materials in the environmental sample matrices are performed as part of the quality assurance program for environmental monitoring.

DIABLO CANYON - UNITS 1 & 2 6-15b Amendment Nos.67 and 66

{

i AM' N!$iRATIVECONTR0($

i

(.9 REFORTING RE0VIREMINTS ROUT:NE REPORTS, i

6.9.1 In addition to the applicable reporting requirements of Title 10. Code of Federal Regulations,$0.4the following reports shall be submitted to the NRC in accordance with 10 CFR STARTUP RFPORTS 6.9.1.1 A sumary report of plant startup and power escalation testing shall be submitted following (1)receiptofanoperatinglicense (2) amendment to the license involving a planned increase in power level. (3). installation of fuel that has a different design or has been manufactured by a different fuel supplier, and (4) modifications that may have significantly altered the nuclear, thermal, or hydraulic perfomance of the plant.

6.9.1.2 The initial Startup Report shall address each of the startup tests identifiec in Chapter 14 of the TSAR and shall include a description of the measured values of the operating conditions or characteristics obtained during the test program and a comparison of these values with design predictions and specifications. Any ce"rective actions that were required to obtain satisfac-tory operation shall also b; described. Any additional specific details required in license conditions based on other comitments shall be included in this report. Subsequent Startup Reports shall address startup tests that are necessary to demonstrate acceptability of the change and/or modification.

6.9.1.3 Startup Reports shall be submitted within:

(1)90daysfollowing completion of the startup test program, ion, or (3) 9 months following initial (2) 90 days following resumption or commencement of commercial power operat criticality whichever is earliest.

If the Startup Report does not cover all three events (i.e.

initial criticality completion of Startu and resumption or c,omencement of comer,cial power operation)p Test Program, supslementary i

reports shall be submitted at least every three montas until a,ll tarte events have been completed.

ANNUAL REPORTS

• 6.9.1.4 Annual Reports covering the activities of the unit as described below during the previous calendar year shall be submitted prior to March 31 of'each year. The initial report shall be submitted prior to March 31 of the year following initial criticality.

Reports required on an annual basis shall include a tabulation on an annual basis.cf the number of station, utility and other-personnel (including contrac-tors) receiving exposures greater than 100 arem/yr and their associated man

'A single submittal may be made for a multiple unit plant. The submittal

.thould combine those sections that are comon to all units at the plant.

DIABLO CANYON - UNITS 1 1 2-6 16 Amendment Nos. 43 and 42 411. I 9 1989

ADMINISTRATIVE _ CONTROLS l

ANNUAL rep 0RTS (Continued) remexposureaccordingtoworkandjobfunctions*e.g.,reactoroperations and surveillance, inservice inspection, routine maintenance, special maintenance (describe maintenant:e), waste processing, and refueling.

The dose assignment to various duty functions may be estimates based on pocket dosimeter, TLD, m film badge measurements.

Small exposures totalling less than 20% of the individual total dose need not be accounted for.

In the aggregate, at least 80% of the total whole body dose received from external sources shall be assigned to specific major work functions.

The results of specific activity analysis in which the primary coolant exceeded the limits of Specification 3.4.8 will be included in the annual report.

The following information shall be included:

(1) reactor power history starting 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> prior to the first sample in which the limit was exceeded; (2) results of the last isotopic analysis for radioiodine performed

-prior to exceeding the limit, results of analysis while limit was exceeded and results of one analysis after the radiciodine activity was reduced to less than limit.

Each result should include date and time of sampling and the radiciodine concentrations priortothefirstsamplel'n(whichthelimitwasexceeded;(4)graphofthe3) clean-up syste I-131 concentration and one other radiciodine isotope concentration in microcuries per gram as a function of time for the duration of specific activity above the steady state level; and (5) the time duration when the specific activity of the primary coolant exceeded the radioiodine limit.

ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT **

6.9.1.5 The Annual Radiological Environmental Operating Report covering the operation of the unit during the previous calendar year shall be submitted before May 1 of each year.

The report shall include summaries, interpretations, and analysis of trends of the results of the Radiological Environmental Monitoring Program for the reporting period.

The material provided shall be consistent with the objectives outlined in (1) the RMCP and (2) Sections IV.B.2, IV.B.3, and IV.C of Appendix ! to 10 CFR Part 50.

"This tabulation supplements the requirements of 10 CFR 20.407.

• • A single submittal may be made for a multiple unit plant.

DIABLO CANYON - UNITS 1 & 2 6-17 Amendment Nos. 67 and 66

ADMINISTRATIVE CONTROLS SEM1 ANNUAL RADI0 ACTIVE EFFLUENT RELEASE REPORT

• 6.9.1.6 The Semiannual Radioactive Effluent Release Report covering the operation of the unit during the previous 6 months of operation shall be submitted within 60 days af ter January 1 and July 1 of each year.

The report shall include a summsry of the quantities of radioactive liquid and gaseous effluents and solid waste released from the unit.

The material provided shall be (1) consistent with the objectives outlined in the RMCP and PCP, (2) in conformance with 10 CFR 50.36a and Section IV.B.1 Appendix i to 10 CFR Part 50.

l MONTHLY OPERATING REPORT 6.9.1.7 Routine reports of operating statistics and shutdown experience, including documentation of all challenges and failures to the PORVs or safety valves, shall be submitted on a monthly basis to the NRC in accordance with 10 CFR 50.4, no later than the 15th of each month following the calendar month covered by the report.

CORE OPERATING LIMITS REPORT 6.9.1.8.a Core operating limits shall be established and documented in the CORE OPERATING LIMITS REPORT before each reload cycle or any remaining part of a reload cycle for the following:

1. Shutdown Rod Insertion Liniits for Specification 3/4.1.3.5,

2. Control Rod Insertion Limits for Specification 3/4.1.3.6,

3. Axial Flux Difference for Specification 3/4.2.1,

4. Heat Flux Hot Channel Factor - F (z) (Surveillance Requirement W(2) of Specification 3/4.2.2), and 9

5. Heat Flux Hot Channel Factor - F (z) ~(Surveillance Requirement F of Specification 3/4.2.2.2).

N

• Y b.

The analytical methods used to determine the core operating limits shall be those previously reviewed and approved by the NRC in:-

1.

WCAP-10216-P-A,-Relaxation of Constant Axial Offset Control Fq Surveillance Technical Specification, June 1983 (Westinghouse Proprietary),

2, WCAP-9272-P-A, Westinghouse Reload Safety Evaluation Methodology, July 1985 (Westinghouse Proprietary), and

• A single submittal may be made for a multiple unit plant.

The submittal should combine those sections that are common to all units at the plant; however, for units with separate radwaste systems, the submittal shall specify the releases of radioactive material from each unit.

DIABLO CANYON - UNils 1 & 2 6-18 Amendment Nos.67 and 66

ADMINISTRATIVE CONTROLS 3.

WCAP-8385, Power Distribution Control :>nd Load following Procedures, September 1974 (Westingh0use Proprietary).

(

The core operating limits shall be determined 50 that all applicable c.

limits (e.g., fuel thermal-mechanical limits, core thermal

• hydraulic limits, ECCS limits, nuclear limits such as SHU1DOWN MARGIN, and transient and accident analysis limits) of the safety analysis are met.

d.

The CORE OPERATING LIMITS REPORT, including any mid-cycle revisions or supplements thereto, shall be provided, upon issuance for each reload cycle, to the NRC Document Control Desk, with copies to the Regional Administrator and Resident Inspector.

SPECIAL REPORTS 67777 Special reports shall be submitted to the NRC in accordance with 10 CFR 50.4 within the time period specified for each report.

6.10 RECORD RETENTION In Addition to the applicable record retention requirements of Title 10, Code of federal Regulations, the following records shall be retained for at least the minimum period indicated.

6.10.1 The following records shall be retained for at least 5 years:

a.

Records and logs of unit operat' covering time interval at each power level; b.

Records ano logs of principal maintenance activities, inspections, repair and replacement of principal items of equipment related to nuclear safety; c.

ALL REPORTABLE EVENTS; DIABLO CANYON - UN1151 & 2 6-19 Amendment Nos. 67 and 66 l

l

ADMikl51RATIVE CONTROLS r

RECORDRETENTION(Continued) e d.

Records of surveillance activities, inspections and calibrations required by these Technical Specifications:

e.

Records of changes made to procedures required by Specification 6.8.1 f.

Records of radioactive shipments g.

Records of sealed source and fissich cetector leak tests and rtsults and j

h.

Records of annual physical inventory of all sealed source material of recoro.

6.10.2 The following records shall be retained for the duration of tlic unit Operating Licenses o.

Records and drawing changes reflecting unit desigr trodifications made to systems and equipment described in the Final Safety Analysis Reports b.

Records of new and irradiated f uel inventory, fuel transfers and assembly burnup histories:

c.

Records of radiation exposure for all inoividuals entering radiation control arcas d.

Records of gaseous and liquid radioactive material released to the environs; e.

Records of transient or operational cycles for those unit components identified in Table 5.7 f.

Records of reactor tests and experiments:

g.

Records of training and qualification f or current members of the s

unit staff; h.

Records of in-service inspections performed pursuant to these Technical Specifications;

-1.

Records of Quality Assurance activities required by the QA Manual J.

Records of reviews performed for changes made to procedura or equip-ment or reviews of tests and experiments pursuant to 10 CFR 50.59:

k.

Records of meetings of the PSRC and NS003

-DIABLO CANYON - UNIT 5 1 & 2 6-20 Amendment Nos.67 and 66 i

ADMiklS1RATIVE CONTROLS RECGRD RETENTION (Continued) 1.

Recordt of analyses required by the Radiological Environmental Monitoring Program; m.

Records of the service lives of all hydraulic and mechanical snubbers required by Specification 3.7.7 including the date at which the service lif comences and associated installation and niair.tenance records; a.,

n.

Recorcs of secondary water sampling and water quality, o.

Recotos of reviews performed for changes made to the RADIOLOGICAL MONITORING AND CONTROLS PROCEAM, OFFSITE 00$E CALCULATION PROCEDURE, ENVIRONMENTAL RADIOLOGICAL MONITORING PROCEDURE, and the PROCES3 CONTROL PROGRAM.

6.11 RADIATION PROTECTION PROGRAM Procedures fcr personnel refiation protection shall be prepared consistent with the requiren.ents of 10 CFR Part 20 and shall be approved, maintained and adhered to for all operations involving personnel radiation exposure.

6.12 HJHRADIATIONAREA 6.12.1-Pursuant to paragraph 20,203(c)(5) of 10 CFR Part 20, in lieu of the

" control device" c. " alarm signal" required b; paragraph 20.203(c)(2) each high radiation area, as defined in 10 CFR Part 20, in which the intensity of radiat.on is equal to or less than 1000 mR/h at 45 cni (18 in.) from the radia-tion source or from any surft:c which the radiation p2tetrates shall be barri-tad 2d and conspicuously posteo as a high radiation area and entrance thereto shall be controlled by requirir.g 1:suance of work permits for radiation (WPR).

Individuals qualified in rediation prutection procedurcs (e.g., Health Physics Technician)-or-personnel continuous 1'

>;ce, ed by such individuals may be exempt-from the WPR issuance requirement du ut,4 performance of their assigrcd duties in_ high radiation areas with exposure : 9-eq a1 to.or less than 1000 mR/h, providea they are otherwise-following piant radiation Protection procedures for entry-into such high radiation areas. Any indivioual or group of indivi-duals permitted to enter such areas shall be provided with or accompanied by one or more of the to11owing a.

A radiation monitoring device whicn continuously indicates the radiation dose rate in the area;.or j

b.

A radietion monitoring device which continuously integrates the rLdietion dose rate in the area and alarms when a preset integrated dose is received.

Entry into such areas with this monitoring device may be mede after the dose rate levels in the area have been estab-lishec and personnel-have been made knowledgeable of them; or DIABLO CANYON - UNITS 1 & 2 6-21 Amendment Nos.67 and 66 3

gDMINISTRATIVECONTROLS HIGH RADIATION AREA (Continued) c.

An individual qualified in radiation protection procedures with a radiation dose rate monitoring device, who is responsible for pro-viding positive control over the activities within the area and shall perform periodic radiation surveillance at the frequency specified by the Radiation Protection Manager in the WPR.

6.12.2 In addition to the requirements of Specification 6.12.1, areas acces-sible to personnel with radiation levels greater than 1000 mR/h at 45 cm (18 in.) from the radiation source or from any surface which the radiation penetrates shall be provided with locked doors to prevent unauthorized entry, anJ the keys shall be maintained under the administrative control of the Shift foreman on duty and/or health physics supervision.

Doors shall remain locked except during periods of access by personnel under an approved WPR which shall specify the dose rate levels in the immediate wnrk areas and the maximum allow-able stay time for individuals in that area.

In lieu of the stay time speci-fication of the WPR, direct or remote (such as closed circuit TV cameras) con-tinuous surveillance may be made by persona-1 qualified in radiation protection procedures to prov:de positive exposure control over the activities being per-formed within the area.

For individual high radiation areas accessible to personnel with radiation levels of oraater than 1000 mR/h that are located within large areas, such as

b PWR tontai e where no enclosure exists for purposes of locking, and where

+

no enclos

< - Da reasonably constructed around the individual area, that hall be barricaded, conspicuously posted, and a flashing light individr

? hall b; t;s +.d as a warning device.

6.13 PROL M Q fROL PROGRAM (PCP) 6.13.1 The PCP shall be apprc d by the Commission prior to implementation.

6.13.2 Changes to the PCP:

a.

Shall be documenced and records of review performed shall be retained e' required by Specification 6.10.2.o.

This documentation shall co" n:

1) nt information to support the change together with the iate analyses or evaluations justifying the chang <(s) and 6.

2)

A Jetermination that the change will maintitin the overall conformance of the solidified waste product to existing requirements of Federal, State, or cther applicable regulations.

b.

Shall become effective after review and acceptance by the PSRC and the approval of the Plant Manager.

DIABLO CANYON - UNITS 1 & 2 6-22 Amendment Nos. 67 and 66 l

m a.

ADMINISTRATIVE-CONTROLS 6.14 RADIOLOGICAL MONITORING AND CONTROLS PROGRAM (RMCP), OFFSITE DOSE CALCULATION PROCEDURE (ODCP) and ENVIRONMENTAL RADIOLOTTC%F H3NITORING PROCEDURE (ERMP) 6.14.1 The RMCP, ODCP and ERMP shall be approved by the Commission prior to implementation.

6.14.2 Changes to the RMCP, ODCP, and ERMP:

a.

Shall be documented and records of reviews performed shall be 4

retained as required by Specification 6.10.2.o.

This dacumentation shall.contain:

1)

Sufficient information to support the chr.nge together with the appropriate analyses or enluations justifying the change (s) and 2)

A determination that the change will maintain the level of

- radioactive effluent control required by 10 CFR 20.106, 40 CFR Part 190, 10 CFR 50.36a, and Appendix I to 10 CFR Part 50 and not adversely impact the accuracy or reliability of effluent, dose, or setpoint calculations, b.

Shall become effective after review and acceptance by the PSRC and the approval of the Plant Manager, c.

Shall be submitted to the Commission in the form of a complete, legible copy of the entire RMCP, ODCP and ERMP as part of or concurrent with the Semiannual Radioactive Effluent Release Report for the period of the report in which any change to the RMCP, ODCP or ERMP was made.

Each change shall be identified by markings in the margin of the affected pages, clearly indicating the area of the page that was changed, and shall indicate the date (e.g.,

month / year) the change was implemented.

DIABLO CANYON - UNITS 1 & 2 6-23 Amendment Nos. 67 and 66