Text

Vol 1,Rev 19 to Technical Requirements Manual for Fermi 2
	ML20248H090
Person / Time
Site:	Fermi
Issue date:	05/31/1998
From:	; DETROIT EDISON CO.
To:	;
Shared Package
ML20248H046	List: ML20248H042; ML20248H090; ML20248H115;
References
	PROC-980531, NUDOCS 9806080059
	Download: ML20248H090 (100)
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i Fermi 2 Technical Requirements Manual Volume I Detroit Ec:ison ymmy PDR N

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I Fermi 2 l-Technical Requirements Manual O

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Detroit Edison ARMS-1NFORAfA TION l

DTC:TMTRM l File: 1754 DSN: TRM VOL 1 l Rev: 19 Date: 05/20/98 Recipient CA j'f i-a________-________

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LICENSING DOCUMENT TRANSMITTAL

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TECHNICAL REQUIREMENTS MANUAL, VOLUME 1 s

V Instructions for Revision 19 dated 05/20/98 j

Immediately upon receipt of the item (s) below, please insert and/or remove the documents indicated. Destroy the removed documents.

Location Remove Insert Title Page Title Page Title Page Rev 18 101497 Rev 19 05/20/98 l

Fermi 2 TRM Introduction Pages 1-2.

(Insert immediately following Title Page)

List of Effective Pages LEP-1, Rev.18 LEP-1, Rev.19 05/98 LEP-2, Rev.18 LEP-2, Rev.19 05/98 LEP-3, Rev.18 Table of Contents Pages i through vi Page i through v 05/98 7-Q Definitions Page 1-1 through 1-1, Rev 19 05/98 Section 2 SafetyLimits Page 2-1, Rev 19 05/98 l

Section 3.0 Pages 3/4 0-1 through 3/4 0-7, Rev 19 05/98 l

Section 3.1 Page 3/41-1, Rev 19 05/98 Section 3.2 Page 3/4 2-1, Rev 19 05/98 Section 3.3 All Pages in Section 3.3 Pages 3/4 3-1 through 3/4 3-10, Rev 19 05/98 Section 3.4 Page 3/4 4-1, Rev 19 05/98 Section 3.5 Page 3/4 5-1, Rev 19 05/98 Section 3.6 All Pages in Section 3.6 Pages 3/4 6-1 through 3/4 6-29, Rev 19 05/98 Section 3.7 Page 3/4 7-1, Rev 19 05/98 Section 3.8 All Pages in Section 3.8 Page 3/4 8-1 through 3/4 8-6, Rev 19 05/98 TN

TRM VOL I INSTRUCTIONS Location Remove Insert Section 3.9 Page 3/4 9-1, Rev 19 05/98 Section 3.10 Page 3/410-1, Rev 19 05/98 Section 3.11 Page 3/411-1, Rev 19 05/98 Section 3.12 Page 3/412-1, Rev 19 05/98 Bases Bases Tab Section 5 Design Page 5-1, Rev 19 05/98 Features Section 6 Administrative Controls Page 6-1, Rev 19 05/98 Core Operating Limits Report Insert Note in front of COLR O

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FERMI 2

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TECHNICAL REQUIREMENTS MANUAL i \\_)

INTRODUCTION' j

There are three main sections in Volume 1 of the Technical Requirements Manual:

1) the Technical Requirements, 2) the Core Operating Limits Report,'and 3) Fire Protection Limiting Conditions for Operation and Surveillance Requirements.

Each of these sections are discussed below.

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TECHNICAL REQUIREMENTS Based on the NRC's Final Policy Statement on Technical Specifications Improvements for nuclear power plants, and 10 CFR 50.36, " Technical. Specifications", as amended in the Final Rule published in the Federal Register dated July 13,1995, certain requirements may be relocated from the Operating License Technical Specifications to other licensee-controlled documents.

In an effort to. centralize the requirements relocated from the Technical Specifications and to ensure the necessary administrative controls are applied to these requirements, these requirements have been relocated as " Technical Requirements" into the Fermi 2 Technical Requirements Manual (TRM) Volume 1. These Technical Requirements provide limitations upon those plant operations which are part of the licensing basis for Fermi 2, but i

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do not meet the 10 CFR 50.36 criteria for inclusion in the

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Technical Specifications.

Volume ~1 of the TRM provides a centralized location for relocated requirements in a consistent format.

Technical Requirements retain the former Technical Specification numbering for relocated items; for example, Technical Specification 3.3.7.2 would become Technical Requirement 3.3.7.2.

However, there is one minor exception for the BASES section.

Instead of being in a separate i

section, each BASES immediately follows its corresponding

' Technical Requirement's Limiting Condition for Operation (LCO) and Surveillance Requirements.

The Technical Requirements contain their own DEFINITIONS which may be the.same as the i

Operating License. Technical Specification Definitions.

The I

Technical Requirements are formatted in a manner consistent with the Technical Specifications.

However, nothing in the Technical Requirements shall supersede any Technical Specification.

The Technical Requirements in the TRM are part of the licensing basis for Fermi 2.

Furthermore, the Technical Requirements are incorporated by reference in Section 1.6 of the Fermi 2 Updated Final Safety Analysis Report (UFSAR) and are part of the UFSAR.

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.TRM Vol I 1

REV 19 5/98 i

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f Violations of the Technical Requirements should be documented

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under the Fermi Condition Assessment Resolution Document (CARD)

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process.

Deviations from the *echnical Requirements may then be evaluated for deportability in accordance with the CARD process.

CORE OPERATING LIMITS REPORT

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The Core Operating Limits Report (COLR) is a plant-specific document that provides selected core operating limits for the current reload cycle.

These cycle specific core operating limits shall be determined for each reload cycle in accordance with the Operating License Technical Specifications.

Plant operation within these core operating limits is addressed in individual Technical Specifications.

The COLR is included.in Volume 1 of the TRM for convenience of easy reference; however, this document is not a part of the UFSAR.

FIRE PROTECTION LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS Volume 1 of the TRM also contains a duplicate of UFSAR section 9A.6, Fire Protection Limiting Conditions'for Operation and Surveillance Requirements. These are included in the TRM for the convenience of easy reference and are part of the UFSAR.

CHANGES TO THE TRM

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Design modifications, procedure changes, license amendments, etc.

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have the potential to affect the TRM.

If this occurs, the initiating department must follow the administrative controls in MLS08, " Licenses, Plans and Programs".

Changes to the TRM must i

be evaluated per the 10 CFR 50.59 program.

This program requires that the TRM's Technical Requirements and Fire Protection Limiting Conditions for Operation and Surveillance Requirements be considered in a manner similar to the UFSAR when evaluating changes to determine if an unreviewed safety question might be involved.

Changes to Volume 1 of the TRM will be reported, as a minimum, to the NRC as part of the UFSAR update submittal in accordance with 10 CFR 50.71(e).

Related safety evaluations will be reported as part of the 10 CFR 50.59 (c) report.

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FERMI 2 - TECHNICAL REQUIREMENTS MANUAL l

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FERMI 2 - TECHNICAL REQUIREMENTS MANUAL 1

TABLE OF CONTENTS - VOLUME 1

(~' s Section and Title

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INTRODUCTION..........................................

1 SECTION 1 DEFINITIONS i

TR 1.0 DEFINITIONS...............................

1-1 SECTION 2 SAFETY LIMITS TR 2.0 SAFETY LIMITS AND' LIMITING SAFETY SYSTEM SETTINGS..................................

2-1 SECTION 3 APPLICABILITY TR 3/4.0 APPLICABILITY...........................

3/4 0-1 SECTION 3.1 TR 3.1 REACTIVITY CONTROL SYSTEMS................

3/4 1-1 SECTION 3.2 TR 3.2 POWER DISTRIBUTION LIMITS.................

3/4 2-1 SECTION 3.3 TR 3/4.3 INSTRUMENTATION TR 3/4.3.1 Reactor Protection System Instrumentation.......................

3/4 3-1 TR 3/4'.3.2 Isolation Actuation Instrumentation...

3/4 3-4

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TR 3/4.3.3 Emergency Core Cooling System Actuation (s'

Instrumentation.......................

3/4 3-8 SECTION 3.4 TR 3/4.4 REACTOR COOLANT SYSTEM.,

3/4 4-1 SECTION 3.5 TR 3/4.5 EMERGENCY CORE COOLING SYSTEMS..........

3/4 5-1 SECTION 3.6 l

TR 3/4.6 CONTAINMENT SYSTEMS.....................

l TR 3/4.6.1 Primary Containment...................

TR 3/4.6.2 Depressurization Systems..............

i TR 3/4.6.3 Primary Containment Isolation Valves..

3.6-1 TR 3/4.6.4 Vacuum Hi.............................

j TR 3/4.6.5 Secondary Containment.................

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TR 3/4.3.6 Primary Containment...................

SECTION 3.7 TR 3/4.7 PLANT SYSTEMS...........................

3/4 7-1 I

l TR 3/4.7.1 Service Water Systems.......

TR 3/4.7.2 Control Room Emergency Filtration System i

TR 3/4.7.3 Shore Barrier Protection..............

, ~s TR 3/4.7.4 Reactor Core Isolation Cooling System.

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TR 3/4.7.5 Snubbers..............................

l TR 3/4.7.6 Sealed Source Contamination...........

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JPERMI 2 - TErNMIN-REQUIn - TS unwUAL TABLE OF CONTENTS (Cont'd) - VOLUME 1

'/'~g Section and Title Pace O

TR 3/4.7.9 ain Turbine Bypass System and Moisture Separator Reheater..........

TR 3/4.7.10 Reserved.............................

TR 3/4.7.11 Appendix R Alternative Shutdown

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Auxiliary Systems....................

I SECTION 3.8 TR 3/4.8 ELECTRICAL SYSTEMS......................

TR 3/4.8.1 AC Sources............................

TR 3/4.8.2 DC Sources............................

TR 3/4.8.3 Onsite Power Distribution Systems.....

TR 3/4.8.4 Electrical Equipment Protective Devices - Motor Operated Valves Thermal Overload Protection...........

3/4 8-1 SECTION 3.9 TR 3/4.9 REFUELING OPERATION.....................

3/4 9-1 TR 3/4.9.1 Reactor-Mode Switch...................

TR 3/4.9.2 Instrumentation.......................

TR 3/4.9.3 Control Rod Position..................

TR 3/4.9.4 Decay Time............................

TR 3/4.9.5 Communications........................

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TR 3/4.9.6.

Refueling Platform....................

'N-TR 3/4.9.7 Crane Travel - Spent Fuel Storage Pcol TR 3/4.9.8 Water Level - Reactor Vessel..........

TR 3/4.9.9 Water Level - Spent Fuel Storage Pool.

l TR 3/4.9.10 Control Rod Removal...................

TR 3/4.9.11 Residual Heat Removal.................

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.SECTION 3.10 i

i TR 3/4.10 SPECIAL TEST EXCEPTIONS...............

3/4 10-1 TR 3/4.10.1 Primary Containment Integrity........

I TR 3/4.10.3 Shutdown Margin Demonstrations.......

TR 3/4.10.4 Recirculation Loops..................

TR'3/4.10.5 Deleted..............................

TR 3/4.10.6 Training Startups....................

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SECTION 3.11 TR 3/4.11-RADIOACTIVE EFFLUENTS..................

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TR.3/4.11.1 Liquid Effluents.....................

SECTION 3.12 TR 3/4.12 DELETED................................

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I FmT 2 - TE N I N REOUIn n W TS w mng TABLE OF CONTENTS (Cont'd) - VOLUME 1

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Section and Title Page iQi SECTION 5 DESIG5"?EATURES TR 5.0 DESIGN FEATURES...........................

5-1 TR 5.1 SITE......................................

TR 5.2 CONTAINMENT...............................

TR 5.3 REACTOR CORE..............................

TR 5.4 REACTOR COOLANT SYSTEM....................

TR 5.5 METEOROLOGICAL TOWER LOCATION.............

TR 5.6 FUEL STORAGE..............................

TR 5.7 COMPONENT CYCLIC OR TRANSIENT LIMIT.......

SECTION 6 ADMINISTRATIVE CONTROLS TR 6.0 ADMINISTRATIVE CONTROLS...................

6-1 TR C.1 RESPONSIBILITY............................

TR 6.2 ORGANIZATION..............................

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TR 6.2.1 Offsite and Onsite Organizations........

'V TR 6.2.2 Unit Staff..............................

TR 6.2.3 Independent Safety Engineering Grou Shift Technical Advisor............p....

TR 6.2.4 TR 6.3 UNIT STAFF QUALIFICATIONS.................

TR 6.5 REVIEW AND AUDIT..........................

TR 6.5.1 Onsite Review Organization (OSRO).......

TR 6.5.2 Nuclear Safety Review Group (NSRG)......

TR 6.5.3 Technical Review and Control............

TR 6.6 REPORSECTIONLE EVENT ACTION...............

TR 6.7 SAFETY LIMIT VIOLATION....................

TR 6.8 PROCEDURES AND PROGRAMS...................

TR 6.9 REPORTING REQUIREMENTS....................

TR 6.9.1 Routine Reports.........................

TR 6.9.2 Special Reports..........................

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TR 6.9.3 Core Operating Limits Report............

l6 TR 6.10 RECORD RETENTION.........................

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TRM Vol. I iii REV 19 05/98

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FnMT 2 - TErmwIcar. p_wrxyrnmeTS wm_wrfa_r.

l TABLE OF CONTENTS fCont'd)

VOLUME 1 Section and Title...................................., pace TR 6.11 RADIATION PROTECTION PROGRAM.............

TR 6.12 HIGH RADIATION AREA......................

i TR 6.13 PROCESS CONTROL PROGRAM..................

TR 6.14 OFFSITE DOSE CALCULATION MANUAL..........

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FERMI 2 TECHNICAL REQUIREMENTS MANUAL TABLE OF MNTENTS (CONT'D) - VOLUME 1 LIST OF TABLES TRM Table

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Number Title Page i

1.1 Surveillance Frequency Notation...........

1-3 1.2 Operational Conditions....................

1-4 3.3.1-2 Reactor Protection S Times...............ystem Response 3/4 3-2 3.3.2-3 Isolation Actuation System Instrumentation Responto Time.............

3/4 3-5 3.3.3-3 Emergency Core Coolin Times................g System Response 3/4 3-9 3.6.3-1 Primary Containment Isolation Valves......

3/4 6-2 3.8.4.3-1 Motor Operated Valves Thermal Overload Protection................................

3/4 8-2 TRM Vol. I v

REV 19 05/98

1.0 DEFINITIONS r

The following terms are defined so that uniform interpretation of

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these' requirements may be. achieved.

The defined terms appear in capitalized type and shall be applicable throughout these Technical Requirements.

ACTION 1.1 ACTION shall be that part of a Technical Requirement which prescribes remedial measures required under designated conditions.

' CHANNEL CALIBRATION.

1.4 'A CHANNEL CALIBRATION shall be the adjustment, as necessary, of the' channel output such that it responds with the

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necessary range and accuracy to known values of the

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parameter which the channel monitors.

The CHANNEL'

~ CALIBRATION shall~ encompass the entire channelLincluding the sensor.and alarm and/or trip functions, and shall include the CHANNEL FUNCTIONAL TEST.

The-CHANNEL CALIBRATION may be performed by any series of sequential, overlapping or total channel steps such th&t the entire channel is calibrated.

Calibration of-instrument channels with resistance temperature detectors (RTD) or thermocouple sensors shall j

consist of verification of operability of the sensing

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element and adjustment, as necessary, of the remaining adjustable devices in the channel.

CHANNEL CHECK l '. 5 _ A CHANNEL CHECK shall be the qualitative assessment of channel behavior during. operation by. observation.

This i

determination shall include, where possible, comparison of the channel ~ indication and/or status with other indications j

and/or status. derived from independent: instrument channels i

measuring the same parameter.

CHANNEL FUNCTIONAL TEST

~1.6 A CHANNEL FUNCTIONAL TEST shall be:

i Analog channels

.the injection of a simulated signal into-i a.

the. channel as.close to the sensor as practicable to verify-4" '

' OPERABILITY including alarm and/or trip functions and channel failure trips.

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Bistable channels the injection of a simulated signal into the sensor to verify OPERABILITY including alarm and/or trip i

functions.

f The CHANNEL FUNCTIONAL TEST may be performed by any series

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of sequential, overlapping.or total channel steps such that

\\1 the entire' channel is tested.

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.TRM Vol. I 1-1 REV 19 05/98

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DEFINITIONS l

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EMERGENCY CORE COOLING SYSTEM (ECCS) RESPONSE TIME 1.11 The EMERGENCY CORE COOLING SYSTEM (ECCS) RESPONSE TIME shall be that time interval from when the monitored parameter I

exceeds its ECCS actuation setpoint at the channel sensor until the ECCS equipment is capable of performing its safety

function, i.e.,

the valves travel to their required positions, pump discharge pressures reach their required values, etc.

Times shall include diesel generator starting and sequence loading delays where applicable.

The response time may be measured by any series of sequential, overlapping or total steps such that the entire response time is measured.

i FREOUENCY NOTATION 1.14 The FREQUENCY NOTATION specified for the performance of Surveillance Requirements shall correspond to the intervals defined in TRM Table 1.1.

ISOLATION SYSTEM RESPONSE TIME 1.16 The ISOLATION SYSTEM RESPONSE TIME shall be that time interval from when the monitored parameter exceeds its isolation actuation setpoint at the channel sensor until the

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isolation valves travel to their required positions.

Times shall include diesel generator starting and sequence loading delays where applicable.

The response time may be measured by any series of sequential, overlapping or total steps such

.that the entire response time is measured.

OPERABLE - OPERABILITY 1.25 A system, subsystem, train, component or device shall be OPERABLE or have OPERABILITY when it is capable of performing its specified function (s) and when all necessary attendant instrumentation, controls, electrical power, cooling or seal water, lubrication or other auxiliary equipment that are required for the system, subsystem, train, component or device to perform its function (s) are also capable of performing their related support function (s).

REACTOR PROTECTION SYSTEM RESPONSE TIME 1.33 REACTOR PROTECTION SYSTEM RESPONSE TIME shall be the time l

interval from when the monitored parameter exceeds its trip setpoint at the channel sensor until de-energization of the scram pilot valve solenoids.

The response time may be measured by any series of sequential, overlapping or total fx steps such that the entire response time is measured.

TRM Vol. I 1-2 REV 19 05/98

DEFINITIONS

' O TRM TABLE 1.1 l

L, SURVEIT T 2LNCE FREGUENCY NOTATION I'

NOTATION FREOUENCY S.

LAt least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

D At least.once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

W At least once per 7 days.

M At least once.per 31 days.

Q-At least once per 92 days.

SA At least once per 184 days.

' 'A At least once per 366 days.

R:

At 'least once per 18 months (550 days).

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. Prior to each reactor startup.

P

. Prior to each radioactive.releas'e.

NA Not applicable.

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DEFINITIONS O

TRM TABLE 1.2 OPERATIONAL CONDITIONS MODE SWITCH AVERAGE REACT R CONDITION POSITION COOIANT TEMPERATURE 1.

POWER OPERATION Run Any temperature 2.

STARTUP Startup/ Hot Standby Any temperature 3.

HCrr SHUTDOWN Shutdown #,***

> 200* F 4.

COLD SHUTDOWN Shutdown #,***

5 200* F 5.

REFUELING

Shutdown or Refue1#

5 140* F O

The reactor mode switch may be placed in the Run, Startup/ Hot Standby, or Refuel position to test the switch interlock functions and related instrumentation provided that the control rods are verified to remain fully inserted by a second licensed operator or other technically qualified member of the unit technical staff.

Fuel in the reactor vessel with the vessel head closure bolts less than fully tensioned or with the head removed, m The reactor mode switch may be placed in the Refuel position while a single control rod is being recoupled or withdrawn provided that the one-rod-out interlock is OPERABLE.

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3 /4. 0 APPLICABILITY l'

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LIMITING CONDITION FOR OPERATION

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3.0.1 Compliance with the Limiting Conditions for Operation in the succeeding Technical Requirements is required during the OPERATIONAL CONDITIONS or other conditions specified therein; except that upon failure to meet the Limiting Conditions for Operation, the associated ACTION statement (s) shall be met.

3.0.2 Noncompliance with a Technical Requirement shall exist when the Limiting Condition for Operation and associated ACTION'

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statement (s) are not met within the specified time intervals.

If the Limiting Condition for Operation is restored prior to expiration of the specified time intervals, completion of the ACTION statement (s) is not required, i

3.0.3 Where corrective measures are completed that permit operation under the ACTION statement (s), the ACTION may be taken I

in accordance with the specified time limits as measured from the time of failure to meet the Limiting Condition for Operation.

3.0.4 Entry into an OPERATIONAL CONDITION or other specified condition shall not be made when the conditions for the Limiting Conditions for Operation are not met and the associated ACTION requires a shutdown if they are not met within a specified time j

interval.

Entry into an OPERATIONAL CONDITION or other specified

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condition may be made in accordance with the ACTION statement (s)

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when conformance to them permits continued operation of the facility for an unlimited period of time.

This provision shall not prevent passage through or to OPERATIONAL CONDITIONS as required to comply with the ACTION statement (s).

Exceptions to these conditions are stated in the individual Technical Requirements.

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APPLICABILITY

SURVEILLANCE REQUIREMENTS-4".'O.1' 'Surveillan'e. Requirements shall be met during the c

OPERATIONAL CONDITIONS or other.. conditions specified.-for individual Limiting Conditions for Operation unless otherwise stated in an individual Surveillan'e Requirement.

c 4.0.2: lEach Surveillance Requirement.shall be performed within the-specified surveillance interval-with a maximum allowable.

' extension:notlto exceedx25 percent of the specified surveillance tinterval.

4.0.3 ~ Failure.to perform al Surveillance Requirement within the

._ allowed' surveillance interval, defined by Technical Requirement

.4.'O.2,-'shall constitute noncompliance with the OPERABILITY requirements;for.a' Limiting Condition for: Operation.

The time' 3

limits;of.the ACTION statement (s). are applicable at the; time it^

isfidentified that a Surveillance Requirement has not been performed.

The ACTION statement (s). may be~ delayed.for.up to 24l hours.to: permit the completion ofLthe surveillance.when the allowable outage: time limits of the' ACTION statement (s) are less than 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

Surveillance. Requirements do not have to.be performed on inoperable' equipment.

I 4 '. 0. 4 Entry.into an OPERATIONAL _ CONDITION?or other_apecified.

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~ applicable. condition shall.not be made unless the Surveillance Requirement (s)' associated; with _ the' Limiting Condition for Operation'have been performed within-the applicable surveillance

' interval.or.as otherwise specified.

This provision shall not prevent passage"through or.to' OPERATIONAL CONDITIONS as required

, to; comply.with ACTION. statement (s).

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3/4 LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS

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3/4.0 APPLICABILITY v

BASES Technical Requirement 3.0.1 establishes the Applicability statement within each individual Technical Requirement as the requirement for when (i.e.,

in which OPERATIONAL CONDITIONS or other specified conditions) conformance to the Limiting Conditions for Operation is required for safe operation of the facility.

The ACTION statement (s) establish those remedial

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measures that must be taken within specified time limits when the i

requirements of a Limiting Condition for Operation are not met.

I It is not intended that the shutdown ACTION statement (s) be used i

as an operational convenience which permits (routine) voluntary

)

removal of a system (s) or component (s) from service in lieu of j

other alternatives that would not result in redundant systems or j

components being inoperable.

j k

There are two basic types of ACTION statement (s).

The first 0

specifies the remedial measures that permit continued operation of the facility which is not.further restricted by the time limits of the ACTION statement (s).

In this case, conformance to the ACTION statement (s) provides an acceptable level of safety for unlimited continued operation as long as the ACTION statement (s) continue to be met.

The second type of ACTION

,T']

statement (s) specifies a time limit in which conformance to the

()

conditions for the Limiting Condition for Operation must be met.

{

This time limit is the allowable outage time to restore an inoperable system or component to OPERABLE status or for i

restoring parameters within specified limits.

The specified time limits of the ACTION statement (s) are applicable from the point in time it is identified that a Limiting Condition for Operation is not met.

The time limits of l

the ACTION statement (s) are also applicable when a system or component is removed from service for surveillance testing or,

investigation of operational problems.

Individual Technical Requirements may include a specified time limit for the completion of a Surveillance Requirement when equipment is l

removed from service.

In this case, the allowable outage time l

limits of the ACTION statement (s) are applicable when this limit J

expires if the surveillance has not been completed.

When a shutdown is required to comply with ACTION statement (s), the plant may have entered an OPERATIONAL CONDITION in which a new Technical Requirement becomes applicable.

In this case, the time limits of the ACTION statement (s) would apply from the point in

{

time that the new Technical Requirement becomes applicable if the requirements of the Limiting Condition for Operation are not met.

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j TRM Vol. I 3/4 0-3 REV 19 05/98 l'

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I

, 3 /4. 0 APPLICABILITY BASES (Con't)

Technical Requirement 3.0.2 establishes that noncompliance with a Technical Requirement exists when the requirements of the Limiting Condition for Operation are not met and the associated ACTION e*S*,ement (s) have not been implemented within the specified time interval.

The purpose of this Technical Requirement is to clarify that (1) implementation of the ACTION statement (s) within the specified time interval constitutes compliance with a Technical Requirement and (2) completion of the remedial measures of the ACTION statement (s) is not required when compliance with a Limiting Condition of Operation is restored a

within the time interval specified in the associated ACTION statement (s).

1 Technical Requirement 3.0.3 establishes that the time limits of the ACTION requirements are applicable from the point in time it I

is identified that there was a failure to meet a Limiting j

Condition for Operation.

Therefore, operation may continue if

)

the ACTION requirements have been met or the time limits of the 1

ACTION requirements have not expired, thus providing an allowance for the completion of the required actions.

Technical Requirement 3.0.4 establishes limitations on a change in OPERATIONAL CONDITIONS when a Limiting Condition for Operation

( ))

is not met.

It precludes placing the facility in a higher 1-CONDITION of operation when the requirements for a Limiting Condition for Operation are not met and continued noncompliance to these conditions would result in a shutdown to comply with the ACTION requirements if a change in CONDITIONS were permitted.

The purpose of this Technical Requirement is to ensure that facility operation is not initiated or that higher CONDITIONS of 1

operation are not entered when corrective action is being taken to obtain compliance with a. Technical Requirement by restoring equipment to OPERABLE status er parameters to specified limits.

Compliance with ACTION statement (s) that permit continued operation of the facility for an unlimited period of time provides an acceptable level of safety for continued operation without regard to the status of the plant before or after a change in OPERATIONAL CONDITIONS.

Therefore, in this case, entry into an OPERATIONAL CONDITION or other specified condition may be made in accordance with the provisions of the ACTION statement (s).

The provisions of this Technical Requirement should not, however, be interpreted as endorsing the failure to exercise good practice in restoring systems or components to OPERABLE status before plant startup.

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TRM Vol. I 3/4 0-4 REV 19 05/98

l 3/4.0 APPLICABILITY

(

)

BASES (Con't)

When a shutdown is required to comply with ACTION statement (s),

the provisions of Technical Requirement 3.0.4 do not apply

.because they would delay placing the facility in a lower CONDITION of operation.

Technical Requirement 4.0.1 establishes the requirement that surveillance must be performed during the OPERATIONAL CONDITIONS or other conditions for which the requirements of the Limiting Conditions for Operation apply unless otherwise stated in an individual Surveillance Requirement.

The purpose of this Technical Requirement is to ensure that surveillance are performed to verify the operational status of systems and components and that parameters are within specified limits to ensure safe operation of the facility when the plant is in an OPERATIONAL CONDITION or other specified condition for which the individual Limiting Conditions for Operation are applicable.

Surveillance Requirements do not have to be performed when the facility is'in an OPERATIONAL CONDITION for which the requirements of the associated Limiting Condition for Operation do not apply unless otherwise specified.

The Surveillance Requirements associated with a Special Test Exception are only applicable when the Special Test Exception are only applicable when the Special Test Exception is used as an allowable exception

, )

to the requirements of a Technical Requirement.

Technical Requirement 4.0.2 establishes the limit for which the specified time interval for Surveillance Requirements may be extended.

It permits an allowable extension of the normal surveillance interval to facilitate' surveillance scheduling and consideration of plant operating conditions that may not be

. suitable for conducting the surveillance; e.g.,

transient conditions or other ongoing surveillance or maintenance activities.

It also provides flexibility to accommodate the length of a fuel cycle for surveillance that are specified with an 18-month surveillance interval.

It is not intended that this provision be used repeatedly as a convenience to extend surveillance intervals beyond that specified for surveillance that are not performed once each fuel cycle.

Likewise, it is not the intent that surveillance with an 18-month interval be performed during power operation unless it is consistent with safe plant operation.

The limitation of Specification 4.0.2 is based on engineering judgment and the recognition that the moct probable result of any particular surveillance being performed is the verification of conformance with the Surveillance Requirements..This provision is sufficient to ensure that the reliability ensured through surveillance activities is not significantly degraded beyond that obtained from the specified surveillance interval.

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TRM Vol. I 3/4 0-5 REV 19 05/98

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3 /4. 0 APPLICABILITY i

n BASES (Con't)

Technical Requirement 4.0.3 establishes the failure to perform a Surveillance Requirement within the allowed surveillance interval, defined by the provisions of Specification 4.0.2, as a condition that constitutes a failure to meet the OPERABILITY requirements for a Limiting Condition for Operation.

Under the provisions of this Technical Requirement, systems and components are assumed to be OPERABLE when Surveillance Requirements have i

been satisfactorily performed within the specified time interval.

However, nothing in this provision is to be construed as implying that systems or components are OPERABLE when they are found or know to be inoperable although still meeting the Surveillance Requirements.

This Technical Requirement also clarifies that the i

ACTION requirements are applicable when Surveillance Requirements have not been completed within the allowed surveillance interval and that the time limits of the ACTION requirements apply from i

the point in time it is identified that a surveillance has not been performed and not at the time that the allowed surveillance interval was exceeded.

Completion of the' Surveillance Requirement within the allowable outage time limits of the ACTION statement (s) rostores compliance with Technical Requirement j

4.0.3.

However, this does not negate the fact that the' failure to have performed the surveillance within the allowed j

surveillance interval, defined by the provisions of Technical l

()

Requirement 4.0.2, constitutes a failure to meet the OPERABILITY k,/

requirements for a Limiting Condition for Operation and any m

reports required by 10 CFR 50.73 shall be determined based on the length of time the surveillance interval has been exceeded, and the corresponding Limiting Conditions for Operation ACTION time requirements.

If the allowable. outage time limits of the ACTION statement (s) are less than 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months or a shutdown is required to comply with ACTION requirements, a 24-hour allowance is provided to permit a delay in implementing the ACTION requirements.

This provides an adequate time limit to complete Surveillance Requirements that have not been performed.

The purpose of this allowance is to permit the completion of a surveillance before a shutdown would be required to comply with ACTICN statement (s) or before other remedial measures would be required that may preclude the completion of a surveillance.

The basis for this allowance includes consideration for plant conditions, adequate planning, availability of personnel, the time required to perform the surveillance, and the safety significance of the delay in completing the required surveillance.

This provision also provides a time limit for the completion of Surveillance Requirements that become applicable as a consequence of CONDITION l

changes imposed by ACTION statement (s) and for completing Surveillance Requirements that are applicable when an exception to the provisions of Technical Requirement 4.0.4 is allowed.

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TRM Vol. I 3/4 0-6 REV 19 05/98

3/4.0 AI PLACABILITY (3

(

)

BASES (Con't)

If a surveillance is not completed within the 24-hour allowance, the time limits of the ACTION statement (s) are applicable at that time.

When a surveillance is performed within the 24-hour allowance and the Surveillance-Requirements are not met, the time lindts of the ACTION statement (s) are applicable at the time that the surveillance is terminated.

Surveillance Requirements do not have to be performed on inoperable equipment because the ACTION statement (s) define.the remedial measures that apply.

However, the Surveillance Requirements have to be met to demonstrate that inoperable I

equipment has been restored to OPERABLE status.

Technical Requirement 4.0.4 establishes the requirement that all applicable surveillance must be met before entry into an j

OPERATIONAL CONDITION or other condition of operation specified in the Applicability statement.

The purpose of this requirement is to ensure that systems and component OPERABILITY requirements or parameter limits are met before entry into an C?ERATIONAL i

CONDITION or other specified condition for which these systems and components ensure safe operation of the faciliay.

This provision applies to changes in OPERATIONAL CONDITIONS or other i

specified conditions associated with plant shutdown as well as

(~]

startup.

Undar the provisions of this Technical Requirement,.the i

applicable Surveillance Requirements must be performed within the specified surveillance interval to assume that the Limiting Conditions for Operation are met during initial plant startup or following a plant outage.

i When a shutdown is required to comply with ACTION statement (s),

the provisions of Technical Requirement 4.0.4 do not apply because this would delay placing the facility in a lower CONDITION of operation.

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3 /4. 3 INSTRUMENTATION

- 3 /4. 3.1 REACTOR PROTECTION SYSTEM INSTRUMENTATION l

LIMITING CONDITION FOR OPERATION 3.3.1 -The Reactor Protection System instrumentation channels shall be OPERABLE with REACTOR PROTECTION SYSTEM RESPONSE TIMES as shown in TRM Table 3.3.1-2.

APPLICABILITY: 'As shown in Technical Specification Table 3.3.3-1.

ACTION:

'As provided in the ACTION of Technical Specification 3.3.1.

SURVEILLANCE REQUIREMENTS 4.3.1 The REACTORLPROTECTION SYSTEM RESPONSE TIME of each reactor trip functional unit shall be demonstrated in accordance with Technical Specification Surveillance Requirement 4.3.1.3.

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TRM - TABLE 3.3.1-2 G

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(UFSAR TABLE 7.2-4)-

REACTOR PROTECTION SYSTEM RESPONSE TIMES

. FUNCTIONAL UNIT RESPONSE TIME (Seconds) 1.

Intermediate Range Monitors:

a.

Neutron Flux -..High NA b.

Inoperative NA 2.

' Average Power Range Monitor *:

a.

Neutron Flux - High, Setdown NA b.

Flow Biased Simulated Thermal Power - High 6

1**

c.

Fixed Neutron Flux'- High s 0.09 d.

Inoperative NA 3.

Reactor Vessel Steam Dome Pressure - High 5 0.55' 4.

Reactor Vessel Low Water Level - Level 3 s 1.05' 5.

Main Steam Line Isolation Valve - Closure s 0.06 6.

Main Steam Line Radiation - High NA j

7.

Drywell Pressure - High NA i

8.

Scram Discharge Volume Water Level - High

'O '

a.

Float Switch NA k

b.

Level Transmitter NA 9

Turbine Stop Valve - Closure s 0.06 10.

Turbine Control Val _ve Fast Closure s 0-08***

11.

Reactor Mode Switch Shutdown Position

-NA

-12.

Manual Scram NA 13.

Deleted-

Neutron detectors are exempt from response time testing.

Response

time shall be measured from the detector output or from the input of the first electronic component in the channel.

- Including simulated thermal power time constant.

- - Measured from deenergization of K-37 relay which inputs the turbine control valve closure signal to the RPS.

The sensor response time need not be measured and may be assumed to be the design sensor response time.

Prior to return to service of a new transmitter' or following refurbishment of a transmitter (e.g.,

sensor cell'or variable damping components), a hydraulic response time test will be performed to determine an initial sensor-specific

-[

response time value.

(

l TRM Vol,.'I 3/4 3-2 REV 19 05/98 I'

t 3/4.3' INSTRUMENTATION BASES l

3/4.3.1 REACTOR PROTECTION SYSTEM INSTRUMENTATION The' measurement of response time at the specified frequencies provides assurance.that the protective functions associated with each channel are' completed.within the. time limit assumed in the safety analyses.

No credit was taken for those

. channels _with response times indicated as r,ot applicable.

Response time may be demonstrated by any series of sequential, overlapping or total channel test measurement, provided such tests demonstrate the total channel response time as defined.

Sensor response time verification may be demonstrated by either

'(1) inplace, onsite or offsite test measurements, or (2) utilizing _ replacement sensors with certified response times..

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.TRM Vol.' I 3/4 3-3 REV 19 05/98

f INSTRUMENTATION 3/4.3.2 ' ISOLATION ACTUATION INSTRUMENTATION LIMITING CONDITION-POR OPERATION

.3.3.2 The Isolation Actuation System instrumentation channels shall be-OPERABLE with ISOLATION SYSTEM RESPONSE-TIMES as shown I

[

in'TRM Table-3.3.2-3.,

L APPLICABILITY:

As'shown in Technical Specification Table 3.3.2-1.

'l

ACTION:

.As provided in the' ACTION of' Technical Specification 3.3.2.

.' SURVEILLANCE REQUIREMENTS The.ISbLATION SYSTEM' RESPONSE TIMES of-each isolation trip I

4.3.2

' function'shall be demonstrated in accordance.with Technical

. Specification Surveillance Requirement.4.3.2.3.

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TRM - TABLE 3.3.2-3

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(UFSAR TABLE 7.3-12)

ISOLATION ACTUATION SYSTEM INSTRUMENTATION RESPONSE TIME TRIP FUNCTION RESPONSE TIME (Seconds) 1.

PRIMARY CONTAINMENT ISOLATION l

a.

Reactor Vessel Low Water Level 1)

Level 3 j

NA 2)

Level 2

)

NA i

3)

Level 1 s1.0*"

b.

Drywell Pressure - High NA

{

c.

Main Steam Line 1)

Radiation - High NA 2)

Pressure - Low NA 3)

Flow - High s0.5*"

d.

Main Steam Line Tunnel Temperature - High NA Condenser Pressure - High NA e-.

f.

Turbine Bldg. Area Temperature - High NA g.

Deleted-h.

Manual Initiation NA

'.j 2.

REACTOR WATER CLEANUP SYSTEM ISOLATION LJ a.

Flow - High NA b.

Heat Exchanger / Pump /High Energy Piping i

Area Temperature.- High NA c.

Heat Exchanger / Pump / Phase Separator Area' Ventilation Temperature T - High NA d.

SLCS Initiation NA e

Reactor Vessel Low Water Level - Level 2 NA f.

Deleted 9

' Manual Initiation NA

)

3, REACTOR CORE ISOLATION COOLING SYSTEM ISOLATION a.

RCIC Steam Line Flow - High NA b.

RCIC Steam Supply Pressure - Low NA RCIC Turbine Exhaust Diaphragm Pressure - High NA c.

d.

RCIC Equipment Room Temperature - High NA e.

Manual Initiation NA

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E __ _ _ _ _ _ _ _ _ _ _ _ _ _ _..

I.

'TRM - TABLE 3.3.2-3 (Continued)

,:(_

d (UFSAR TABLE - 7.3-12) 1 ISOLATION ACTUATION' SYSTEM INSTRUMENTATION RESPONSE T M

' TRIP FUNCTION EESPONSE TIME (Seconds) 4.

-HIGH PRESSURE COOLANT INJECTION SYSTEM' ISOLATION a.

.HPCI Steam Flow - High' NA b.

'HPCI Steam Supply Pressure - Low NA HPCI Turbine Exhaust Diaphragm Pressure - High' NA c.

d.

'HPCI Equipment Room Temperature-High NAq e.

-Manual Initiation NA-

- 5.

RHR SYSTEM SHUTDOWN COOLING MODE ISOLATION 4.

~a.

. Reactor Vessel Low Water Level _- Level 3 NA b.

Reactor Vessel (Shutdown Cooling Cut-in Permissive' Interlock) Pressure - High NA c.

Manual-Initiation" NA-6.

SECONDARY CONTAINMENT ISOLATION a.

Reactor Vessel Low Water Level - Level 2 NA b.

Drywell Pressure - High

NA

,./(/7'f-Fuel Pool Ventilation Exhaust Radiation - High NA c.

d.

Manual Initiation' NA'

LIsolation. system instrumentation response time for MSIVs only..No

'aiesel' generator delays assumed for MSIVs.

1. .The: sensor. response time need not be measured and may be assumed to be.the design sensor response. time.. Prior to return to service of a new-transmitter or following refurbishment of a transmitter (e.g.,

l

._ sensor cellor' variable damper components), a hydraulic response time

-test.will be: performed to determine an initial sensor-specific

' response time value.

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b L

4 t

g INSTRUMENTATION

.BASESi 3/4.3.2 ' ISOLATION-ACTUATION INSTRUMENTATION i

r-

Thisirequirement ensures th ' effectiveness of-the e

] instrumentation ~ used.to mitigate the consequences of. accidents by

~

L

. prescribing.the. OPERABILITY response times for isolation-of the

+-

reactor systems.

Except for the MSIVs, the' safety analysis does not address

~

individual. sensor response. times or the response times of.the,

? logic systems toLwhich the sensors;are connected..For D.C.

s

. operated valves,=a-3 second delay is assumed before the valve-starts to move. 'For A.C. operated valves, it is assumed that the

< ~

A.C. power supply is lost'and is restored by startup of the

_ emergency.~ diesel generators.

In this event, a time-of 13' seconds is assumed before the valve' starts to move.

In addition to the pipe. break, the failure of the D.C. operated valve'is assumed; ' '

1thus_the signal-delay..(sensor response)'is concurrent with the.10

'second. diesel startup.

The safety analysis! considers an-

. allowable inventory loss in each case which in' turn' determines e

. the valve speedlin conjunction:with the 10 second delay.

It

~

follows.that checking the; valve speeds and..the'10 second time for i.

emergency power 1 establishment will establish.the; response'. time.

'p^

for;theTisolati'nifunctionst.

However, to enhance overall system" o

. reliability;andito monitor; instrument channel. response time

. trends, the : isolation: actuation -instrumentation response time shall be measured'and recorded.as.a.part offthe ISOLATION SYSTEM

? RESPONSE TIME.

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INSTRUMENTATION 3/4.3.3~ EMERGENCY CORE COOLING SYSTEM ACTUATION INSTRUMENTATIO

' LIMITING' CONDITION FOR OPERATION

-3.3.3-The' Emergency Core Cooling System (ECCS) actuation instrumentation channels shall be OPERABLE with ECCS RESPONSE TIMES asishown in TRM Table 3.3.3-3.

APPLICABILITY 'As shown in Technical Specification Table 3.3.3-1.

ACTION:

_ s.

As provided in the ACTION of Technical Specification 3.3.3.

1

' SURVEILLANCE REQUIREMENTS

.4.3.3 The ECCS RESPONSE TIME:of each ECCS trip function shall be demonstrated in accordance with Technical Specification Surveillance' Requirement 4.3.3.3.

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TRM TABLE 3.3.3-3

,-~s (UFSAR TABLE - 7.3-11) 4 L)

EMERGENCY CORE COOLING SYSTEM RESPONSE TIMES TRIP FUNCTION RESPONSE TIME (Seconds) 1.

CORE SPRAY SYSTEM a.

Reactor Vessel Low Water Level - Level 1 s 30**

b.

Drywell Pressure - High s 30**

c.

Reactor Steam Dome Pressure - Low NA*

d.

Manual' Initiation NA 2.

LOW PRESSURE COOLANT INJECTION MODE OF RHR' SYSTEM a.

Reactor Vessel Low Water Level - Level 1 s 55**

b.

Drywell Pressure - High s 55**

c.

Reactor Steam Dome Pressure - Low NA*

d.

Reactor Vessel Low Water Level - Level 2 NA e.

Reactor Steam Dome Pressure - Low NA f.

Riser Differential Pressure - High NA l

g.

Recirculation Pump Differential Pressure -

NA 1

High

{

h.

Manual Initiation NA 3.

HIGH PRESSURE COOLANT INJECTION SYSTEM a.

Reactor Vessel Low Water' Level - Level 2 s 30**

b.

Drywell Pressure - High NA i

c.

Condensate Storage Tank Level - Low NA e3 d.

Reactor Vessel Water Level - High, Level 8 NA

]f

}-

e.

Suppression Pool Water Level - High NA

(/

f.

Manual Initiation NA 4.

AUTOMATIC DEPRESSURIZATION SYSTEM i

a.

Reactor Vessel Low Water Level - Level 1 NA-b.

Drywell Pressure - High NA c.

ADS Timer NA d.

Core Spray Pump Discharge Pressure - High NA e.

RHR LPCI Mode Pump Discharge Pressure - High NA f.

Reactor Vessel Low Water Level - Level 3 NA g.

Manual Initiation NA h.

Drywell Pressure - High Bypass Timer NA 1.

Manual Inhibit NA 5.

LOSS OF POWER 4.16 kV Emergency Bus Undervoltage (Loss a.

of Voltage)

NA b.

4.16 kV Emergency Bus Undervoltage (Degraded Voltage)

NA l

These are permissive signals only.

They do not activate ECCS initiation.

- ECCS actuation instrumentation response time need not be measured and may be assumed to be the design instrumentation response time.

Prior

,- s to return to service of a new transmitter or following refurbishment

(

)

of a transmitter (e.g., sensor cell or variable damping components),

's a hydraulic response time test will be performed to determine an initial sensor-specific response time value.

TRM Vol. I 3/4 3-9 REV 19 05/98 L

l j,

INSTRUMENTATION

'/'}

BASES.

4 j.

3/4:3.3-EMERGENCY' CORE COOLING SYSTEM ACTUATION INSTRUMENTATION

-The emergency core cooling system actuation instrumentation is.provided to: initiate actions to mitigate the-consequences of accidents that.are beyond the ability of the operator to control.

This requirement'provides the. OPERABILITY requirements, trip setpoints and response times that will ensure effectiveness of the systems to provide the design protection.

Although the instruments are listed by system, in some cases the same instrument may.be used to send the actuation signal'to more than-one system at the same time.

Operation with a trip. set less conservative than its Trip Setpoint but.within its specified Allowable Value is acceptable.

on the basis that the difference between each Trip Setpoint and j

the Allowable Value is' equal to or less than the drift allowance assumed for each trip in the safety analyses.

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. CONTAINMENT SYSTEMS 3/4.6.3 PRIMARY CONTAINMENT ISOLATION VALVES LIMITING' CONDITION FOR OPERATION

- 3.6.3 Leach-primary containment isolation valve shall be OPERABLE with the maximum isolation times as shown in TRM Table.3.6.3-1.

APPLICABILITY:

OPERATIONAL CONDITIONS 1, 2 AND 3.

l i

ACTION:

As provided in the ACTION _of Technical Specification - 3.6.3 s

SURVEILLANCE REQUIREMENTS 1

4.6.3. Each primary containment isolation valve shall be l

demonstrated OPERABLE in accordance with Technical Specification

- Surveillance Requirements 4.6.3.1 and 4.6.3.3.

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-TRM - TABLE 3.6.3-1 jy kj PRIMARY CONTAINMENT ISOLATION VALVES MAXIMUM M

-ISOLATION TIME

. VALVE' FUNCTION AND NUMBER (Seconds) 1A, Automatic Isolation Valves I*'

4

-1, Groun 1 - Main Steam System Main Steam: Isolation Valves (MSIVs):

Inboard-

'Line A: B2103-F022A 5

Line B: B2103-F022B 5

Line C: B2103-F022C 5

Line D: B2103-F022D 5

3 Outboard Line'At B2103-F028A 5

Line B: B2103-F028B 5

Line C: B2103-F028C 5

Line Dr B2103-F028D 5

-Main Steam'Line: Drains Isolation Valves O

Inboard:

B2103-F016 23-

'V-Outboard:'B2103-F019 23 2,

Grouc 2 - Reactor Water Samole System Reactor. Water Sample Line Isolation Valves Inboard:.' B310 0-F019 -

Outboard: B3100-F020 15 15 ap '

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.TRM Vol.

E1100-F025B 4Q/

5.

RHR Pumo Suction From Recire Pinino Reverse Flow Check Valve NA E1100-F408 6.

RHR Shutdown Coolino Suction Relief Valve lt) (P)

NA E1100-F029 7.

RHR Pume Torus Suction Relief Valves 'IIPI NA I

E1100-F030A E1100-F030B E1100-F030C E1100-F030D i

(

!\\s)

I TRM Vol. I 3/4 6-16 REV 19 05/98

-TRM - TABLE 3:6.3-1 PRIMARY CONTAINMENT' ISOLATION VALVES MAXIMUM I

ISOLATION TIME "I VALVE FUNCTION-AND NUMBER (Seconds) l I

D.

Other Isolation Valves (Cont:Inued)

'8.

Core Sorav Loon Containment Reverse Flow check Valves ~

NA' -

E2100-F006A.

.E2100-F006B

.9.

Core Sorav Loon Pumo Suction Relief Valves (t)(P)

.pg i

E2100-F032A E2100-F032B 10.

Core Sorav Loon Pumo Discharoe Pressure I

L Relief Valves *I -

NA

(. I

'I.

E2100-F011A

'E2100-F012A E2100-F011B~

E2100-F012B

-11.

Excess Flow' Check Valves 'I I

NA

.a.

-Jet-Pump Instrumentation B21-F513A-I-

^

B21-F513B B21-F513C B21-F513D.

B21-F514A-0 B21-F514B B21-F514C-1 l-B21-F514D

.B21-F515A-B21-F515B B21-F515C I

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-3/4 6-17 REV 19-05/98 l

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m'm_mm________ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _. _. _ _ _. _ _

___m__-__;______________-_..._-_______

m___ _ _ _ _ _ _ _. _ _ _ _ _ _ _ _ _

____.__.__s..

~

TRM - TABLE 3.6.3-1 (Continued)

R.

.j PRIMARY CONTAINMENT ISOLATION VALVES MAXIMUM-ISOLATION' TIME VALVE FUNCTION AND NUMBER (Seconds)

D.

-Other Isolation Valves (Continued)

11. Excess Flow' check Valves M (Continued)
NA a.
Jet Pump Instrumentation _(Continued)
I i
B21-F515D A
B21-F515E B21-F515F.
B21-F515G B21.r515H
'B21-F515L' B21-F515M B21-F515N' B21-F515P
'B21-F515R" 1
i B21-F515S j
B21-F515T
-B21-F515U t
b.
RPV Instrumentation j
1)
Level:
B21-F507
'B21-F508 B21-F509 B21-F510-t' B21-F511 B21-F512 2)
Pressure:
B21-F506 l
B21-F508 B21-F516A'1 1
- l S
O 1
4
TRM Vol~. I 3/4 6-18 REV 19 05/98 w
1 TRM - TABLE ~3.6.3-1 PRIMARY CONTAINMENT ISOLATION VALVES MAXIMUM I
ISOLATION TIME l
f VALVE FUNCTION AND NUMBER (Seconds)
~
D.
Other Isolation Valves (Continued)
.11 -. Excess Flow Check Valves # (Continued)
NA b.
~ RPV Instrumentation (Continued) 2)
Pressure'(Continued)
B21-F516B l
B21-F516C B21-F517A B21-F517B B21-F517C B21-F517D N21-F539A N21-F539B G33-F583
c. _ Core Spray Instrumentation E21-F500A E21-F500B
-d.
HPCI Instrumentation E41-F500 E41-F501' E41 F502'.
E41-F503 e.
RCIC Instrumentation
(
-E51-F503 E51-F504 E51-F505 E51-F506 i
)
-w.
TRM Vol. I 3/4 6-19 REV 19 05/98 i
f'
TRM
' TABLE 3.6.3-1 (Continued)
T.-_./
' PRIMARY' CONTAINMENT ISOLATION VALVES MAXIMUM-M ISOLATION TIME VALVE FUNCTION AND NUMBER (Seconds)
D.
Other Isolation Valves'(Continued)
11. Excess Flow Check Valves (Continued)
NA f.
Recirculation Pump Instrumentation 1)': Flow Loop A:
B31-F503A B31-F504A B31-F505A B31-F506A Loop B:
B31-F503B B31-F504B B31-F505B B31-F506B 2)
Inlet Differential Pre.ssure B31-F501A B31-F501B B31-F501C B31-F501D B31-F502A B31-F502B
-B31-F502C i
B31-F502D
3). Pump Differential-Pressure i
Pump A:
B31-F510A-B31-F511A i
~
i i
I
. TRM Vol. I; 3/4 6-20 REV 19 05/98 o
___ 1 _..._ E.__._.-__. - - - - - - _ - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - -
- - ' ' ' - - ~ ~ - ~ ~ ~ ' ' ~ ~
~ ~ ~ ~ ~ - ~ ~
TRM - TABLE 3.6.3-1 (Continued)
PRIMARY CONTAINMENT ISOLATION VAfV_ES t
MAXIMUM ISOLATION TIME VALVE FUNCTION AND NUMBER (Seconds)
D.
Other Isolation Valves (Continued)
11. Excess Flow Check Valves (Continued)
NA f.
Recirculation Pump Instrumentation (Continued) 3)
Pump Differential Pressure (Continued)
Pump B:
B31-F510B B31-F511B 4)
Seal Cavity Pressure Pump A, #1 Seal: B31-F516A Pump A, #2 Seal: B31-F515A Pump B, #1 Seal: B31-F516B Pump B, #2 Seal: B31-F515B 5)
Pumps A and B Suction Pressure B31-F512A B31-F512B g.
Main Steam Flow Instrumentation:
Line A: B21-F501A B21-F502A B21-F503A B21-F504A Line B: B21-F501B B21-F502B B21-F503B B21-F504B O
TRM Vol. I 3/4 6-21 REV 19 05/98
TRM - TABLE 3.6.3-1 (Continued)
,/-(j PRIMARY CONTAINMENT ISOLATION VALVES MAXIMUM I
ISOLATION TIME "I VALVE FUNCTION AND NUMBER (Seconds)
D.
Other Isolation Valves (Continued) l 1
I
11. Excess Flow Check Valves #I (Continued)
NA i
g.
Main Steam' Flow Instrumentation (Continued) i Line C:
B21-F501C i
B21-F502C l
B21-F503C B21-F504C j
Line D:
B21-F501D B21-F502D B21-F503D B21-F504D
12. HPCI Turbine Exhaust Drain Pot Drain To Suceression
(
)
Chamber Reverse Stoo Check Valve "II*I NA I
LJ E4150 F022
13. RCIC Turbine Exhaust Line Isolation Check Valve "II*I NA I
E5150-F001 i
14. HPCI Turbine Exhaust Line Isolation Valve "II'I NA I
E4150-F021
15. RCIC Barometric Condenser Vacuum Pume Discharce Ston Check Valve "II*I I
NA E5150-F002
. f *y x.sl l-I
[
TRM Vol. I 3/4 6-22 REV 19 05/98 l
t..
TRM - TABLE 3.6.3-1 (Continued) s s
PRIMARY CONTAINMENT ISOLATION VALVES MAXIMUM ISOLATION TIME "3 I
. VALVE FUNCTION AND NUMBER (Seconds) l D '.
Other Isolation Valves (Continued)
J
16. Combustible Gas Control System Return Line
. Relief Valves NA
' Division I:
T4804-F016A
. Division II: T4804-F016B i
17. Suoeression Pool to Reactor Buildino Check Valves NA T2300-F450A I
T2300-F450B-l l
18. CRD-Insert and Withdrawal ValvesI 3 I*I
.NA The following valve identifiers are common to all HCUs and'are sub-
. components under each HCU PIS number..HCU PIS numbers are C1103-D001 t
through C1103-D185.
C11 "120 l
C11-F121 l,
C11-F122 C11 ' W1 L
15. Standbv Licuid Control Reverse Flow Check Valves NA
. Inboard:
C4100-F007 p.
Outboard:
C4100-F006
20. (DELETED)l
21. EECW Suco1v to Drvwell Eauioment Check Valves NA l
Division I: -P4400-F282A Division II: P4400-F282B r
o d
't
,TRM Vol.'I 3/4 6'-23 R2V 19 05/98
_.__am_____m_------_2--_=-
--' ' - - ~ - - ~ - - - ^ - - - - - - ~
I' l '.'
.TRM - TABLE 3.6.3-1 (Continued)-
~[]:<
L' -
PRIMARY CONTAINMENT ISOLATION VALVES
'MAXIMLH I
ISOLATION TIME ^
j-
. VALVE FUNCTION ~AND' NUMBER (Seconds)
[.
D.
Other Isolation Valves (Continued).
t
).
22..(DELETED) l fl 23, Control Rod Drive System Insert and Withdrawal
~
Lines'$
NA l..
The following_ valve identifiers are common to all'HCUs and are sub-y components,under each HCU PIS number. HCU PIS numbers are C1103-D001 through C1103-D185.
C11-F115' l
C11-F138
24. Control = Rod Drive Scram Discharoe Volume NA'.
t C1100-F010 C1100-F011 C1100-F180 l /
C1100-F181
t o
l
~
h-P TRM'Vol..I.
3/4 6-24 REV 19 05/98 L
--/.
w_-___-.-_-__L
-~
TRM - TABLE 3.6.3-1 (Continued)
PRI_ MARY CONTAINMENT ISOLATION VALVES TABLE NOTATIONS l
(a)
The following is a summary of the parameters which will automatically actuate the Primary Containment Isolation Valve Groups. The instrumentation associated with these parameters is described in Technical Specification 3.3.2.
1.
Grouc 1 - Main Steam System Reactor Vessel Low Water Level - Level 1 Main Steam Line Radiation - High Main Steam Line Flow - High Main Steam Line Tunnel Temperature - High Main Steam Line Pressure - Low Condenser Pressure - High Turbine Building Area Temperature - High 2.
Grouc 2 - Reactor Water Samole System Reactor Vessel Low Water Level - Level 2 Drywell Pressure - High Main Steam Line Radiation - High 3.
Group 3 - Residual Heat Removal (RHR) System Reactor Vessel Low Water Level - Level 1 Drywell Pressure - High 4.
Grouc 4 - Residual Heat Removal Shutdown Coolino and Head Spray Reactor Vessel Low Water Level - Level 3 Reactor Vessel Pressure - High, Shutdown Cooling Interlock 5.
.Groun 5 - Core Sorav System Reactor Vessel Low Water Level - Level 1 Drywell Pressure - High 6.
Grouc 6 - Hioh Pressure Coolant Iniection (HPCI) System HPCI Steam Line Flow - High HPCI Steam Supply Pressure - Low HPCI Turbine Exhaust Diaphragm Pressure - High HPCI Equipment Room Temperature - High 7.
Groun 7 - Hioh Pressure Coolant Iniection (HPCI) Vacuum Breakers Drywell Pressure - High with simultaneous HPCI Steam Supply Pressure - Low TRM Vol. I 3/4 6-25 REV 19 05/98
1 l
i TRM - TABLE 3.6.3-1 (Continued)
~
gQ PRI_MAPY CONTAINMEt'iT ISOLATION VALVES TABLE NOTATIONS (Continued) i l
8.
Grouc 8 - Reactor Core Isolation Coolino (RCIC) System RCIC Steam Line Flow - High RCIC Steam Supply Pressure - Low RCIC Turbine Exhaust Diaphragm Pressure - High 1
RCIC Equipment Room Temperature - High 9.
Groun 9 - Reactor Core Isolation Coolino (RCIC) Vacuum Breakers Drywell Pressure - High with simultaneous RCIC Steam Supply Pressure - Low 10.
Groun 10 - Reactor Water Cleanuo (RWCU) System (Inboard)
RWCU Differential Flow - High f
RWCU Area Temperature - High RWCU Area Ventilation Differential Temperature - High Reactor Vessel Low Water Level - Level 2 11.
Grouc 11 - Reactor Water Cleanuo (RWCU) System (Outboard) s T
4
(
l i
SLCS Initiation (not a containment isolation signal)
RWCU Differential Flow - High RWCU Area Temperature - High RWCU Area Ventilation Differential Temperature - High Reactor Vessel Low Water Level - Level 2 12.
Groun 12 - Torus Water Manacement System (TWMS)
Reactor Vessel Low Water Level - Level 2 Drywell Pressure - High 13.
Groun 13 - Drvwell Sumos Reactor Vessel Low Water Level - Level 3 Drywell Pressure - High 14.
Grouc 14 - Drvwell and Suoeression Pool Ventilation System Reactor Vessel Low Water Level - Level 2 Drywell Pressure - High 15.
Groun 15 - Traversino In-Core (TIP) System i
Reactor Vessel Low Water. Level - Level 3
, - ~
(L')
Drywell Pressure - High TRM Vol. I 3/4 6-26 REV 19 05/98
TRM -~ TABLE 3.6.3-1 (Continued)
PRI_ MARY CONTAINMENT ISOLATION VALVES TABLE NOTATIONS (Continued)'
15.
'Groun 15 - Traversino In-Core (TIP) System (Continued)
NOTE:
Either of these signals initi' ate TIP withdrawal which results in automatic closure of the TIP Ball Valves when the TIP probe has entered the shield cask.
16.
Groun 16 - Nitrocen Inertino System Reactor Vessel Low Water Level - Level 2 Drywell Pressure - High 17.
Groun 17~- Recirculation Pumo System and Primary Containment Radiation Monitorinc System Reactor Vessel Low Water Level - Level.2
~
Drywell Pressure - High 18.
Groun 18 - Primary Containment Pneumatic Sucolv System Reactor Vessel Low Water Level - Level 2
{
Drywell Pressure - High
'I
- ~
(b).
These valves'are hydrostatically leak tested.
.O'
(./
(c)
- Deleted.
(d)'
Also closes at. somatically as a result of Torus Room Floor Drain Sump Level - High
.High and'Drywell Floor Drain Sump Level 1High - High.
(e)
These valves may be closed remotely from one of the following locations:
1) control room.
2).
their. respective local panels.
(f)
Will automatically reposition as a result of the actuation of the i
LPCI Loop Selection Logic.
(g)
Will automatically close when the corresponding RHR loop flow is'
' greater than 3000-gpm.
~(h)'
~
Will automatically close when the corresponding core spray loop flow is greater than approximately 775 gpm.
. (1)-
Will automatically close when a) HPCI Turbine Steam Stop Valve
?+-
~ E4100-F067 closes or b) HPCI Turbine Steam Supply Isolation Valve E4150-F001 closes.
(j)
Will automatically close as a result of the condition listed in Note (1), above, as well as when HPCI flow is greater than 1200
. []
. gpm.
LJ TRM Vol..'I 3/4 6-27 REV 19 05/98
--,.w--aw--.-
-.---wa-

.-.,-,---.--_---------sn----,.

r -
I t
l l
TRM - TABLE 3.6.3-1 (Continued) f)
PRI_ MARY CONTAINMENT ISOLATION VALVES TABLE NOTATIONS [(Continued) l-(k)
Will' automatically close when a) _RCIC Turbine Steam Stop Valve
E5150-F045 closes or b) RCIC Turbine Governor Trip and' Throttle l
Valve E5150-F059 closes.
l-
[(l' )
Will. automatically close as a result of the conditions listed in j
Note (k) above, as well as when RCIC flow is greater than 130.gpm.
~(m)!
These valves are actuated by remote manual key-locked switches and will cut.the TIP cable and seal-off the TIP guide tube when-
[
actuated. These valves.are squib-fired.
[
(n)
May be closed remotely as a secondary actuation mode to reverse
. flow.
(o).- > Valves. realign automatically on'a reactor scram signal.
.(p)
Thermal relief valves.
-(q)
.' Locked closed.
'(r):
Not subject to Type C leakage tests.
(s)'.Hydrostatically tested in accordance with Technical Specification 4.4.3.2.2 in lieu of the requirements of Specification 4.6.1.2.
(t)
These Containment Isolation Valve (s) are not Type C tested.
Containment'by-pass leakage is prevented'since the line terminates below the minimum water"3evel in the suppression chamber and the K
-system is a closed system outside Primary Containment.
2 (u)-
Valve closes onilow reactor water leve1< signal'(Level 1) or.high
[
drywell pressure signal to ensure all SDC flow is directed to the reactor vessel.
(v)
Includes' valve stroke time only.
1 l
l i
.TRM Vol'..I-3/4 6-28 REV 19 05/98
,o
T CONTAINMENT SYSTEMS O
AeEs-3/416.3 PRIMARY CONTAINMENT ISOLATION VALVES The' OPERABILITY offthe primary containment.~ isolation valves ensures that=the-~ containment: atmosphere.will be isolated'from.the' r
a.-
'outside environment in the event of a release of.-radioactive.
material-to the containment atmosphere or pressurization'of the-containment and-is consistent;with the requirements of.GDC 54 R
through.57iofJAppendix A of_10 CFR Part 50.
Containment...
isolation within the' time limits,specified for those isolation-
1. valves designed.to closeLautomatically' ensures'that the release
of.; radioactive materiality the' environment'will be'. consistent-with the' assumptions used.in the analyses for a LOCA.
~
I 4
4 7
-A.
lJ.
a h
q, o g:-
7 ;.
c
[.f 'o Q
1 1TRM Vol. I
.-3/4 6-29 REV 19 05/98 t
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O l
l TRM Vol. I 3/4 7-1 REV 19 05/98 i
)
-j
ELECTRICAL POWER SYSTEMS 3/4.8.4 ELECTRICAL EOUIPMENT PROTECTIVE DEVICES MOTOR-OPERATED VALVES THERMAL OVERLOAD PROTECTION l
LIMITING CONDITION FOR OPERATION 3.8.4.3 The thermal overload protection of each valve in TRM Table 3.8.4.3-1 shall be OPERABLE.
AEPIICABILITY:
Whenever the motor-operated valve is required to be OPERABLE.
ACTION:
As provided in the ACTION of Technical Specification 3.8.4.3.
SURVEILLANCE REQUIREMEITTS 4.8.4.3 The thermal overload protection for the above required valves shall be demonstrated OPERABLE in accordance with Technical Specification Surveillance Requirement 4.8.4.3.
O O
TRM Vol. I 3/4 8-1 REV 19 05/98
TRM - TABLE 3.8.4.3-1 iD
-Q MOTOR-OPERATED VALVES THERMAL OVERLOAD PROTECTION SYSTEM (S)
VALVE NUMBER AFFECTED 1.
B2103-F016 Nuclear Boiler System B2103-F019 Nuclear Boiler System B2103-F021 Nuclear Boiler System.
B2103-F600 Nuclear Boiler System
2.
.B3105-F031A Reactor Recirculation System B3105-F031B Reactor Recirculating System 3.
E1150-F003A Residual Heat Removal (RHR)
E1150-F003B RHR E1150-F004A RHR E1150-P004B RHR E1150-F004C
.RHR E1150-F004D RHR E1150-F006A RHR E1150-F006B
'RHR E1150-F006C RHR E1150-F006D RHR E1150-F007A RHR E1150-F007B RHR
'Q E1150-F008 RHR rl O E1150-F009 RHR E1150-F010 RHR E1150-F015A RHR E1150-F015B RHR l
E1150-F016A RHR E1150-F016B RHR-E1150-F017A RHR E1150-F017B RHR E1150-F021A RHR E1150-F021B RHR E1150-F022 RHR H
E1150-F023 RHR f
E1150-F024A RHR i
.E1150-F024B RHR E1150-F026B RHR E1150-F027A RHR
{
E1150-F027B RHR E1150-F028A:-
RHR E1150-F028B RHR I
'E1150-F047A RHR E1150-F047B RHR E1150-F048A RHR
-,,c TRM Vol. I 3/4 8-2 REV 19 05/98
l l
TRM - TABLE 3.8.4.3-1 (Continued) i D(g' MOTOR-OPERATED VALVES THERMAL OVERLOAD PROTECTION
{
SYSTEM (S)
VALVE NUMBER AFFECTED-l
'E1150-F048B RHR E1150-F068A RHR E1150-F068B RHR E1150-F073 RHR t
E1150-F075 RHR l
E1150-F608 RHR E1150-F611A RHR E1150-F611B RHR 4.
E1150-F601A RHR Service Water Pumps and Motors E1150-F601B RHR Service Water Pumps and Motors E1150-F602A RHR Service Water Pumps and Motors E1150-F602B RHR Service Water Pumps and Motors E1150-F603A RHR Service Water Pumps and Motors E1150-F603B RHR Service Water Pumps and Motors E1150-F604A RHR Service Water Pumps and Motors E1150-F604B
,RHR Service Water Pumps and Motors E1150-F605A-RHR Service Water Pumps and Motors l
E1150-F605B RHR Service' Water Pumps and Motors 1
/%
5.
E2150-F004A Core. Spray System E2150-F004B Core Spray System E2150-F005A Core Spray System E2150-F005B Core-Spray System E2150-F015A Core: Spray System-E2150-F015B Core Spray System E2150-F031A Core Spray System I
E2150-F031B Core Spray System E2150-F036A Core Spray System E2150-F036B Core Spray Sys?.em 6.
E4150-F001 High Pressure CooAant Injection System (HPCI)
E4150-F002 HPCI E4150-F003-HPCI E4150-F004 HPCI E4150-F006 HPCI E4150-F007 HPCI E4150-F008 HPCI E4150-F012.
HPCI E4150-F021 HPCI
.tu
[
TRM Vol. I 3/4 8-3 REV 19 05/98 O___________
TRM - TABLE 3. 8. 4. 3-1 ' (Continued)
MOTOR-OPERATED VALVES THERMAL OVERLOAD PROTECTION-SYSTEM (S)
VALVE NUMBER AFFECTED
,E4150-F022~
HPCI E4150-F041 HPCI E4150-F042 HPCI
-E4150-F059 HPCI E4150-F075
'HPCI E4150-F079 HPCI E4150-F600 HPCI 7.
E5150-F001 Reactor' Core Isolation. Cooling.
System (RCIC)-
E5150-F002 RCIC E5150-F007' RCIC
'E5150-F008 RCIC E5150-F010 RCIC E5150-F012 RCIC E5150-F013 RCIC E5150-F019 RCIC E5150-F022
'RCIC E5150-F029 RCIC E5150-F031 RCIC
' /^)g E5150-F045 RCIC i
E5150-F046 ECIC
.E5150-F059 RCIC E5150-F062.
RCIC E5150-F084 RCIC E5150-F095 RCIC-8.
G1154-F018 Drywell Floor Drain System G1154-F600 Drywell Floor Drain System I
'9.
G3352-F001 Reactor Water Clean-up System (RWCU)
H, G3352-F004 RWCU G3352-F220 RWCU Return Line
10. -GS100-F600 Torus. Water Management System (TWMS)
G5100-F501 TWMS G5100-F602 TWMS G5100-F603 TWMS G5100-F604 TWMS
G5100-F605 TWMS G5100-F606 TWMS LG5100-F607 TWMS 11.
N1100-F607 Main Steam System
[_}
N1100-F608 Main Steam System L/
N1100-F609 Main Steam System N1100-F610 Main Steam System i
TRM Vol.'I-3/4 8-4 REV 19 05/98 L______.______._
~
i l
j TRM - TABLE 3.8.4.3-1 (Continued)
MOTOR-OPERATED VALVES THERMAL OVERLOAD PROTECTION SYSTEM (S)
VALVE NUMBER AFFECTED 12.
DELETED 13.
P4400-F601A Emergency Equipment Cooling Water (EECW)
L P4400-F601B EECW P4400-F602A EECW P4400-F602B EECW
.P4400-F603A EECW P4400-F603B EECW P4400-F604 EECW P4400-F605A EECW P4400-F605B EECW
.P4400-F606A EECW P4400-F606B EECW P4400-F607A EECW P4400-F607B EECW P4400-F608 EECW P4400-F613 EECW P4400-F614 EECW P4400-F615 EECW
}
P4400-F616 EECW w/
E 14.
P5000-F603 Compressed: Air System P5000-F604 Compressed Air System 15.
T4804-F601A Containment Atmosphere Control System
.T4804-F601B Containment Atmosphere Control System T4804-F602A Containment. Atmosphere Control System T4804-F602B Containment Atmosphere. Control System T4804-F603A Containment. Atmosphere Control System T4804-F603B Containment Atmosphere Control System
'T4804-F604A Containment Atmosphere Control System T4804-F604B Containment Atmosphere-Control System
,T4804-F605A Containment Atmosphere. Control System T4804-F605B Containment Atmosphere Control System
'T4804-F606A Containment Atmosphere Control System T4804-F606B Containment Atmosphere' Control System T4804-F601 Containment Atmosphere Control System T4804-F602 Containment Atmosphere Control System 16.
T4901-F601 Primary Containment Pneumatic Supply System L
T4901-F602.
Primary Containment Pneumatic Supply L
System
, ~. -
kJ TRM Vol. I 3/4 8-5 REV 19 05/98 a
ll' I
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l -- - _
ELECTRICAL POWER SYSTEMS
("U BASES 3,
t 3/4.814 ELECTRICAL EQUIPMENT PROTECTIVE DEVICES The' OPERABILITY of the motor operated valves thermal
l. :
overload protection ensures-that.the thermal overload protection will not prevent safety related valves from perfoming their function.
The' Surveillance Requirements for demonstrating the OPERABILITY of the thermal overload protection are in accordance with Regulatory Guide 1.106 " Thermal Overload Protection for
' Electric. Motors on Mocor Operated Valves," Revision 1, March-r=
l
((
1977.
1 L
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I Note:
The Core Operating Limits Report is provided in this manual for convenience
. and is NOT a part of the Updated Final Safety Analysis Report
}
)
4 g.
9
+
,

ML20248H090

Text

Response

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