ML13312A862

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Rev 0 to Surveillance Operating Instruction SO23-3-3.0, Operations Surveillance Program Requirements. W/Five Oversize Drawings
ML13312A862
Person / Time
Site: San Onofre  Southern California Edison icon.png
Issue date: 01/02/1987
From:
SOUTHERN CALIFORNIA EDISON CO.
To:
Shared Package
ML13303B878 List:
References
SO23-3-3.0, NUDOCS 8801210047
Download: ML13312A862 (32)
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Text

NUCLEAR GENERATION SITE SURVEILLANCE OPERATING INSTRUCTION S023-3-3.0 UNT 2 AN 3

REVTSION 0 oAGE OF EFFECTIVE DATE JAN 0 1987 OPERATIONS SURVEILLANCE PROGRAM REQUIREMENTS TABLE OF CONTENTS SECTION 1.0 OBJECTIVE 2.0 EFERENCES 3.0 PREREQUISITE JAN 02 1987 SITE Fll-r"'

4.0 PRECAUTIONS 6

5.0 CHECKLIST(S) 6 6.0 PROCEDURE 6.1 Surveillance Program Responsibilities 7

6.2 Surveillance Scheduling Guidelines 7

6.3 Surveillance Performance Guidelines 10 6.4 Unsatisfactory Surveillance Actions 12 7.0 RECORDS 13 ATTACHMENTS I

Technical Specifications Surveillance:Requirements 14 2

Technical Specifications Surveillance Control Sheet 32 3

Surveilance Intervals and Notations 33 PDR ADOCK 05000361 P

PDR)

NUCLEAR GENERATION SITE SURVEILLANCE OPERATING INSTRUCTION S023-3-3.0 UNITS 2 AND REVISION 0 PAGE 2 CF 33 OPERATIONS SURVEILLANCE PROGRAM REQUIREMENTS 1.0 OBJECTIVE 1.1 To delineate the responsibilities and requirements of the Operations Department Technical Specifications Surveillance Program as required by SO123-G-3.

2.0 REFERENCES

2.1 Licensino Commitment 2.1.1 Technical Specifications 2.2 Site Order 2.2.1 SO123-G-3, "Technical Specification Surveillance Requirements" 2.3 Procedures 2.3.1 S0123-VI-0.9, "Documents - Author's Guide to the Preparation of Site Orders, Procedures, and Instructions" 2.3.2 S0123-XV-5.0, "Non-conforming Materials, Parts, or Components" 2.3.3 S023-V-3.5.0, "In-service Testing of Valves Program" 2.3.4 S023-XV-3.0, "Technical Specification Surveillance Program Implementation" 2.3.5 S023-XV-3.1, "Technical Specification Surveillance Requirements for Change in Operating Mode" 2.4 Operating Instructions 2.4.1 S0123-0-13, "Technical Specification LCO Action lRequireinents (LCOAR) and Equiment.

Deficiency Mode Restraints (EDMR) 2.4.2 S0123-0-20, Use ofProcedures" (when issued) 2.4.3 S0123-0-21, "Equipment Status Control" 2.4.4 S0123-0-23 "Contr of System Aignments" (when-ssed 0

-o Al i

2 ed)

NUCLEAR GENERATION SITE SURVEILLANCE OPERATING INSTRUCTION S023-3-3.0 UNITS 2 AND 3 REVISIDN 0 PAGE S CF 33

2.0 REFERENCES

(Continued) 2.4.5 S0123-0-32, "Operations Records and Transmittal" (when issued) 2.4.6 S0123-0-42, "Cumulative Equipment Hours, Inoperability, and Design Cycles" 2.4.7 S023-0-28, "Operating Records" 2.4.8 S023-0-35, "Use of Procedures" 2.4.9 S023-0-36, "Control of System Alignments" 2.4.10 S023-1-4.2, "Containment Purge and.Recirculation Filtration System" 2.4.11 S023-3-1.1, "Reactor Startup" 2.4.12 S023-3-1.2, "Reactor Shutdown" 2.4.13 5023-3-2.9, "Containment Spray/Iodine Removal System Operation" 2.4.14 5023-3-2.19.1, "CEDM MG Set Operation" 2.4.15 S023-3-3.1, "Boric Acid Flow Path Testing" 2.4.16 5023-3-3.2, "Excore Nuclear Instrumentation Calibration" 2.4.17 S02(3)-3-3.3, "RCS Flow Rate Determination - Unit 2(3)"

2.4.18 S023-3-3.4, "Radwaste Quarterly.Surveillance" 2.4.19 5023-3-3.5, "CEA Monthly Operability Test" 2.4.20 S023-3-3.6, "COLSS Out Of Service Surveillance" 2.4.21 S023-3-3.7, "Radiation Monitoring System Tests (PERMS)"

2.4.22 S023-3-3 8, "Safety Injection tMonthly Tests" 2.4.23 S023-3-3.10, "Containment Integrity Verification" 2.4.24 S023-3-3.10.1, "Containment Airlock Integrity Verification" 2.4.25 S023-3 -3.11, Containment Spray and Iodine iemovaI System Monthly est" 2.4.26 S023-3-3.11.2- "Containment Spray System Refueling Test"

NUCLEAR GENERATION SITE SURVEILLANCE OPERATING INSTRUCTION S023-3-3.0 UNIT_ 2 AND 3 REV SION 0 PAGE 4 O 3

2.0 REFERENCES

(Continued) 2.4.27 S02(3)-3-3.21.3, "Spray Chemical Addition Pump Flow Test -

Unit 2(3)"

2.4.28 S023-3-3.12, "Integrated ESF System Refueling Test" 2.4.29 S02(3)-3-3.13, "Containment Cooling Monthly Test Unit 2(3)"

2.4.30 5023-3-3.16, "Auxiliary Feedwater System Monthly Tests" 2.4.31 S023-3-3.16.2, "Auxiliary Feedwater Flow Test" 2.4.32 S02(3)-3-3.17, "Main Steam Isolation Valve Operability Test -

Unit 2(3)"

2.4.33 5023-3-3.18, "Component Cooling/Saltwater System Monthly Test" 2.4.34 S023-3-3.19, "4kV Emergency Bus Transfer Test" 2.4.35 S023-3-3.20, "Monthly Control Room Emergency Air Cleanup System Test" 2.4.36 S023-3-3.20.1, "Control Room.Emergency Air Cleanup System

.18-Month Surveillance" 2.4.37 S023-3-3.21, "Radiation.Monitoring Shiftly Surveillance" 2.4.38 5023-3-3.21.1, "Radiation Monitoring Daily Surveillance" 2.4.39 S023-3-3.23, "Diesel Generator Monthly Test" 2.4.40 S23-3-3.23.1, "Diesel Generator Refueling Interval Tests".

2.4.41 5023-3-3.24, "Monthly Fuel Handling Building Post-Accident Air Cleanup System-Test" Idng ergency 2.4.42

-S023-3-3.24.1, "Fuel Handling Building Emergency.

.Ventilation System 8-Month Surveillance 2.4.43 5023-3-3..25, "Once-A-Shift Surveillance (Modes 1-4)"

2.4.44 5023-3-3.25.1 "Once-A-Shift Surveillance (Modes 5-6)"

2.4.45 7.'S023-3-3.26, "Once A Day urveilla e (Mod 2.4.46

-"5023-3-3.26.1, "Once A Day Surveillante (Modes 5-6)"

NUCLEAR GENERATION SITE SURVEILLANCE OPERATING INSTRUCTION S023-3-3.0 UNIFS 2 AND 5 REVISION 0 PAGE 5 OF 3

2.0 REFERENCES

(Continued) 2.4.47 S023-3-3.27, "Once A Week Surveillances (Modes 1-4)"

2.4.48 S023-3-3.27.1, "Once A Week Surveillances (Modes 5-6)"

2.4.49 S023-3-3.27.2, "Weekly Electrical Bus Surveillance" 2.4.50 S023-3-3.27.3, "Once A Week Surveillances (Common)"

2.4.51 S023-3-3.28, "Remote Shutdown Panel Instrumentation Monthly Checks" 2.4.52 S023-3-3.29, "Determination of Reactor Shutdown Margin" 2.4.53 S023-3-3.30, "In-service Valve Testing, Quarterly" 2.4.54 S023-3-3.31, "In-service Valve Testing - Cold Shutdown" 2.4.55 5023-3-3.31.1. "RCS Pressure Isolation Valve Leak Rate Measurement" 2.4.56 S023-3.3.31.2, "In-service Testing of Check Valves (Cold Shutdown Frequency)"

2.4.57 S023-3-3.33, "Containment Purge Isolation System Test" 2.4.58 5023-3-3.34, "Turbine Overspeed Protection Valve Operability Tests" 2.4.59 S02(3)-3-3.35, "Post-Accident Monitoring Instrumentation Monthly Checks" 2.4.60 5023-3-3.36, "Fire Suppression System Monthly Tests" 2.4.61 S023-3-3.36.1, "Fire Suppression System Annual Test" 2.4.62 5023-3-3.36.2, "Fire.Suppression Water System 18 Month Tests" 2.4.63 S023-3-3.36.3, "Fire Suppression System Tri-Annual Flush" 2.4.64 S023-3-3.37, "Reactor Coolant System Water Inventory Balance" 2.4.65 S02(3)-3-3.38, "Reactor Power Calculation (Manual Method)

- Uit 2(3)"

2.4.66 S023-3-3.40, "Ca lculation of CPC Flow Coefficients" 2.4.67 5023-3-3.42, "Hydrogen Recombiner Operability 0.Check

- Semiannual"

NUCLEAR GENERATION SITE SURVEILLANCE OPERATING INSTRUCT TON S023-3-3.0 U:NITS 2 A N 3 REVISION 0 PAGE 6 OF

2.0 REFERENCES

(Continued) 2.4.68 S02(3)-3-3.43, "Semiannual ESF Subgroup Relay Test" 2.4.69 S023-3-3.44, "Containment Loose Debris Inspection" 2.4.70 5023-3-3.45, "Control Room Indication Status Check" 2.4.71 S023-3-3.47, "Emergency Chilled Water System Monthly Test" 2.4.72 5023-5-1.3. "Plant Startup From Cold Shutdown To Hot Standby" 2.4.73 S023-5-1.3.1, "Plant Startup From Hot Standby To Minimum Load" 2.4.74 S023-5-1.4, "Plant Shutdown To Hot Standby" 2.4.75 S023-5-1.5. "Plant Shutdown From Hot Standby To Cold Shutdown' 2.4.76 S023-5-1.8, "Shutdown Operations (Mode 5 and 6)"

2.4.77 5023-8-7,. "Liquid Radioactive Waste Discharge Operations" 2.4.78 S023-8-15, "Radwaste Gas Discharge" 2.4.79 S023-13-3, "Earthquake" 3.0 PREREQUISITE 3.1 Prior to use of an uncontrolled (pink) copy of this Site Document to perform.work, verify that it is current by checking a controlled copy and any TCNs or by use of the method described in S0123-VI-0.9.

4.0 PRECAUTIONS 4.1 Failure to perform a Tech. Spec. surveillance within the specified time interval shall constitute a failure to meet the operability requirements of the LimitihgCondition' forOperation (LCO).

(Ref.

2.1.1, 4.0.3) 4.2 Entry into an operational mode or applicable condition as specified by'a Tech.' Sec. LCO shal 1not be made until the required associated surveillances have been successfully coplete d. Re

.1, 40.)

5 0. CHECKLIST(S) 5.1 None.

NUCLEAR GENERATION SITE SURVEILLANCE OPERATING INSTRUCTION S023-3-3.0 UN TS 2 ANiD 3 REVISION 0 7

6.0 PROCEDURE 6.1 Surveillance Program Responsibilities 6.1.1 The Plant Superintendent has the overall responsibility for the Operations Department Technical Specifications Surveillance Program (TSSP).

6.1.2 The Supervisor of Plant Coordination is responsible ensuring proper implementation of the TSSP and approving the daily Tech.

Spec. Surveillance Control Sheets.

6.1.3 The Surveillance Coordinator is responsible for generating the daily Tech. Spec. Surveillance Control Sheets for the operating shifts, producing the Surveillance Report for the cognizant Equipment Control and Operations Supervisors, and auditing completed surveillance documents for deficiencies.

6.1.4 The SRO Ops.-Supervisor is responsible for authorizing the performance of Surveillance Operating Instructions (SOIs) [except shiftly, daily and weekly SOIs],

reviewing the completeness, accuracy, and results of SOIs, taking action to maintain/restore equipment operability, reporting schedule deviations.to the Surveillance Coordinator, reporting unsatisfactory SOI results to the Shift Superintendent, and initiating a LCOAR/EDMR, as applicable.

6.1.5 The Control Operator is responsible for completing the scheduled SOIs and informing the SRO Ops. Supervisor of deficiencies/difficulties encountered.

6.1.6 The Supervisor of Operations Procedures is responsible for ensuring the SOIs conform to the latest Technical Specification requirements/amendments.

6.2 Surveillance Scheduling Guidelines NOTES: 1. The Operations designated surveillances in SO23-XV-3.0 are cross-referenced to specific Surveillance Operating Instructions in Attachment 1.

2. Surveillance intervals and notations are described in.
3. There is no requirement to perform surveillances on inoperable equipment. (Ref. 2.1.1 403) 6.2.1 Surveillance requirements shall be applicable during the operational modes and conditions specified In the LCOs.

(Ref. 2.1.1, 4.0.1)

NUCLEAR GENERATION SITE SURVEILLANCE OPERATING INSTRUCTION S023-3-3.0 UNITS 2 AND 3 REVISION v FAGE F

6.0 PROCEDURE (Continued)

CAUTION Failure to perform a Tech. Spec. surveillance within the specified time interval shall constitute a failure to meet the operability requirements of the Limiting Conditions for Operation (LCO).

(Ref. 2.1.1, 4.0.3) 6.2.2 Each surveillance requirement shall be performed within the specified time interval with a maximum extension not to exceed 25% of the surveillance interval, and the combined time interval for any three consecutive surveillance intervals not to exceed 3.25 times the specified time interval.

(Ref. 2.1.1, 4.0.2) 6.2.3 For conservatism and simplification the Operations surveillance schedule is based on a month containing exactly 28 days or 4 week cycles. (In effect this creates 13 months per year.)

.1 Surveillances on redundant equipment required to be tested on a staggered basis are scheduled on different week cycles (i.e., a monthly surveillance on Train B would normally be performed two week cycles later than Train A).

.2 Any extensions allowed by step 6.2.2 are based on the Tech. Spec. interval rather than the actual scheduling frequency.

6.2.4 The computerized Operations Surveillance Tracking and Scheduling Program (OSTSP) generates the daily Tech.

Spec. Surveillance Control Sheet (TSSCS) which is facsimiled as Attachment 2.

.1 The TSSCS contains all of the shiftly and daily surveillances. In addition, it contains all of the longer interval surveillances from Attachment 1, which currently need to be performed.

.2 During Refueling Outages, the TSSCS contains the additional surveillances required to be performed on an 18 month or refueling interval.

NUCLEAR GENERATION SITE SURVEILLANCE OPERATING INSTRUCTION S023-3-3.0 UN:%S 2 AND 3 REVISIONr 0

C.G 9

7 6.0 ROCEDURE (Continued) 6.2.5 The daily TSSCS will be implemented as follows:

.1 The Surveillance Coordinator reviews the TSSCS and consults with the Equipment Control Coordinators to determine if all scheduled surveillances can be performed. Any which cannot be performed are rescheduled within the limits of step 6.2.2.

.2 The final/corrected TSSCS is placed in a red loose-leaf binder (Rec Dook) and submitted t; the Supervisor of Plant Coordination (or his designee) for approval.

(There is a separate Red Book for each Control Room station:

Unit 2, Unit 3, and Common.)

.3 After approval, the Red Books are delivered to the Control Room by the Surveillance Coordinator (for use commencing at midnight).

.4 The SRO Ops. Supv. on duty at midnight will reschedule (as necessary) any uncompleted surveillances from the previous day's TSSCS to the current TSSCS, and review the violation Date/Time to ensure sufficient extension time is'available to complete the surveillance requirement.

.5 All required surveillances.are performed in accordance with Section 6.3 and completed documents are placed in the Red Books.

.6 After the Red Books have been used for the applicable day, they are retrieved by the Surveillance Coordinator.

.7 The Surveillance Coordinator updates the OSTSP then generates the computerized Surveillance Report.

.8 For planning purposes, the Surveillance Report is periodically distributed to the Supervisor of Plant Coordination, Equipment Control Supervisors, and the Control Room Supervisors.

CAUTION Entry into an operational mode or condition specified by a Tech. Spec. LCO shall not be made until the required associated surveillances have been successfully completed. -(Ref. 2.1.1, 4.0.4)

NUCLEAR GENERATION SITE SURVEILLANCE OPERATING INSTRUCTION S023-3-3.0 UNITS 2 AJD 3 REVISION J PA..E I0 r r 6.0 PROCEDURE (Continued) 6.2.6 The surveillance requirements necessary to change operational modes or conditions as required by 5023-XV-3.1 are delineated in the respective Integrated Operating Instructions (S023-5-1.3, S023-5-1.3.1, S023-5-1.4, S023-5-1.5, and S023-5-1.8.)

.1 Surveillances required by t~he Integrated Operating Instructions are augmented by the Red Book as described in step 6.2.5.

6.3 Surveillance Performance Guidelines 6.3.1 Surveillance Operating Instructions (SOI) will be approved for use by the cognizant on-shift SRO Ops.

Supv.

This final approval takes into account current plant status and equipment operability. It ensures that performing the SOI will not violate the associated LCOs or place the Unit(s) in an unsafe condition.

.1 SRO Ops. Supv. approval is not required to initiate and complete shiftly, daily, or weekly SOIs.

6.3.2 Performance and documentation of SOIs will meet the requirements of-S023-0-35 (S0123-0-20 when issued).

CAUTION Failure to perform a Tech. Spec. surveillance within. the specified time. interval shall constitute a failure to meet the operability requirements of the Limiting Conditions for Operation (LCO).

(Ref. 2 1 1 4.0.3) 6.3.3 Surveillances shall be performed in the specified modes and within the specified time frames.

any t of asurve 1

nge ust be-complete u e

the spectfied time frame then an diate notificat on of the SRO Ops. Supv. is required.

In addition, this fact should be documented in the SOl Comments section with the reason and time the surveillance was completed

NUCLEAF GENERATION SITE SURVEILLANCE OPERATING INSTRUCTION S023-3-3.0 LN TS 2 tND 3 REVISION 0 PAGE 11 CE 6.0 OCEDURE (Continued)

CAUTION Entry into an operational mode or condition specified by a Tech. Spec. LCO shall not be made until the required associated surveillances have been successfully completed.

(Ref. 2.1.1, 4.0.4) 6.3.4 For surveillances performed in more than one mode (i.e., S023-3-3.25), plant status mode changes will be documented in the Comments section with the time that the mode change occurred.

6.3.5 For surveillances performed in more than one mode (i.e., S023-3-3.25), readings shall be recorded for all equipment and/or instrumentation in service that is required for the applicable mode.

6.3.6 If any displayed parameter is invalid due to a test or maintenance in progress, then the SRO Ops. Supv. will be immediately notified, and the circumstances documented in the Comments section.

6.3.7 If any displayed parameter is invalid or out-of-tolerance, then the SRO Ops. Supv. will be immediately notified, the value recorded, and the appropriate action taken (as specified in the SOI and/or Section 6.4).

6.3.8 Surveillances which verify system alignments require only a single check of component position.

.1 If components are found.to be out of the required position, then the actions of 5023-0-36 (S0123-0-23 when issued), section for Discovery of System Misalignments, must be followed.

6.3.9 All completed SOIs shall be reviewed by the SRO Ops.

Supv. for completeness, accuracy,.and acceptability of the results. (Actions for unsatisfactory surveillance results are delineated in Section 6.4.)

.1 Completed SOIs will be placed in the Red Book along.

with the updated TSSCS for subsequent retrieval by the Surveil lance Coordinator.

6.3.10 The Surveillance Coordinator will audit completed SOIs for deficiencies prior to filing in Equipment Control.

NUCLEAR GENERATION S'TE SURVEILLANCE OPERATING INSTRUCTION S0?3-3-3.0 JNITS 2 AND 3 RE"'ISION 0 PAGE 12 O 6.0 TOCEDURE (Continued) 6.4 Unsatisfactory Surveillance Actions CAUTION Failure to perform a Tech. Spec. surveillance within the specified time interval shall constitute a failure to meet the operability requirements of the Limiting Conditions for Operation (LCO).

(Ref. 2.1.1, 4.0.3)

CAUTION Entry into an operational mode or condition specified by

-= =

a Tech. Spec. LCO shall not be made until the required associated surveillances have been successfully completed. (Ref. 2.1.1, 4.0.4) 6.4.1 The SRO Ops. Supv. must be immediately notified when surveillance acceptance criteria results are unsatisfactory.

6.4.2 The SRO Ops. Supv. is responsible for reviewing the affected Tech. Spec. LCO, declaring equipment inoperable, and initiating a LCOAR/EDMR per S0123-0-13.

.1 All reporting requirements are addressed by S0123-0-13.

.2 The LCOAR/EDMR will be referenced in the Comments section of the SOI,.

6.4.3 The SRO Ops. Supv. will ensure Maintenance Orders are initiated per S0123-0-21.as required to restore operability.

6.4.4 Unsatisfactory surveillances and action taken should be documented in the appropriate Control Operator's Log.

6.4.5 After the deficiency,' has been corrected, a retest of the affected components shall be performed by completing the associated steps in the SOI under the same conditions as the initial test. The, combined initial test and retest constitute a single sur eillance.

.1 The SRO Ops.- Supv. may direct'a partial or total retest, depending upon thecIrcumitances.

NUCLEAR GENERATION SITE SURVEILLANCE OPERATING INSTRUCTION S023-3-3.0 UNITS 2 AND 3 R VISIGN 0

'? 13 03 6.0 PROCEDURE (Continued) 6.4.6 After completing a satisfactory retest, the LCOAR/EDMR will be closed out and the equipment declared operable.

.1 If a Non-Conformance Report (NCR) was generated on the affected equipment, then prior to declaring the equipment operable the NCR must be closed, or the reouirements of S0123-XV-5.0, section for Closing NCRs and Returning Equipment/Systems to an Operable Condition, must be followed.

6.4.7 The Surveillance.Coordinator will update the Surveillance Report to reflect the satisfactory surveillance results.

7.0 RECORDS 7.1 After deficiencies are resolved, the SOIs will be filed in the Tech. Spec. Surveillance File located in Equipment Control per 5023-0-28 (S0123-0-32 when issued).

7.2 Completed 50Is will be periodically transferred to CDM, however the most recent three (3) SOIs should remain on file to assist in implementing the surveillance program. In the case of shiftly, daily, and weekly SOIs, the most recent 30 day period should be kept on file.

DKauppinen:3045g

J0 NUCLEAR GENERATION SITE SURVEILLANCE OPERATING INSIRUCTION S023-3-3.0 UNITS 2 AND 3 RIVISION 0 PAGE 14 OF 33 ATTACHMENT 1 TECHNICAL SPECIFICATIONS SURVEILLANCE REqUIREMENIS NOTE:

Intervals are defined in Attachment 3.

CC -

Channel Check CCR -

Channel Calibration SC -

Source Check CF1 -

Channel Functional Test TECH. SPEC.

SURVEILLANCE REQUIREMENT SECTION MODE INTFRVAL NOHE PROCEDURE Shutdown Margin -

Tavg > 2000 F 4.1.1.1.1.a 1,2,3,11 S

(1)

S()23-3-3.29 Shutdown Margin -

.Tavg > 2000 F 4.1.1.1.1.b 1,2 S

Sn23-3-3.25. 3-3.29 Shutdown Margin - Tavg > 200 0 F 4.1.1.1.1.c 2

S/U 823-3-1.1 Shutdown MargIn Tavg > 2000 F 4.1.1.1.1.e 3,4

. D S023-3-3.26, 3-3.29 Shutdown Margin Tavg < 200 0 F

.4.1.1.2.a 5

S (1)

S023-3-3.29 Shutdown Margin - Tavg < 2000F 4.1.1.2.b 5

D S023-3-3.26.1, 3-3.29 MInImumTemperature foar CritIcalIIty 4.1.1.4.a 1,2 S/1J (2)

S03-3-1.1 Minimum Temperature for Criticality 4.1.1.4.b 1,2 S/1J (2)

S023-5-1.3.1, 5-1.4, 3-1.2 Boron injection Flowpaths 4.1.2.1.b 5,6 M

S023-3-3.1 Boron I ectIon F" Iwpths 4.1.2.2.b.

1,2.3,4 M

S023-3-3.1 Boron Injection Flowpaths 4.1.2.2.c 1,2,3,I R

5023-3-3.43, 3-3.12 BoratedWater Source, 4.1.2.7.a.2 5,6 W

S023-3-3.27.1 Borated'yater Source.

4.1.2.7.b 5,6.

D SO;3-3-3.26.1 Borated Water Source.,

4.1.2.8.a.2 1,2,3,4 W

S023-3-3.27 Borated ater Source 1.2.8.b 1,2,3,1 D

5023-3-3.26 (1) WIthi r ore hour fte detectIon. of an inoperable CEA(s) and at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> thereafer while the CEA()

inoperable.

(2)

At leas onceper 30 minutes when the Reactor is critical and RCS Tavq is

<535 0 F and within 11, minuite prior to achieving Reactor critica ity.

AlI ACIIMENT 1

PA;1 O

NUCLEAR GENERAT ON SI SURVEILLANCE OPERATING INSTRUCTION S023-3-3.0 UNITS 2 AND 3 REVISION 0 PAGEI 15 OF 33

. AT ACHMENT 1 TECHNICAL SPECIFICATIONS SURVEILLANCE REQUIREMENTS (Continued)

TECH. SPEC.

SURVEILLANCE REQUIREMENT SECTION MODE INTERVAL NOl PROCEDURE Movable Control-Assemblies 4.1.3.1.1 1,2 S

(3)

S023-3-3.25 MoVable Control Assemblies 4.1.3.1.2 1,2 M

S023-3-3.5 Position dat el 41..2 1,2 S

SO'3-3-3.25 S

d El

.1.3 5 a 1,2 S/U S0,13-3-1.1 Shutdown CLA nserti Lmit 4.1.3.5b 1.2 S

so;3-3-3.25 Reg6lating CEA nsertion Lit

-4.1:3.6 1.2 S

(3)

SO;3-3-3.25 Regulating CEA Insertion Limt 4.1.3.6 1

D3-3-3.26 Part Length CEAInsertion Lim t 4.1.3.7 1,2 5

"3-3-3.25 Linear Hedt, Rate 1 >20%

ContinuOuS SO3-3-3.25 LInear Heat Rate 4.2.1.2 1 >20%

2 Ilv.

COLSS OOS SO'3-3-3.6 Azimuthat Power T it 4.2.3.833.2 Azimutha

'Power Tl t 4.2.3.a 1 >20%

Continuous A 1 >20%

S -

COLSS OOS 5023-3-3.6 DNBR Margin ~ 4 ~4.2.14.2 1 >20%

Cont inuous 35023-3-3.25 DNBRrgi n,:

4.2.14.2 1 >20%

2 HIr.

COLSS OOS SO:13-3-3.6 RCS"' F>20 Cot inu S123-3-3.25, 3-3.3 1, >20%----

S --

OL S-O-S-33-.

C 4.2.6-

~~~1

>20%e'T Continuous~rtur SO0 3 3.2 5 Cor T oolant Teprture 4.2.6 1 >30%

S 023-3-3.25 ASI 4.2.7 1 >20%

S so'3-3-3.25 1,~

S-Se' 3.25 Press rj zewPresu re

.~.

1.2.81 50--.5 (3) TFour hours en one or both CEACs are inoperable, or when the PDIL Auctioneer Alarm Circuit is inperable.

Al ACIIMENI 1

PAnI 2 0 I

NUCLEAR GENERATION SITE SURVEILLANCE OPERATING INSTRUCTION S023-3-3.0 UNITS 2 AND 3 REVISION 0 PAGE 16 OF 33 ATTACHMENT 1 TECHNICAL SPECIFICATIONS SURVEILLANCE REQUIIREMENTS (Continued)

TECH. SPEC.

SURVEILLANCE REQUIREMFNT SECTION MODE INTERVAL NOTE PROCEDURE Reactor Protective, insrumentation 4.3.1.1 (See Below) 1 Manual Reacto0 TrIp A

Table 4.3-1 1,2,3,4,5 R(CFT)

(0) 5023-3-2.19.1 2 Linear Powe e

High Table.3-1.

1,2 D(CCD)

S023-3-3.25, 3-3.2, 3-3.38 A Linear Power eve I High Table

.3-1 1,

S(cc) 3023-3-3.25 3 LoqarIthmic Power Level -

High Table 4.3-1 1.2,3,i S(Cc)

S023-3-3.25 Logarithmic Power Level -

High Tablelt.3-1 5

S(CC)

S023-3-3.25.1 4 Pressurizer-Pressure -

High Table 4.3-1 1,2, S(CC)

SOP3-3-3.25 5 Pressurizer, ressure -

Low Table 4.3-1 1,2.

S(CC)

S023-3-3.25 6 Containment Pressure -

High-Table 4.3-1 1.2 S(CC)

S023-3-3.25

~7 Stea enerorPressure -

Low Table 4.3-1 1.2 S(CC) 5023-3-3.25 8 Steam Generato rLevel Low Table 4.3-1 1,2 S(CC)

S023-3-3.25 9 LocaI Power Density High Table4.3-1 1,2 S(CC)

S023-3-3.25 Loca Power Density High Table

.3-1 1,2.

D(CCO) 5023-3-3.25, 3-3.2, 3-3.38 10 DNBR -

Low Table 4.3-1 1,2 S(CC)

S023 DNBR Low Table

.3-1 1 >70%

S(CCO)

S03-33.25, 3-3.3, fiNIlR -

Low Table 4.3-1 1,2 DCC)3 3-3.38 1 Steam Generator Level-High Tab

.3-1 1,2 S(CC)

SO3-3-3.25

4)

In Modes 3 4-or wIth Reactor Trip Breakers In the Closed position and the CEA Drive Systo.em :n plheIn of CEA wit.IidrwaI A IIA(CIIMFN1 I

PMA(

O 01 ;

NUCLEAR GEN RAT ON S E SURVEILLANCE OPERAT ING INSTRUCTION SO23-3-3.0 UNITS 2 AND 3 REVISION 0 PAGE 17 OF 33 ATTACHMENT 1 TtCHNICAL SPECIFICATIONS SURVEILLANCE REQUIREMENTS (Continued)

TECH. SPEC.

SURVEILLANCE REQU iREMENT SECTION MODE INTERVAL NOTE PROCEDURE Reictor Potective Instrumentation:

4.3.1.1 (See Below)

(Continued)n 14 Cor -Protect o a1cu ators Table 4*3-1 1,2 S(C)

Core Protection Calculators Table 4.3-1 1 >70%

S(CCB) 3-3.40 Core_ P rotect1-a IcuIatos4, Table 4.3-1 1,2 D(CCI) 5023-3-3.25, 3-3.2.

3-3 38

_4 15 CEA CaIcuIats Table 4.3-1 1,2 S(CC) 5023-3-3.25 Table.4.3-1

.1,2 S(CC) 50;3-3-3.25 imTa

.3-1 1,2 S(C(C)

S023-3-3.25 1Table4.3-1 1 >55%

S(cc) 3-3-3.25 ntrumen on 4.315,6 1,2 S

(5) 5023-3-3.25 ESAS instrumentation 4.3.2.1

,(See Below)

.1b ntinent ressure Hih able 4.3-2 1,2,3 S(CC) 5023-3-3.25 pr zer ressure -'Lo Table 4.3-2 1,2,3 S(CC)

S023-3-3.25 dtcuatio LogiTabl 4.3-2

.1,2,3,'

SA(CF)

(13)

SO23-3-3.13, 3-3.12 2 Rsae (Tl 4.3-2 1.2,3 S(CC)

(023-3-3.25 t

.Tabl 4.3-2 12,3 SA(CT)

(13) 023-3-3.13. 3-3.12 Habe 4.3-2 1,2,3 S(CC)

SO23-3-3.25 SA A

aTable 4.3-2 1,2,3,1 SA(CIT)

(13) 5023-3-3.43

5) Operat ons to notify Compute Te hnicians when a High CPC Cabinet al Am comes in.

(1)Relas no e

be durin plnt operation shiall be tested each Cold Shutdown exceeding 2?0 hontr.

ioln; tested 1iuring the:

preoIau six mo ths.

A' IA(CHMENl PS3,

0 of

NUCLEAR GENERATION SITE SURVEILLANCE OPERATING INSTR&ION S023-3-3.0 UNITS 2 AND 3 REVISION 0 PAGE 18 0: 33 Al IACIIMENT 1

TECHNICAL SPECIFICATIONS SURVEILLANCE REQUIREMENTS (Continued)

TECH. SPEC.

SURVEILLANCE REQU REMENT SECTION MODE INTERVAL NOL PROCEDURE ESFAS Instrumentation: (Continued) 4.3.2.1 (See Below)

Stm. Generator Pressure Lo Table 4.3-2 1,2,3 S(CC) 3.25

' c t Ic ActatIon Logic _.

Table 4.3-2 1,2,3 SA(CIT)

(1N3)

S023-3-3.43 cAutomatic-Actuation Logic Table 4.3-2 1,2,3, SA(CFT (1.3) 023-3-3.L3 5Rec ircdlat ion RASi ansT-oiatle

.- 2 1.2,3,4 S(CC-).

03-3-3.25 6cA" in TableCC A32 0233 A omatiCActuation Lo Table 4.3-2 1.2,3,4 SA(CIT)

(1:)

S023-3-3.43 7 LSS f' O~e (LV) able 143-2 1,2,3,li S(CC)

S023-3-3.25

.6 i.n8Eergc ~edae (EFAS),

btoa Gonrietor Level LwTable 14.3-2 23 S()52--35 A team Generator Le e-l Table 4.3-2

)

,.ad No Pressure tow Trip

d. sitomatic ActuatIon ~Logic
  • Table 4.3-2123 SAIT(1)

S33-.4 id, 'Art a I 0213-3-3.25 0tm721,2, 3,'

SA(CF)(1) 503334 9 Control Room isol3 (CRIS) aManua CRIS (Trip Buttons)

Table 4.3-2 N/A R(C)

SO23-3-3.20.1 lkanual SIAS (Trip Buttons)

Table 14.3-2 N/A R(CII)

S023-3-3.12 ArborneRalation Table.

.3-2

,AlI S(CC)

SOP3-3-3.21

1) Particulate/Iodine r..
2)

Gaseous I R6 (13) Relays not testale during plant operation shal be tested each Cold Shutdown exceedin-2.4 ho1 unle; t.st2ed during t2h previous sx mnths

.Ar

AnnMENI 1

.PAnI

'. )f i

NUCLEAR GENERATON STE SURVEILLANCE OPERATING INSTRUCTION S023-3-3.0 UNITS 2 AND 3 REVISION 0 PAGE 19 OF 33 ATTACHMENT 1

?T4 TECHNICAL SPECIFICATIONS SURVEILLANCE REQUIREMENTS (Continued)

TECH 'SPEC.

SURVEILLANCE REQUIREMENT SECTION MODE INTERVAL NO_

PROCEDURE ESF nsrumentatf ln (Cont e3 (See Below)

10 To'xI! Gas ISl tion (TGIS a anual (TripBu ttons)

Table 4A-2 N/A R(CFT)

S023-3-3.20.1

.,.~.

b Chlor~ne

~High Table 4.3-2' Al.

SC) 03332 bChtorine HgA

'Al S(CC)

S03-3-3.21 t~t* -

mmo gh' Table 4.3-2Al d f'~tane/Propane

-High Table 4.3-2

.All S(CC)

S0;'3 3.2 1 71 Fu

%Handlingui Isola t Ion (FHII.S) a ~

-ulTrip Buttons)

Tbe1.-N/R(F)S023-3-3.24i.1 a Han~a 1,1 Table 14.3-2N/

(F b ioeaa

-Table 4.3-2 All S(CC)

(6)

SM23-3-3.21 1)Gaseous 2 Con ePre lolation(PIS) aManualI

(.Trilp Buttons),'

Table:4.3-2 N/A R(C[r S023-3-3.33 b~ibori Raiaio 7.:

.~.,Table

.4.3-1,2,3,1j,6 S(Cc)

S3023-3-3.21 i

Patculate Table '4. 3-2 7

1.2,31, W(C(;)

SO;'3-3-3.27.3 od~~~~A I

e.

8,,,

Table 4.3-2 6

W(CC)

SM-3-3-3.27.3 Containment-' Area Radiatio'-flr- (ama) 'Tab Ie -4. 3-2 1,2,3,14,6 S(CC)

S3023-3-3.21

( See e l o

)

-AI y

Alt ACHMEIfNT 1

PA(;[

6 OF1P

NUCLEAR GENERATION SITE SURVEILLANCE OPERATING INSTRUCTION S023-3-3.0 UNITS 2 AND 3 REVISION 0 PAGE 20 OF 33 ATIACIIMENT 1

TECHNICAL SPECIFICATIONS SURVEILLANCE REQUIREMINTS (Continued)

TECH.. SPEC.

SURVEILLANCE REQUIREMENT SECT ON MODE INTERVAL NOH PROCEDURE Radiation Monitoring InstrUmentatIon:

14.3. 3.1 (See Below) 1 Area Monitors:

a Containment'- High Range Table

.3-3 1,2,3,4 S(CC) 5023-3-3.21 bAContainment Purge Isolation Table 4.13-3 1,2,3,4,6 S(CC)

S023-3-3.21 c'Maln Steam LIne Table 4.3-3 1.2,3,4 S(CC)

SO3-3-3.21 2 Process Monitors:

a Fuel Storage Pool Airborne Table 43-3 All S(CC)

(6)

S023-3-3.21 1)K Gaseous 2)'

Pa rticulate/IodIne b onto i'nmen kI rborn

1) Gaseous Table 4 3-3 1.2,3,4,6 S(CC)

S023-3-3.21 Particulate Table 3-3 1,2,3,4,6 W(CC) 5023-3-3.27.3

3) IodIne Table 4.3-3 6

W(CC)

So?3-3-3.27.3 cControRoomAIrbornTable 3-3 Al I S(CC)

S023-3-3.21

1) Pa rtulate/Iodine
2)
Gaseous, 3 Noble Gas Monitors:

a Pipnt Vent Stack Table 4.3-3 1,2,3,4 D(CC)

S023-3-3.21.1 b Condenser Evacuation System Table 4.3-3 1,2,3,4 D(CC)

(20)

SO23-3-3.21.1 Meteorological InstrumentatIon 4.3.3.4 1,2,3,I D(CC)

S023-3-3.26 Table 3-5 5,6 D(CC)

SO23-3-3.26.1 (6) With'irradiat(d '6e In the st6rage pool.

(20) With any MSIV aid/ or MSIV Bypass VaIve notAfu I y closed.

Al ACIIMEN I 1 PAm 1 01

NUCLEAR GENERATIO SITE SURVEILLANCE OPERATING INSTRUCTION S023-3-3.0 UN IS 2 AND 3 REVISION 0 PACE 21 OF 33 AlTACHMENT 1

TECHNICAL SPECIFICATIONS SURVEILLANCE REQUIREMENTS (Continued)

TECH. SPEC.

SURVEILIZLCE REQUIREMENT SECTION MODE INTERVAL NOIL PROCEDURE Remote Shutdown Mon toring 4.3.3.5 (See Below) ristrumer to lon:

1 Log Power Lev aTab I8e.3-6 1,2,3 M(CC)

S023-3-3.28

2. Reactor Coo ant Cold Leg emp
3. Pressurizer-Pressure
4. Pressur ize r Level
5. Steam Generator Level
6. Steam Generator Pressure
7. Reactor:Coolant Boron Conc.

'8.

sCondonser Vacuum

9. VolumeControl Tank Level
10.

Letdowrieat.Exch.cKPressure

11.

Letdown Heat Excih. Temp.

12.

Bor Ai d dMakeupiTank Level

13.

Condensate Storage,. ank Level

14.

ReactorCoolant Hot Leg Temp

15. 'Pressurizer Pressure.Lo 16 Pressurizer Pressure -

Hi

17.

Presurizr Level 4 18

'teain Geierwior. Pressure 19 Steam Generator Level Acc dent onito eng I ntrumentation 4.3.3.6 (See Relow) 1.n t

&birO (NR)"

Table 1..3-7 12,3 M(CC)

S0:3-3-3.35

~2-ift Prss (WR)

)

3.....

C Outlet T o

m~

Thot (WR _.

4 C Inlet Tem.- Told (WRV.

"5 Pressur~rer Iressure (WR) 6..

i essirizer Water Leve

'1.7 SteamWLInfe Pressure 8

Steam Generator water Level R) 9 fRefuelrg: Water Storage ik-Water Level w10 Ai i ry Fedwa te r Flow Rate 11 RC SystemSnbcoolirig Margti M6nitor

< 12 Safety1Valva Position Ini tiori 13 4ray Sysm Pressuire it.

4LPsi laderTemperature2 5.,

15.

onta inment Temperature 16 Conta inment ator'-LeveLINR).

17 Contin ment Wato'f Level (WR)

18. Core Exit Thermocouples 19.

Coid Leg HP lo

20. Hot Leg HPS Fow A

1.l Al I AGIIMFJ41 I1 PAl:

Wl

NUCLEAR G ENERATION SITE

-SURVEILLANCE OPERAlING INSTRUJCTION S023-3-3.0 UNITS 2 AND 3 U

REVISION 0 PAGE 22 OF 33 ATTACHMENT 1 TECHNICAL SPECIFICATIONS SURVEILLANCE REQUIREMENTS (Continued)

TECH. SPEC.

SURVEILLANCE REQUIREME SECTION MODE INTERVAL NOTE PROGEDURE Fire Detection nstrumentat ion14.3.3.7.14.8 Al I 2 Hours After (7)

S03-13-3 Seismic Event Fi re Detection Instr umentatIon 14.3.3.7.Z4.b A I 72 Hotrs After (7)(21) SW)3-13-3 Seismic Event.

Radiact Liquid Effluent Monitor 4.3.3.8.1 Instrumentation:

iquid Radwaste EffItent L. ne Table 4.3-8 Al b S/0 Blowdown Neut. Sump)

Effluent Line c Ts rbine Building Sumps Effluent Lines d S/G E-088 Biowdown Bypass Effluent Line e S/GE-089 8ow down Bypass rEff uent Line k a 'Liquid Radwaste Effluent Line Table 4.3-8 All P(SC) s;1-8-7 b

G Bilowdown(Neut.

Sump)

Table

.3-8 Al 3

Effluent Line c

.curbine Build Ig Sumps Table

.3-8 All M(SC) 3-3-3.27.3 Effluent,Line

/Eo ass Tab 3-8 Al 3-3-3.27.3 Effluent line; e S/G E088 Blowdown Bypass Table 1 3-8 Al M(SC)

Eff Iuent:Line-_

(7 Wheno ver e qupmerit pro tcted by the fire detection instrument is required to he nper;uhlI.

O tonS wII notfy(StStioneEngieneering.l AlI AClIlEN 1 1

Ps I

(I

NUCLEAR GENERATION SITE, SURVEILLANCE OPERATING INSTRUCTION S023-3-3..

UNITS 2 AND 3 REVISION 0 PAGE 23 OF 33 ATTACHMENT 1 TECHNICAL SPECIFICATIONS SURVEILLANCE REQUIREMENTS (Continued)

TECH. SPEC.

SURVEILLANCE REQU IREMENT SECTION MODE INTERVAL NOTE PROCEDURE Radi oact i i qui d Efflent Monitor 4.3.3.8.1 See IleIow)

Instrumentat ion:

(Corl nued r

2 Flow Rate Measurement Devices Table 4.3-8 All DCC)

S023-3-3.21.1 a Liquid Radvaste Effluent Line b S/G Blowdown(Neut.'Sutp)

Effluent LIne c

G/C E-088 Blowdown Bypass Effluent Line d S/G E-089 Blowdown Bypass E ffluent Line Effuen F4nitrin>

4.3.3.8.2 All

.4husS023-8-7 R~d~O8CtV~ GseousLEffuent, Monitr1 339(eeBlw Instrumentatlon:

1 Waste Gas Ho IdupSystem a Noble Gas Actiity Mon tor Table 4.3-9.

All P(CC)(SC)

S02-8-15 b Flow Rate>Mon tor Table 4.3-9.

All P(CC)

SO;'3-8-15 2 Waste Gas Holdup System Explos ve Gas Monitoring System a Hydroge Monitor: (Continuous Table 4. 3-9 All D(CC)

(8)

S023-3-3.26.1 I

.S023-3-3.26 b Hydroen tor (Periodic) rable

.3-9D(CC) 3.26.1

~

S023-3-3.26 c Oxygen Mont (Contnuous)

Table All D(CC)

(8) 3-3-3.26.1 S0213-3-3.26 d Oxygen Mon itor (Per Iodic)

Table 4.3-9 All D(CC)

(B) 3-3-3.26.1 10,-1-3-3. 26 (8)Du~ngWate asHolupSystem operation....

AA II 1 N1 1 1

01 1

NUCLEAR GENERATION SITE SURVEILLANCE OPERATING INSTRUCTION S023-3-3.0 UNITS 2 AND 3 RfVISION 0 PAGE P11 Of 33 Af ACHMENT 1

TECHNICAL SPECIFICATIONS SURVEILLANCE RFQUIREMENTS (Continued)

TECH. SPEC.

SURVEILIANCE REUIfRFMENT SECTION MODE INTIVAL NOTE PROCEDURE Radioactive Gaseous Effluent Monitor 4.3.3.9 (Sec Below)

Instrumentation:

(Continued) 3 Condenser Evacuat ion System a Noble GasiActivity Monitor Table

.3-9 1,2,3,11 D(Cc)

(20)

S023-3-3.21. I a..NobleGas: Actility Monitor Tabi

.3-9 1,2,3,4 M(SC)

(20)

SO23-3-3.27.3 b Iodine Sa er Table4.3-9 1,2,3,11 W(CC)

(20) 5023-3-3.21.1 c arti ulate.Sampler

-Table4.3-9 1,2.3,4 W(CC)

(20)

S023-3-3.21.1 aiple Flo easurement Table 4.3-9 1,2,3,4 D(CC)

(20)

S023-3-3.21.1 eProcess Rate e

TabIe 4.3-9 1,2,3,14 D(CC)

(2)

S023-3-3.21.1 4Plant Vent Stack a Noble Gas A

\\tity Monitor TableL.3-9 Al I D(C(;)

5023-3-3.21.1 a Noble Gas Ac ivity Monitor Table 4.3-9 Al I M(SC)

S023-3-3.27.3

'abb

.3-9 A

I W(CC

()023-3-3.21.

r;..

1able 4.3-9 All W(CC)

S023-3-3.21.1 F

'I'T abil&4.3-9 All D(C) 5023-3-3.21.1 eSmp ate Measur ng

'Tabl 4.3-9 All D(CC)

S023-3-3.21.1 ContaInmen urge System Noble Gag c Ivity Monitor Table 4.3-9 All D(CC)

S023-3-3.21.1 Noble Ga Acivity Monitor

'Table 4.3-9 Al I P( S) 5023-1-4.2 a Noble Gas,ctivity Monitor Table 4.3-9 Al I M(SC)

S023-3-3.27.3 b Iodine Samler

,Table 4.3-9 All W(CC)

S023-3-3.27.3, 3-3.21.1 c Particulate Sampler Table 4.3-9 All W(CC)

S023-3-3.27.3, 3-3.21.1 F

now RaitMonItor Table,4.3-9 AlI D(CC)

S023-3-3.21.1 Sample o Rate Measuring Table'4.3-9 Al I D(CC)

S023-3-3.21.1 Lose Parts-Detctlon,nstrumntatlolo 4.3.3.(10.a 1,2 D(C)

S023-3-3.26 Turbi neOerspeed krotectofl 4.3.4.a 1,2,3 W

(20)

S023-3-3.34 Tubno 0 se otection 4.3.4.b 1,2,3 M

(2i)

S023-3-3.31I ton

1.

1.2 S

Sf?3-3-3.25 (20 )W i':6nyMSl andr MSIV Bypass aiye not fully closed.

Al IACHMENI 1

PA'-

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1p

NUCLEAR GENERATION SITE SURVEILLANCE OPERATING INSTRUCTION S023-3-3.0 UNITS 2 AND 3 REVISION 0 PAGE 25 OF 33 ATTACHMENT 1 TiHNICAL SPECIFICATIONS SURVEILLANCE REQUIREMENTS (Continued)

... TECH.

SPEC.

SURVEILLANCE REQUIREMENT SECTION MODE INTERVAL NO[,.

PROCEDURE RCS -

Hot Standby 4.4.1.2.1 3

W S023-3-3.27 RCS -

HotKStandby

.4.4.1.2.2 3

S SO23-3-3.25 RCS Hot -Standby 4.4.1.2.3 3

S 5023-3-3.25 RCS -

Ho Shutdown 4.4.1.1 t-W S023-3-3.27 RCS -

HoIotShutdown 4.4.1.3.2 11 S3-3-3.25 RCSi-rHot Shutdown

.4.A1.3.3 S

S023-3-3.25 RCS-Cod Shutdon (Loops FI Iled) 4.1.1. 41.1 5

W S023-3-3.27. 1 RCS Cold Shutdown-(oops Filled)

4.1.1.4

.1.2 5

. 3.25.

RCS -

Cold Shutdown (loops FIlled) *.4.1.4.1.3 5

S 503-3-3.25.1 RCS -

Cold Shutdown (Loops Not Filled) 4.4.1.4.2 5

S SW 3-3-3.25. 1 RC Pressurizer' 4.4.3.1 1.2,3 S

5023-3-3.25 RCS Leakage Detection 4.4.5.1.a 1,2,3,4 W(C(.)

503-3-3.27.3 RCS -Leakage Detection 4.4.5.1-c 1,2:3,4 S(C(;)

5023-3-3.21 RCS" -

operationa I;eak'a~g'e

.4.4.5.2.1*.a 1,2,3,4 5

S023-3-3.21 1

023-3-3.25 RCS' 00artI on:I-'Lea kage 4.4-5.2.1.b 1.2.3,4 5

S023-3-3.25 RCS. -' Operational :Leakage 4 4.5.2.1.c 1.2,3,4 72 Hours 023-3-3.37 RCS'Oporationa~liLeakage 4:4.5.2.1.d 1,2, 3,'1 0

S023-3-3.26 RCS Operational leakage

.4.4.52.2.a-d 1,2,3,4 R

(S)5023-3-3.31.1 RC 4.4.5.1.1 3All S/U, 30 Mi.

(9) 5023-5-1.3 RCS -

Pressrae/Temp Limits

.4.8.1.1 1.l2,3.(9) 5023-5-1.5 RCS Pr ierInits4.4.8..1

.A I

~

S/U. 30 Min.

S023-5-1.3 RCS P

sre/TeapLimits4..8;1.1 AllISD 0Mn

()

82--.

RC-Presirizeor mHea'ttp/Cooldown is.8..4I S/U. 30 Min.

SOP135-.

RCS -

Pressurizer-Heatup/Cooldown 4.4.8.2.1 All S/D, 30 Mi 5023-5-1.5 RCS -

Pressurizer-Heatup/Cooldown 4.4.8.2.2 All S

(10) 50123-0-42

023-5-1.3, 5-1.5 (9) Also during n-service leak and hydrostatic testing.

(10) During main 4pray operation th less than four (4) RCPs operating and durinq auxiIiary spray operation.

(22) b. Priorto entering Moe 2 h te it; has been in Cold Shutdown for 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or more ant look:me testing hai not been performed in the previous 9 nonths; c Prior 6 declaring the valve opirable following maintenance, repair, or rapincement:

d. Within 148 hofars (24 hT-rs UnIt 3)-following valve actuation.

A] 1ACIMENT 1

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I, o

1W

NUCLEAR GENERATION SITES SURVEILLANCE OPERATING INSTRUCTION S023-3-3.0 UNITS 2 AND 3 REVISION 0 PAGE 26 OF 33 ATTACHMENT 1

TECHNICAL SPECIFICATIONS SURVEILLANCE REQUIREMENTS (Continued)

TECH. SPEC.

SURVEILLANCE REQUIREMENT SECTION MODE INTERVAL NO IIL PROCEDURE RCS,- Overpressure Protection t.1.8.3.1.1.a i4 72 Ilours S023-3-3.26 Unit 2 < 235 0 F -

Unit 3 < 285 0 F 5,6 72 Hours (2,)

5023-3-3.26.1 RCS.- Overpressure Protection 74.4.8.3.1.2 4

S (11)

S023-3-3.25 Unit 2 < 235OF -

Unit 3 < 285cF 5.6 S

(11 )(!)

SO?3-3-3.25.1 RCS -

Overpressure Protection 4.4.8.3.2.1.a 4

72 lours SW'3-3-3.26 Unit P > 235oF -

Unit 3 > 285cF RCS'- Overpressure Protection 4.1.8.3.2.3 4

S (11)

SO;'3-3-3.25 UnIt 2 > 2350 F Unit 3 > 285cF ECCS -

SIT 4.5.1.a.1,2 1,2,3 S

SO;'3-3-3.25 ECCS -

SIT 4.5.1.c 1,2,3 M

(21') 3.8 ECCS-SIT 4.5.1.d 1,2,3 M

(;II)

S023-3-3.8 ECCr S I SIT'..

4.5.1.e.2 1,2P.,

3 R

(2) 023-3-3.12, 3-3.43 ECCS

>1 350 0 1F.

4.5.2.a 1.2,3 5

(25)

S023-3-3.25

.1,2(251)

SO23-3-3.25 ECCS" -

3 F

4.5 2.c 1 2 1.2,3 12 (;"()

S023-3-3.8 CC 5()

)

SO 3-3-3.8 ECCS - SIT 4.5.1.e1.2 1,2,3 R

5 e2(2)

S023-3-3.12, 3-3.43 ECCS -

350aF.4.5.2.e.3 2R 2')

SO23-3-3.12, 3-3.43 ECCS -

<3500 41.5.3

2.

.1, R

(26)

Se Section

.5.2 ECCS RW3T0 4.5.2.a.1.

1,2,3,4 W

S.1,2-3-3.27 ECCS-RWST

.4.5.2.b 1,2,3,4 D

.33-3-3.26 ContInme~ntIntegrlty (4.6.1.1.a 11,2,3,4 M

S023-3-3.10 (1)Except' when the vent. pathway I s provided with a Valve which is locked, sealed, or otherwise sfu(.me in the Open position,

,j.,-then,verIfy..these -valves open at leastonce. per,.31 days.

(12)PrIor'( to

)establishing Containment 0ntegr2t3 (23') Moe6wth Jthe Reactor Vessel Head on.

(24). With Pressu rizer' pressure greate r than or equal to 715 psia.

(25) Witha 1Pressrzer pressure greater than or(equal to 400 psia.

(26) With Pressurier pressure less than 400 psia.

AE.ACIIMEN1 C

RSI.54.12,,

NUCLEAR GENERATION SITE SURVEILLANCE OPERATING INSTRUCTION S023-3-3.0 UNITS 2 AND 3 REVISION 0 PACE 27 Of 33 ATFACHMENT 1 TECHNICAL SPECIFICATIONS SURVEILLANCE REQUIREMENTS (Continued)

TECH. SPEC.

SURVEILLANCE REQUIREMENT SECTION MODE INTERVAL NO1L PROCEDURE Containment Air Locks 4.6.1.3.a 1,2,3,t4 72 Iloisrs

(

1h) 50;3-3-3.10.1 Containment Internal Pressure 4.6.1.4 1,2,3,4 S

SO23-3-3.25 ContaInment Temperature 4.6.1.5 1,2,3,t4 D

S023-3-3.26 Containment Ventilation 4.6.1.7.1 1.2,3,4 M

SOP3-3-3. 10 ContaInment VentIlation 4.6.1.7.2 1.2,3,1 W

S0123-0-42, 5023-3-3.26 Containment Spray 4.6.2.1.a 1,2,3 M

SO23-3-3.11 Containment Spray 4.6.2.1.b.1,2,3 1,2,3 R

5023-3-3.12 ContaInment Spray 4.6.2.1.b.4 1,2,3 R

SO23-3-3.11.2 Iodine Removal Sy tm-4.6.2.2.a 1,2,3 D

S023-3-3.26 Iodine Removal System J4.6.2.2.b 1.2,3 M

5023-3-3.11 odine Remnoval System~

.6.2;.2.c.1 1,2'3 SA

'!3-3-3.11 odine Removal 'System 4.6.2.2.d.(1) 1,2,3 R

S023 Iodine Removal Sytem!-

4.6.2.2.d.(2) 1,2,3 R 3.12, 3-3.43 odine Removal Sy4"tem 4.6.2.2.e 1,2,3 3.11.3 Containment Cooling 4.6.2.3.a.1,2 1,2,3,4 M

ContaInment CoolIng 4.6.2.3.b 1.2,3,4 R

S01'3-3-3.12, 3-3.43 Containment Csol lo aives ContaInment Isolation Valves1,2,3,4 Follwing 3-3-3.30. 3-3.31 Containment 'isola lon alves4.3(1 Maintenance ContaInment lisolatlon.Valves.

4.6.3.2 1.2,3,14 R, Cold S/D S023-3-3.33. 3-3.12, 1*

3-3.43 Containment isolation Valves 4.6.3.3 (4.0.5) 1,2,3,4 Q

S023-3-3.30 Containment Isolation Valves

.4.6.3.3 (4.0.5) 1.2,3,4 R, Cold S/D S023-3-3.31 Electric d

e Reombiner, 4.6.4.2.a 1,2 SA 5023-3-3.42 (4)- Within '72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> fol lowing each coslng except when the air lock. is being usedr for mtultiple ent io s, th n atI.

least once

_ !per',72 houirs..

(15) Reter to S023-V73.'5.O when notSfound In these procedures.

AlIl ACIIMEN I 1

PACI II Of

(

1.

NUCLEAR GENERATION SITE SURVEILLANCE OPERATING INSTRUCTION S023-3-3.0 UNITS 2 AND 3 REVISION 0 PAGE 28 OF 33 ATTACHMENT 1

TECHNICAL SPECIFICATIONS SURVEILLANCE REQUIREMENTS (Continued)

TECH. SPEC.

SURVEILLANCE REQUIREMENT SECTION MODEITRA PROCEDURE Containment Dome Circulators -..

4.6.4.3.a 1,2 R

S023-3-3.43, 3-3.12 Auxilary reedwater System 4.7.1;.2.1.-a.2-4 1,2,3 M

S023-3-3.16 Auxiliar Feedwater System 4.7.1.2.1.b.1,2 1,2,3 R

S023-3-3.12, 3-3.43 Aux11.1a eedwater--System 4.7.1.2.2 1.2, 3 S/URPrior to Mode 2 S023-3-3.16.2 After Each Cold S/D C

ense tora nk 4.7.1 3 1,2,3 S

S023-3-3.25 sIv 4.7.1.5 (.0.5) 1,2,3 Cold S/fl SO;3-3-3.17 S/C Pre ssure/Temperature Limits

.7.2 1,2,3,4 Hourly When < 700 F S023-3-3.25 5.6 Hourly When 70aF 5023-3-3.25.1 CCw 4.7.3.a 1,2,3,l M

5023-3-3.18 C

4.7.3.b 1,2,3,4 R

S0113-3-3.12, 3-3.43 SaItwater Cool ing 4.7.4.a 1,2,3,4 M

S023-3-3.18 Saltwater Cooling 4.7.4.b 1.2,3, 4 R

S023-3-3.12, 3-3.43 CR Emergency Air Cleanup 4.7.5.a 1,2,3,4 S

5023-3-3.25 5.6 S

5023-3-3.25.1 CR Emergency Air C eanup 4.7.5.b All M

50:3-3-3.20 CR Emergency Air Cleanup 4.7.5.e.2,3 All R

S023-3-3.20.1 Fi re Suppression Water System 7..

.8.1.1.a All.

W 5023-3-3.27.3 Fire Suppression Water System 4.7.8.1.1.bc Al l M

S023-3-3.36 FireKSuppression water System 4.7.8.1.1.d-AlI Y

S023-3-3.36.1 Fire Suppression ater System

-4.7.8.1.1.e.1,2,3 All R

So,3-3-3.36.2 Fi re Suppression ato System 4.7.8.1.1.f Al I 3Y S023-3-3.36.3 Fire Suppression Wati r System 4.7.8.1.2.a.1 Al I M

SO23-3-3.36, 3-3.21.3 Fire Suppression Wat r System 4.7.8.1.2.a.2 All M

S023-3-3. 36 AlIACIIMENI I

PA.

1" Of 1p,

NUCLEAR GENERATION SITE SURVEILLANCE OPERATING INSTRUCTION S023-3-3.0 UNITS 2 AND 3 REVISION 0 PAGE 29 OF 33 ATTACHMENT 1 TECN ICAL SPECIFICATIONS SURVEILLANCE REQUIREMENTS (Continued)

TECH. SPEC.

SURVEI LLANCE REQUIREMENT SECTION MODE INTERVAL NO I PROCEDURE Spray and/or Sprinkler System 4.7.8.2.a,b

!All M

I/or'11 M(16)

SO:13-3-3.36 spray and/or Sprinkler System 4.7.8.'2.c All Y

SO:'3-3-3.36.1 Spray and/or SprInkler System 4.7.8.2.d.1.b AllI.

R S 3-3-3.36.2 Emergent Chliled ater System 4.7.10.a 1,2,3,14 M

S02.3-3-3.147 EmergencyChIlledWater System 4.7.10.b 1,2,3,4 R

SO3-3-3.12, 3-3.20.1.

3-3.24.1 Electrical A.C. Sources

.4.8.1.1.1.a 1.2,3,4 W

S023-3-3.27.2 Electrical -A.C. Sources 4I.8.1.1.1.b 1,2,3,4 R

SO;)3-3-3. 19 Electrical - A.C. Sources 4.8.1.1.2.a.(1-6) 1.2,3,4 Tabln 4.8-1 SO23-3-3.23 Electrical -A.C.

Sources 4.8.1.1.2.b 1,2,3,11 M

SO23-3-3.23 Electrical A.C.

Sources 4.8.1.1.2.d.(2, 1,2,3,14 R

SO-3-3-3.12, 3-3.23.1 3, 4a and b, 5, 7a-c, 8, 10a-c, 11, 12, 114)

Electrical A.C. Sources 4.8.1.1.2.e 1,2,3'14 10Y 5023-3-3.12 ElectrIcal A.C. Sources 4.8.1.2.1 5.6 W

s3-3-3.27.2 Electrical A.C. Sotirces 14.8.1.2.2 5,6 Table 4.8-1 (19) 5083-3-3.23 Electrical A.C. Botirces 4.8.1.2.2 5.6 M

SO;3-3-3.23 Electrical -

A.C.gources 4.8.1.2.2 5,6 R

(19)

SO23-3-3.12, 3-3.23.1 El ectric9 OfsIte Power,

I4.8.3.1 1,2,3,4 W

S023-3-3.27.2 Electrlcal,,

Onsite Power 1.8.3.2.

5,6 W

5023-3-3.27.2 Refuel ingloperations -

Boron Concentration t4.9.1. 1.a,b 6

R S023-5-1.8 Refueling Opera tions nstrumentation,

.9.2.a

6.

S(CC)

S023-3-3.25.1 Refelng Operat Decay Time 5.9.3 6

Kerr < 1 (1/)

S023-5-1.8

> 72 Hours (16) Inside Contaln nwt during cold shutdown or-refueling outages.

(17) Prior to movement of Irradiated fuel In the Reactor Pressure Vessel.

19) See Techn Ical Speciication 4.8.1 2.2 for exceptIons.

Al l ACIHfNI 1 PAwI I."

NUCLEAR GENERATION SITE SURVEILLANCE OPERATING INSTRUCTION S023-3-3.0 UNITS 2 AND 3 REVISION 0 PACE 30 OF 33 ATTACHMENT 1 TECHNICAL SPECIFICATIONS SURVEILLANCE REQUIREMENTS (Continued)

TECH. SPEC.

SUR VEILLANCE REQUIREMENT SECTION MODE INTERVAL NOTE PROCEDURE Refueling Operations -Containment 4.9.4.a 6

W (18)

S023-3-3.27.1, 5-1.8 Penetrations 72 Hours Prior To Core Alterations Refueling Operatlons - Containment 4.9.4.b 6

W (18)

SO;'3-3-3.33, 5-1.8 Penetrations 72 Hours Prior To Core Alterations Refuel ing Operat ions CommunicatIons 4.9.5 6

1 Hour Prior and S023-3-3.25.1, 5-1.8 S,

During Core Alterations Refueling Operations Shutdown Cooling

.9.8.1 6

S So?3-3-3.25. 1 and Coolant Circulation Ref elngt Operatid Low Water Level

.9.8.2 6

S S023-3-3.25.1 Ref ueIinq Operat 1oh Containment Purge 4.9.9 6

72 Hours Prior To S023-5-1.8 Isolation System Core AItLerations Re fueIngOp erato0-

-Containment prge

.9.9 6

W During Core SOP3-3-3.33 Isolation System Alterations Refuel Ing-O eratlIfl -Water Level 4.9.10 6

2 Hours Prior To S023-5-1.8 Reactor Vessel Core Alterations Refuel ing Operat Ions aterLevel 4.9.10 6

D During Core SO;03-3-3.26.1 Reactor Vessel Alterations Refuel ing Operat Ions f'Water, Level

.9.11 A I (6)

Storage Pool Refuel I ng operationS FHB Post-Acdilent

-V.9.1.a

.:AI I M

(6) 3-3-3.24 Cleanup Refueling Operations -4FHB Post-Accident 4.9.12.d.2 All R

(6)

S023-3-3.24.1 C I.ilip (6) Wthj rradiated fuel, in the storage pooF2, (18 Durng core altr rations ormo t of frrdatedfuel In the Containment Building.

Al I ArIIMENT 1

PAW.I 11 Of IP

NUCLEAR GENERATION SIT SURVEILLANCE OPERATING INSTRUCTION S023-3-3.0 UNITS 2 AND 3 RE'VISION 0 PAGE 31 OF 33 ATTACHMENT 1 TECHNICAL SPECIFICATIONS SURVEILLANCE REqUIREMENTS: (Continued)

TECH. SPEC.

SURVEILLANCE REQ IU REENT SECTION MODE INTERVAL Nmr PROCEDURE L qid Effluents Con ntratlon

4. 11.1.. 3 (See Below)

B.

lscelaneo Waste Table 1

A7 M-3-3.27.3 Evaporator Cond nsate IRadioactive ffIuent Liqu d Waste 4 11.1.3.2 All Q

Treatment I.

Radioactive Effluent Gaseous t11.2.14.2 AllQ Radws ste 7reatmen t.

Rad oact ve Ef flent Explos Ive

. 11.2.5 1

Continuous 2323-3-3.26 d-a s MI xture

~

--~-

5,6' Cont i nuous 3-3-3.26.1 0

3 4S.P3-3-3.

3 AllACIMEN I 1 PAci 18 O 18

NUCLEAP GENERATION SITE SURVVILLANCE OPERATiN INSTRUCTION SOr 3-3-3.0 UNITS 2 AND 3 REVISION 0 PAGE 3 O' 3E ATTACHMENT 3 SURVEILLANCE INTERVALS AND NOTATIONS NOTE:

For conservatism, the scheduling frequency is shorter than the Technical Specification required surveillance interval.

RE RAIRED SURVE ILLANCE INTERVAL SCHEDULING ALLO ALE C

INTERVAL NOTATION FREQUENCY EXTENSION [1]

> 18 months (No. of years)

No. of years

+ 25%

18 months R (Refueling Outage) 546 days 136 days 1 year Y (Yearly) 364 days 91 days 184 days SA (Semi-Annual) 182 days 46 days 92 days Q (Quarterly) 91 days 23 days 31 days M (Monthly) 28 days 7.75 days 7 days W (Weekly) 7 days 1.75 days 1 day.

D (Daily) 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> 6 hours 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> S (Shiftly) 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> N/A Variable S/D (Shutdown)

Prior to or4.

N/A during shutdown Variable S/U (Startup)Prior to or N/A during startup Variable P (Prior to Release)

Prior to Release N/A

[1]

The maximum allowable extension shall not exceed the reuired surveillance interval by morethan 25%'

The-combined time%nterva or. any three consecutive surveillances shall not exceed 3.25 times the required surveillance. interval. (Ref. 2.1.1 4.0.2) 3045g ATTACHMENT 3 PAGE 1 OF 1

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