ML070530371
| ML070530371 | |
| Person / Time | |
|---|---|
| Site: | Vermont Yankee  |
| Issue date: | 01/30/2007 |
| From: | Hamer M Entergy Corp |
| To: | Rowley J NRC/NRR/ADRO/DLR |
| References | |
| TAC MD2297 | |
| Download: ML070530371 (58) | |
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From: "Hamer, Mike" <mhamer@entergy.com>
To: "Jonathan Rowley" <JGR@nrc.gov>
Date: Tue, Jan 30, 2007 10:35 AM
Subject:
<<VYNPS TRM Revision 25.pdf>>
See Section 4.13.C. for fire hose station requirements.
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VYNPS TRM Creation Date Tue, Jan 30, 2007 10:35 AM From: "Hamer, Mike" <mhamer@entergy.com>
Created By: mhamer@entergy.com Recipients nrc.gov TWGWPO03.HQGWDOO1 JGR (Jonathan Rowley)
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Vermont Yankee Technical Requirements Manual (TRM)
4 TRM CHANGE FORM
- k PREPARATION, REVIEW AND PROCESSING OF TEC-NICAL REQUIREMENTS MANUAL CHANGE REQUESTS TRM Change# 0 0 a TRM Revision # ____
Effective Date: 714010J6
'I/
M] Administrative Change [*echnical Change Prepared by: 19f C/e/ /fcC-q5ke/7 Iff Date:________ka Printed Name -~ Sibnature Approved by: , / XJ'- /22*6-*
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Licensing Maoer Approved by: -0#4 td 1t "
Reviewed by PORC*: A)I/ Date: 411, PORd!Meeting (I
Approved**: cttA- Date:.
,Manager
- Required for technical that contain a 10CFR50.59 Evaluation.
- Required for technical changes only.
VYAPF 0060.02 AP 0060 Rev. 4 Page I of I
VYNPS TRM Vermont Yankee Technical Requirements Manual List of Effective Pages Revision 25 Page Revision Page Revision TOC-1 25 3.10-1 14 1.0-1 22 3.13-1 14 3.13-2 22 3.0-1 25 3.13-3 14 3.0-2 25 3.13-4 19 3.13-5 14 3.2-1 14 3.13-6 14 3.2-2 21 3.13-7 20 3.2-3 14 3.13-8 14 3.2-4 14 3.13-9 14 3.2-5 14 3.13-10 14 3.2-6 25 3.13-11 14 3.2-7 25 3.13-12 14 3.2-8 21 3.2-9 21 6.0-1 19 3.2-10 21 6.0-2 19 3.2-11 21 6.0-3 25 3.2-12 21 6.0-4 25 3.2-13 25 6.0-5 19 3.2-14 25 6.0-6 22 3.2-15 21 3.2-16 21 3.2-17 24 3.2-18 21 3.5-1 14 3.6-1 14 3.6-2 14 3.6-3 14 3.6-4 14 3.7-1 14 3.7-2 23 3.7-3 18 3.7-4 18
TRM RECORD OF REVISION Revision Description of TRM Change Affected Pages Number Original Original Issue All Addition of Administrative Rev. 1 Control Section 6 per TS 1, 18, and 19 thru 30 Amendment #163 Administrative Change to Rev. 2 Section 3.13 per TS Amendment 9, 14, and 15
- 164 Technical Change to Fire Water Rev. 3 Requirements due to TRM Change 1, 11 and 12 No.99-003 Technical Change to Sections Rev. 4 3.13 and 6.7 to remove 30 day 5, 6, 7, 10, 11, 12, reporting requirement from TRM. 27 and 28 Administrative Change to remove Rev. 5 information relocated to the 1, 19 thru 30 VOQAM.
(Seven pages will be removed.)
Administrative Change to Rev. 6 relocate information per TS 1, 2a thru 2f and 23 Amendment 186 and delete page 23.
Administrative Change to update Rev. 7 to RHR SW pressure required at 3 the outlet of the RHR Heat Exchanger.
Administrative Change to make Rev. 8 the VY TRM a General UFSAR 2 reference.
Administrative Change to change Rev. 9 the smoke detectors in the 15 Emergency Diesel Generator rooms per MM 99-050.
Administrative Change to Rev. 10 relocate information per TS 1, 3a, 3b Amendment 190.
Administrative Change to Rev. 11 relocate information per TS 2, 20, 21, 22 Amendment 193 and revise MOO title to VP.
Administrative Change to Rev. 12 accommodate higher 2, 3a, 3b and 3c conductivities associated with Noble Chemical.Injection.
Page 1 of 3 JULY 6, 2006
TRM RECORD OF REVISION Revision Description of TRM Change Affected Pages Number Technical Change to fire Rev. 13 protection surveillance 5, 6, 7, 9, 10, 12, frequencies. 13, 14, 17 and 20 Administrative Change to Rev. 14 relocate information from the All pages of the TRM Tech Specs to the TRM per TS are affected by this Amendments No. 210 and 211, change.
reformat pages as necessary, renumber all TRM pages and update the Table of Contents.
Rev. 15 Change to Section 3.7 to delete 3.7-2, 3.7-4 and 3.7-5 unnecessary information.
Rev. 16 Technical Change to Control Rod 3.2-13 Block Instrumentation Functional Test.
Rev. 17 Technical Change to revise APRM TOC, 1.1-1 through Rod Block specifications. 1.1-4, 3.2-7, 3.2-15 and 3.2-16 Rev. 18 Technical Change to Table 3.7-2, 3.7-3, 3.7-4, 4.7.2. 3.7-5 Rev. 19 Technical Change to add Table 1.0-1, 3.13-4, 6.0-1 6.1.2, revise for consistency through 6.0-6 with License Amendment No. 214 and other minor changes.
Rev. 20 Technical Change to Fire 3.13-7 Barrier Surveillance Frequency Rev. 21 Technical Changes to add Post- 3.2-2, 3.2-6 - 3.2-18 Accident Instrumentation Section and changes related to ARTS/MELLLA License Amendment Rev. 22 Administrative Change to Titles 1.0-1, 3.13-2, 6.0-4, 6.0-6 Rev. 23 Administrative Change to normal 3.7-2 valve position specified in Table 4.7.2 Page 2 of 3 JULY 6, 2006
TRM RECORD OF REVISION Revision Description of TRM Change Affected Pages Number Rev. 24 Administrative Change to 3.2-6, 3.2-17 implement EPU license amendment 229.
Rev. 25 Change IRM Rod Block TOC-I, 3.0-1, 3.0-2, requirements to be consistent 3.2-6, 3.2-7, 3.2-13, with TS requirements. Also 3.2-14, 6.0-3, 6.0-4 make editorial and administrative changes
+ 4
+ +
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Page 3 of 3 JULY 6, 2006
VYNPS TRM TABLE OF CONTENTS Introduction 1.0-1 TRM 1.0 DEFINITIONS 1.0-1 TRM 3.0 Limiting Conditions for Operation and Surveillance Requirement (SR) Applicability 3.0-1 TRM 3.2 Protective Instrument Systems 3.2-1 A. Emergency Core Cooling System 3.2-1 B. Primary Containment Isolation 3.2-1 C. Reactor Building Ventilation Isolation and Standby Gas Treatment System Initiation 3.2-1 E. Control Rod Block Actuation 3.2-2 G. Post Accident Instrumentation 3.2-2 L. Reactor core Isolation Cooling System Actuation 3.2-2 TRM 3.5 CORE AND CONTAINMENT COOLING SYSTEMS 3.5-1 C. Residual Heat Removal (RHR) Service Water System 3.5-1 D. Station Service Water and Alternate Cooling Tower Systems 3.5-1 TRM 3.6 REACTOR COOLANT SYSTEM 3.6-1 B. Coolant Chemistry 3.6-1 G. Single Loop Operation 3.6-2 TRM 3.7 STATION CONTAINMENT SYSTEMS 3.7-1 D. Primary Containment Isolation Valves 3.7-1 TRM 3.10 AUXILIARY ELECTRICAL POWER SYSTEMS 3.10-1 B. Operation with Inoperable Components 3.10-1 TRM 3.13 FIRE PROTECTION SYSTEM 3.13-1 A. Fire Detection 3.13-1 B. Vital Fire Suppression Water System 3.13-2 C. Fire Hose Stations 3.13-5 D. CO2 Systems 3.13-6 E. Vital Fire Barrier Penetration Fire Seals 3.13-7 F. Sprinkler Systems 3.13-8 G. Foam Systems 3.13-9 TRM 6.0 ADMINISTRATIVE CONTROLS 6.0-1
Introduction:
The TRM is established as part of implementing an NRC approved Safety Evaluation Report. The TRM provides a central location for those items that have been relocated out of Technical Specifications, as well as any other items deemed appropriate by plant management, and may be physically located and maintained in the back of the existing Technical Specifications or in a separate binder on distinctly colored paper. The TRM may contain TRM Limiting Conditions for Operation (TLCOs), lists, cross-references, acceptance criteria, programs or operational conveniences. The controls established by this procedure provide permanent records to document required reviews, implementation and NRC submittal of TRM changes, as applicable.
The definitions contained in Technical Specifications Section 1.0, "Definitions," apply to the TRM. All items relocated from the plant Technical Specifications to the TRM shall retain their existing numbering with a "TRM" added in the front. For example, Surveillance Requirement (SR) 4.13 in the plant Technical Specifications becomes TRM 4.13 upon relocation to the TRM. In addition, the TRM control requirements have been incorporated into the FSAR as FSAR Section 13.10, "Technical Requirements Manual." As such, changes to the TRM are governed by the 10CFR50.59 change process.
The TLCOs are contained in Section 3.0 and include operational requirements, TRM Surveillance Requirements (TSRs), and Required Actions for inoperable equipment. References to "Specifications" within the TRM refer to the Technical Specifications unless otherwise noted.
While the TLCOs are to be treated like Technical Specifications from an implementation viewpoint, the TLCOs are essentially procedures.
Therefore, unless specifically stated in the TLCO, entry into or violation of a TRM Required Action, or violation of a TRM Surveillance Requirement is not specifically reportable per 10 CFR 50.72 or 10 CFR 50.73.
Likewise, power reductions and/or plant shutdowns required to comply with TRM ACTIONS are not specifically reportable per 10 CFR 50.72(b)(1)(i)(A) or 10 CFR 50.73(a) (2)(i) (A) or (a) (2) (i) (B). Failure to comply with TLCO requirements shall be treated as a failure to follow procedure and entered into the corrective action program, as appropriate.
TRM 1.0 DEFINITIONS AA. Vital Fire Suppression Water System - The vital fire suppression water system is that part of the fire suppression system which protects those instruments, components,' and systems required to perform a safe shutdown of the reactor. The vital fire suppression system includes the water supply, pumps, and distribution piping with associated sectionalizing valves, which provide immediate coverage of the Reactor Building, Control Room Building, and Diesel Generator Rooms.
JJ. Process Control Program (PCP) - A process control program shall contain the sampling, analysis, tests, and determinations by which wet radioactive waste from liquid systems is assured to be converted to a form suitable for off-site disposal.
VYNPS TRM TRM 3.0 LIMITING CONDITIONS FOR TRM 4.0 SURVEILLANCE REQUIREMENT (SR)
OPERATION APPLICABILITY APPLICABILITY TRM 3.0.1 RESERVED TRM 4.0.1 SRs shall be met during the modes or other specified conditions in the Applicability for individual TLCOs, unless otherwise stated in the SR.
Failure to meet a Surveillance, whether such failure is experienced during the performance of the Surveillance or between performances of the Surveillance, shall be failure to meet the TLCO. Failure to perform a Surveillance within the specified frequency shall be failure to meet the TLCO except as provided in TRM 4.0.3.
Surveillances do not have to be performed on inoperable equipment or variables outside specified limits.
TRM 4.0.2 Unless otherwise stated in these specifications, periodic surveillance tests, checks, calibrations, and examinations shall be performed within the specified surveillance intervals. These intervals may be adjusted plus 25%. The operating cycle interval is considered to be 18 months and the tolerance stated above is applicable.
TRM 4.0.3 If it is discovered that a surveillance was not performed within its specified frequency, declaring applicable TRM Limiting Conditions for Operation (TLCOs) not met may be delayed, from the time of discovery, up to 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or up to the limit of the specified frequency, whichever is greater. This delay period is permitted to allow performance of the surveillance. A risk evaluation shall be performed for any Surveillance delayed greater than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> and the risk impact shall be managed.
VYNPS TRM TRM 3.0 LIMITING CONDITIONS FOR TRM 4.0 SURVEILLANCE REQUIREMENT (SR)
OPERATION APPLICABILITY APPLICABILITY TRM 4.0.3 (Continued)
If the surveillance is not performed within the delay period, applicable TLCOs must immediately be declared not met, and applicable TLCOs must be entered.
When the surveillance is performed within the delay period and the surveillance is not met (i.e., acceptance criteria are not satisfied),
applicable TLCOs must immediately be declared not met, and applicable TLCOs must be entered.
VYNPS TRM TRM 3.2 TRM LIMITING CONDITIONS FOR TRM 4.2 TRM SURVEILLANCE REQUIREMENTS OPERATION TRM 3.2 PROTECTIVE INSTRUMENT SYSTEMS TRM 4.2 PROTECTIVE INSTRUMENT SYSTEMS Applicability: Applicability:
Applies to the operational status Applies to the surveillance of the plant instrumentation requirements of the systems which initiate and instrumentation systems which control a protective function. initiate and control a protective function.
Objective: Objective:
To assure the operability of To verify the operability of protective instrumentation protective instrumentation systems. systems.
Specification: Specification:
A. Emergency Core Cooling System A. Emergency Core Cooling System When the system(s) it initiates Instrumentation and logic or controls is required in systems shall be functionally accordance with Specification tested and calibrated as 3.5, the instrumentation which indicated in Table TRM 4.2.1.
initiates the emergency .core cooling system(s)shall be operable in accordance with Table TRM 3.2.1.
B. Primary Containment Isolation B. Primary Containment Isolation When primary containment Instrumentation and logic integrity is required, in systems shall be functionally accordance with tested and calibrated as Specification 3.7, the indicated in Table TRM 4.2.2.
instrumentation that initiates primary containment isolation shall be operable in accordance with Table TRM 3.2.2.
C. Reactor Building Ventilation C. Reactor Building Ventilation Isolation and Standby Gas Isolation and Standby Gas Treatment System Initiation Treatment System Initiation The instrumentation that Instrumentation and logic initiates the isolation of systems shall be functionally the reactor building tested and calibrated as ventilation system and the indicated in Table TRM 4.2.3.
actuation of the standby gas treatment system shall be operable in accordance with Table TRM 3.2.3.
,VYNPS TRM TRM 3.2 TRM LIMITING CONDITIONS FOR TRM 4.2 TRM SURVEILLANCE REQUIREMENTS OPERATION TRM 3.2 PROTECTIVE INSTRUMENT SYSTEMS TRM 4.2 PROTECTIVE INSTRUMENT SYSTEMS E. Control Rod Block Actuation E. Control Rod Block Actuation During reactor power Instrumentation and logic operation the instrumentation systems shall be functionally that initiates control rod tested and calibrated as block shall be operable indicated in Table TRM 4.2.5.
in accordance with Table TRM 3.2.5.
G. Post-Accident Instrumentation G. Post-Accident Instrumentation During reactor power The post-accident operation, the instrumentation shall be instrumentation that displays functionally tested and information in the Control calibrated in accordance with Room for the operator to Table TRM 4.2.6.
monitor and assess the systems used during and following a postulated accident' or abnormal operating condition shall be operable in accordance with Table TRM 3.2.6.
L. Reactor Core Isolation L. Reactor Core Isolation Coolinq System Actuation Cooling System Actuation When the Reactor Core Instrumentation and Logic Isolation Cooling System is Systems shall be required in accordance with functionally tested and Specification 3.5.G, the calibrated as indicated in instrumentation which Table TRM 4.2.9.
initiates actuation of this system shall be operable in accordance with Table TRM 3.2.9.
VYNPS TRM TABLE TRIn 3.2.1t EMERGENCY CORE COOLING SYSTEM ACTUATION INSTRUMENTATION High Pressure Coolant Injection System Minimum Number of Required ACTION When Operable Instrument Minimum Conditions Channels per Trip For Operation-System Trip Function Trip Level Setting Are Not Satisfied 1 (Note 3) Bus Power Monitor (23A-K41) Note 5 NOTES:
- 3. One trip system with initiating instrumentation arranged in a one-out-of-two taken twice logic.
- 5. If the minimum number of operable channels are not available, the system is considered inoperable and the requirements of Technical Specification 3.5 apply.
Automatic Depressurization Minimum Number of Required ACTION When Operable Instrument Minimum Conditions Channels per Trip For Operation System (Note 4) Trip Function Trip Level Setting Are Not Satisfied 1 Bus Power Monitor (2E-KlA/B) Note 6 NOTES:
- 4. One trip system with initiating instrumentation arranged in a one-out-of-two logic.
- 6. Any one of the two trip systems will initiate ADS. If the minimum number of operable channels in one trip system is not available, the requirements of Technical Specification 3.5.F.2 and 3.5.F.3 shall apply.
If the minimum number of operable channels is not available in both trip systems, Technical Specification 3.5.F.3 shall apply.
VYNPS TRM TABLE TRM 3.2.2 HIGH PRESSURE COOLANT INJECTION SYSTEM ISOLATION INSTRUMENTATION Minimum Number of Required ACTION When Operable Instrument Minimum Conditions Channels per Trip For Operation Are System Trip Function Trip Level Setting Not Satisfied Bus Power Monitor (23A-K38)
REACTOR CORE ISOLATION COOLING SYSTEM ISOLATION INSTRUMENTATION Minimum Number of Required ACTION When Operable Instrument Minimum Conditions Channels per Trip For Operation Are System Trip Function Trip Level Setting Not Satisfied 1 Bus Power Monitor (13A-K33) Note 3 NOTES:
- 3. Close isolation valves in system and comply with Technical Specification 3.5.
VYNPS TRM TABLE TRM 3.2.3 REACTOR BUILDING VENTILATION ISOLATION & STANDBY GAS TREATMENT SYSTEM INITIATION Minimum Number of Required ACTION When Operable Instrument Minimum Conditions Channels per Trip For Operation System Trip Function Trip Setting Are Not Satisfied 1 Logic Bus Power Monitor Note 1 (16A-K52/53)
NOTES:
- 1. If the minimum number of operable instrument channels is not available in either trip system, the reactor building ventilation system shall be isolated and the standby gas treatment system operated until the instrumentation is repaired.
VYNPS TRM TABLE TRM 3.2.5 CONTROL ROD BLOCK INSTRUMENTATION Modes in Which Function Must be Operable Required Trip Function Refuel"' Startup Run Trip Setting Channels Source Range Monitor 2 a. Upscale (2) (7-40(A-D)) X X <5 x 105 cps(1 2 b. Detector Not Fully Inserted X X (7-11(A-D) (LS-4))
Intermediate Range Monitor (Notes 2 a. Upscale (7-41(A-F)) X X <108/125 Full Scale 1,10) 2 b. Downscale(4) X X >5/125 Full Scale 2 (7-41(A-F))
- c. Detector Not Fully Inserted X X (7-11(E,F,G,H,J,K) (LS-4))
Avg. Power Range Monitor (APRM A-F) 2 a. Upscale (Flow Bias) X Two loop operation: (5)
S*0.33W+45.3% power for 0%<W*30.9% flow S:I.07W+22.4% power for 30.9%<W*66.7% flow S*0.55W+57.1% power for 66.7%<W*99.0% flow maximum of 108% power for W>99.0% flow Single loop operation: (5 S*0.33W+41.1% power for 0%<W*39.1% flow S*1.07W+12.2% power for 39.1%<W*61.7% flow S*0.55W+44.3% power for 61.7%<W*122.3% flow maximum of 108% power for W>122.3% flow
- b. Downscale X >2/125 Full Scale (Notes 1 (per Scram Discharge Volume X X X <12 Gallons 10,11) volume) (LT-3-231A/G (Sl))
VYNPS TRM TABLE TRM 3.2.5 NOTES
- 1. There shall be two operable or tripped trip systems for each function in the required operating mode. If the minimum number of operable instruments are not available for one of the two trip systems, this condition may exist for up to seven days provided that during the time the operable system is functionally tested immediately and daily thereafter; if the condition lasts longer than seven days, the system shall be tripped. If the minimum number of instrument channels are not available for both trip systems, the systems shall be tripped.
- 2. One of these trips may be bypassed. The SRM function may be bypassed in the higher IRM ranges when the IRM upscale rod block is operable.
- 3. This function may be bypassed when count rate is >100 cps or when all IRM range switches are above Position 2.
- 4. IRM downscale may be bypassed when it is on its lowest scale.
- 5. The APRM - Upscale (Flow Bias) Trip Setting is a nominal value.
- 6. With any control rod withdrawn from a core cell containing one or more fuel assemblies.
- 10. When a channel is placed in an inoperable status solely for performance of required surveillances, entry into associated Limiting Conditions for Operation and required action notes may be delayed for up to 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> provided the associated Trip Function maintains Control Rod Block initiation capability.
- 11. A. With the number of operable channels one less than required by the minimum operable channels per trip function requirement, place the inoperable channel in the tripped condition within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
B. With the number of operable channels two less than required by the minimum operable channels per trip function requirement, place the Trip System in the tripped condition within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.
VYNPS TRM TABLE TRM 3.2.6 POST-ACCIDENT INSTRUMENTATION Minimum Number of Operable Instrument Channels (Note 5) Parameter Type of Indication Instrument Range l/valve Safety Valve Position From Meter ZI-2-1C Closed - Open Acoustic Monitor NOTES:
- 5. If safety valve position from the acoustic monitor is unavailable, safety valve position can alternatively be determined from safety valve discharge temperature or drywell pressure indication.
VYNPS TRM TABLE TRM 3.2.9 REACTOR CORE ISOLATION COOLING SYSTEM ACTUATION INSTRUMENTATION Minimum Number of Required ACTION When Operable Instrument Minimum Conditions Channels per Trip For Operation System Trip Function Trip Level Setting Are Not Satisfied 1 Bus Power Monitor (13A-K36) Note 4 NOTES:
- 4. If the minimum number of operable channels are not available, the system is considered inoperable and the requirements of Technical Specification 3.5 apply.
VYNPS TRM TABLE TRM 4.2.1 MINIMUM TEST AND CALIBRATION FREQUENCIES EMERGENCY CORE COOLING ACTUATION INSTRUMENTATION High Pressure Coolant Injection System Trip Function Functional Test(8) Calibration(8) Instrument Check Bus Power Monitor (Note 1) None Once each day Automatic Depressurization System Trip Function Functional Test(8) Calibration(8) Instrument Check Bus Power Monitor (Note 1) None Once Each Day Notes:
- 1. Initially once per month; thereafter, a longer interval as determined by test results on this type of instrumentation.
- 8. Functional tests and calibrations are not required when systems are not required to be operable.
VYNPS TRM TABLE TRM 4.2.2 MINIMUM TEST AND CALIBRATION FREQUENCIES HIGH PRESSURE COOLANT INJECTION SYSTEM ISOLATION INSTRUMENTATION Trip Function Functional Test(8) Calibration(8) Instrument Check Bus Power Monitor (Note 1) None Once each day REACTOR CORE ISOLATION COOLING SYSTEM ISOLATION INSTRUMENTATION Trip Function Functional Test(8) Calibration(8) Instrument Check Bus Power Monitor (Note 1) None Once each day Notes:
- 1. Initially once per month; thereafter, a longer interval as determined by test results on this type of instrumentation.
- 8. Functional tests and calibrations are not required when systems are not required to be operable.
VYNPS TRM TABLE TRM 4.2.3 MINIMUM TEST AND CALIBRATION FREQUENCIES REACTOR BUILDING VENTILATION AND STANDBY GAS TREATMENT SYSTEM ISOLATION Trip Function Functional Test(8) Calibration(B) Instrument Check Logic Bus Power Monitor (Note 1) None Once Each Day NOTES:
1 . Initially once per month; thereafter, a longer interval as determined by test results on this type of instrumentation.
- 8. Functional tests and calibrations are not required when systems are not required to be operable.
VYNPS TRM TABLE TRM 4.2.5 MINIMUM TEST AND CALIBRATION FREQUENCIES CONTROL ROD BLOCK INSTRUMENTATION Trip Function Functional Test Calibration Source Range Monitor'6)
- a. Upscale(4) Within 31 Days Before Entering STARTUP/HOT STANDBY(7) and Once Per Operating Every 31 Days During STARTUP/HOT STANDBY, Every 31 Days Cycle(7' During Refueling
- b. Detector Not Fully Inserted Within 31 Days Before Entering STARTUP/HOT STANDBY(7) and N/A Every 31 Days During STARTUP/HOT STANDBY, Every 31 Days During Refueling Intermediate Range Monitor(6)
- a. Upscale(4) Within 31 Days Before Entering STARTUP/HOT STANDBYM and Once Per Operating Every 31 Days During STARTUP/HOT STANDBY, Every 31 Days Cycle(7)
During Refueling
- b. Downscale(4) Within 31 Days Before Entering STARTUP/HOT STANDBY(7) and Once Per Operating Every 31 Days During STARTUP/HOT STANDBY, Every 31 Days Cycle(7)
During Refueling
- c. Detector Not Fully Inserted Within 31 Days Before Entering STARTUP/HOT STANDBY( 7 ) and N/A Every 31 Days During STARTUP/HOT STANDBY, Every 31 Days During Refueling Average Power Range Monitor
- a. Upscale (Flow Bias) Every Three Months(Note 4) Every Three Months
- b. Downscale Every Three Months(Note 4) Every Three Months High Water Level in Scram Discharge Every Three Months Refueling Outage Volume VY TRM Revision 25 3.2-13
VYNPS TRM TABLE TRM 4.2 5 NOTES
- 4. This instrumentation is excepted from functional test definition. The functional test will consist of injecting a simulated electrical signal into the measurement channel.
- 6. When a trip function is required to be operable, an instrument check shall be performed on the instrumentation once per day.
- 7. Not required to be performed when entering STARTUP/HOT STANDBY MODE from RUN MODE until 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> after entering STARTUP/HOT STANDBY MODE.
VYNPS TRM TABLE TRM 4.2.6 CALIBRATION REQUIREMENTS POST-ACCIDENT INSTRUMRNTATION Parameter Calibration Instrument Check Safety Valve Position Every Refueling Outage (Note 9) Once Each Day (a Functional Test to be performed quarterly)
NOTES:
- 9. The thermocouples associated with safety valve position, that may be used for back-up position indication, shall be verified to be operable every operating cycle.
VYNPS TRM TABLE TRM 4.2.9 MINIMUM TEST AND CALIBRATION FREQUENCIES REACTOR CORE ISOLATION COOLING SYSTEM ACTUATION INSTRUMENTATION Trip Function Functional Test(8) Calibration(8) Instrument Check Bus Power Monitor (Note 1) None Once each day NOTES:
- 1. Initially once per month; thereafter, a longer interval as determined by test results on this type of instrumentation.
- 8. Functional tests and calibrations are not required when systems are not required to be operable.
TRM 3.2 PROTECTIVE INSTRUMENTATION The trip logic for the nuclear instrumentation control rod block logic is 1 out of n; i.e., any trip on one of the six APRMs, six IRMs or four SRMs will result in a rod block. The minimum instrument channel requirements for the IRMs may be reduced by one for a short period of time to allow for maintenance, testing or calibration.
The purpose of the APRM rod block function is to avoid conditions that would require Reactor Protection System action if allowed to proceed. The APRM upscale rod block alarm setting is selected to initiate a rod block before the APRM high neutron flux scram setting is reached. The APRM upscale rod block trip setpoint is varied as a function of reactor recirculation flow. This provides an effective rod block if core average power is increased above the power level specified at any flow rate.
The APRM - Upscale (Flow Bias) control rod block Trip Function is not credited in the safety analysis. The Trip Setting specified in Table TRM 3.2.5 for the APRM - Upscale (Flow Bias) Trip Function is a nominal value (Table TRM 3.2.5 Footnote (5)) and not an operability limit. A "nominal" trip setting is an approximate value within a defined calibration tolerance. Because the instrumentation does not provide a safety function, uncertainty relationships associated with analytical limits do not exist. Nominal trip setpoints have corresponding administrative limits (as-found and as-left tolerances) which can render the field setting above or below the nominal value. These administrative limits are typically based on equipment performance and are required by calibration procedures/data sheets. The nominal value Trip Setting is selected to ensure a control rod block is initiated before the reactor protection system APRM High Flux (Flow Bias) trip setpoint is reached.
As with the reactor protection system APRM High Flux (Flow Bias) Trip Setting, the APRM - Upscale (Flow Bias) control rod block Trip Setting is reduced for single recirculation loop operation to account for the difference between the single loop and two loop drive flow at the same core flow. The terms for the Trip Setting of the APRM - Upscale (Flow Bias) Trip Function are defined as follows:
S = Nominal setpoint in percent of rated thermal power (1,912 MWt).
W= percent of rated two loop drive flow where 100% rated drive flow is that flow equivalent to 48 x 106 lbs/hr core flow.
Since the purpose of the APRM - Upscale (Flow Bias) Trip Function is to avoid conditions that would require reactor protection system action if allowed to proceed, the APRM - Upscale control rod block Trip Function is required to be operable during reactor power operation.
TRM 3.2 PROTECTIVE INSTRUMENTATION (Continued)
For single recirculation loop operation, the APRM rod block trip setting is reduced in accordance with the analysis presented in NEDO-30060, I February 1983. This adjustment accounts for the difference between the single loop and two-loop drive flow at the same core flow. The single loop equations are based on a bounding (maximum) difference of 8%
between two loop and single loop drive flow at the same core flow.
The IRM rod block function provides local as well as gross core protection.
The scaling arrangement, is such that trip setting is less than a factor of 10 above the indicated level. Analysis of the worst-case accident results in rod block action before MCPR approaches the fuel cladding integrity safety limit.
A downscale indication on an APRM or IRM is an indication the instrument has failed or the instrument is not sensitive enough. In either case, the instrument will not respond to changes in control rod motion and thus control rod motion is prevented.
Post-Accident Instrumentation TRM Specification 3.2.G requires that the post-accident monitoring (PAM) instrumentation of Table TRM 3.2.6 be operable during reactor power operation. PAM instrumentation is not required to be operable during shutdown and refueling conditions when the likelihood of an event that would require PAM instrumentation is extremely low. The primary purpose of the PAM instrumentation is to display plant variables that provide information required by the control room operators during accident situations. The operability of the PAM instrumentation ensures that there is sufficient information available on selected plant parameters to monitor and assess plant status and behavior following an accident.
If Table TRM 3.2.6 minimum number of operable instruments for safety valve position from acoustic monitors is not met, a note provides alternate indication to assist the operator in determining safety valve position. One of these alternate indications is drywell pressure. If the alternate instrumentation is not available, the loss of drywell pressure indication will place the plant in a restrictive Technical Speciification LCO. Thus, no instruction is provided for follow-up actions if both the primary and backup instrumentation is not available, as plant operation will be restricted by the Technical Specifications.
VYNPS TRM TRM 3.5 TRM LIMITING CONDITIONS FOR TRM 4.5 TRM SURVEILLANCE REQUIREMENTS OPERATION TRM 3.5 CORE AND CONTAINMENT COOLING TRM 4.5 CORE AND CONTAINMENT COOLING SYSTEMS SYSTEMS Applicability: Applicability:
Applies to the operational status Applied to periodic Testing of of the Emergency the emergency cooling Cooling Subsystems.
subsystems.
Objective:
Objective:
To assure adequate cooling capability for heat removal in To verify the operability of the the event of a loss-of-coolant core containment cooling accident or isolation from the subsystems.
normal reactor heat sink.
Specification:
C. Residual Heat Removal (RHR)
Service Water Svstem Surveillance of the RHR Service Water System shall be performed as follows:
- 1. RHR Service Water Subsystem testing:
Each RHR service water pump shall deliver at least 2700 gpm and a pressure of at least 105.3 psia shall be maintained at the RHR heat exchanger service water outlet when the corresponding pairs of RHR service water pumps and station service water pumps are operating.
D. Station Service Water and Alternate Cooling Tower Systems Surveillance of the Station Service Water and Alternate Cooling Tower Systems shall be performed as follows:
- 1. Each pump shall deliver at least 2700 gpm against a TDH of 250 feet.
VYNPS TRM TRM 3.6 TRM LIMITING CONDITIONS FOR TRM 4.6 TRM SURVEILLANCE REQUIREMENTS OPERATION TRM 3.6 REACTOR COOLANT SYSTEM TRM 4.6 REACTOR COOLANT SYSTEM Applicability: Applicability:
Applies to the operating status Applies to the periodic of the reactor coolant system. examination and testing requirements for the reactor coolant system.
Objective: Objective:
To assure the integrity and safe To determine the condition of the operation of the reactor coolant reactor coolant system and the system. operation of the safety devices related to it.
Specification: Specification:
B. Coolant Chemistry B. Coolant Chemistry
- 1. Intentionally blank. 1. Intentionally blank.
- 2. The reactor coolant water 2. During startups and at shall'not exceed the steaming rates below following limits with 100,000 pounds per hour, steaming rates less than a sample of reactor 100,000 pounds per hour coolant shall be taken except as specified in every four hours and TRM Specification analyzed for conductivity 3.6.B.3: and chloride content.
Conductivity 5jimho/cm Chloride ion 0.1 ppm
- 3. For reactor startups and 3. a. With steaming rates during the period when greater than or Noble Metals are injected equal to into the reactor coolant, 100,000 pounds per the maximum value for hour, a reactor conductivity shall not coolant sample shall exceed 10 umho/cm and the be taken at least maximum value for every 96 hours0.00111 days <br />0.0267 hours <br />1.587302e-4 weeks <br />3.6528e-5 months <br /> and chloride ion when the continuous concentration shall not conductivity exceed 0.1 ppm, in the monitors indicate reactor coolant water for abnormal the first 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> after conductivity (other placing the reactor in than short-term the power operating spikes), and condition. analyzed for conductivity and
- 4. Except as specified in chloride ion TRM Specification 3.6.B.3 content.
above, the reactor coolant water shall not exceed the following VY TRM Revision 14 3.6-1
VYNPS TRM 3.6 TRM LIMITING CONDITIONS FOR 4.6 TRM SURVEILLANCE REQUIREMENTS OPERATION TRM 3.6 REACTOR COOLANT SYSTEM TRM 4.6 REACTOR COOLANT SYSTEM limits with steaming b. When the continuous rates greater than or conductivity monitor equal to 100,000 pounds is inoperable, a per hour. reactor coolant sample shall be taken Conductivity 5 ýthmo/cm every four hours and Chloride ion 0.5 ppm analyzed for conductivity and
- 5. If TRM Specification chloride ion content.
3.6.B is not met, an orderly shutdown shall be initiated and the reactor shall be in the cold shutdown condition within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
G. Single Loop Operation
- 1. The reactor may be started and operated or operation may continue with a single recirculation loop provided that:
- a. The designated adjustments for rod block trip settings (Specification 2.1.B.1, and Table 3.2.5) are initiated within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />. During the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />, either these adjustments must be completed or the reactor brought to Hot Shutdown.
TRM 3.6 and 4.6 Reactor Coolant System B. Coolant Chemistry Materials in the primary system are primarily 304 stainless steel and Zircaloy. The reactor water chemistry limits are established to prevent damage to these materials. The limit placed on chloride concentration is to prevent stress corrosion cracking of the stainless steel.
When conductivity is in its proper normal range (approximately 10 !Imho/cm during reactor startup and 5 ýimho/cm during power operation), pH and chloride and other impurities affecting conductivity must also be within their normal range. When and if conductivity becomes abnormal, then chloride measurements are made to determine whether or not they are also out of their normal operating values. This would not necessarily be the case. Conductivity could be high due to the presence of a neutral salt, e.g., Na2SO4, which would not have an effect on pH or chloride. In such a case, high conductivity alone is not a cause for shutdown. In some types of water-cooled reactors, conductivities are in fact high due to purposeful addition of additives. In the case of BWRs, however, no additives are used and where neutral pH is maintained, conductivity provides a very good measure of the quality of the reactor water.
Significant changes therein provide the operator with a warning mechanism so he can investigate and remedy the condition causing the change before limiting conditions, with respect to variables affecting the boundaries of the reactor coolant, are exceeded. Methods available to the operator for correcting the off-standard condition include operation of the reactor cleanup system reducing the input of impurities and placing the reactor in the cold shutdown condition.
The major benefit of cold shutdown is to reduce the temperature dependent corrosion rates and provide time for the cleanup system to reestablish the purity of the reactor coolant. During startup periods, which are in the category of less than 100,000 pounds per hour, conductivity may exceed 5 pmho/cm because of the initial evolution of gases and the initial addition of dissolved metals.
During this period of time when the conductivity exceeds 5 ýtmho (other than short term spikes), samples will be taken to assure the chloride concentration is less than 0.1 ppm.
The NobleChem application process increases the conductivity of the reactor water due to the ionic characteristics of the injected compounds of platinum and rhodium. During the application process, the major species that contribute to increased conductivity are sodium, nitrate/nitrite and hydroxide. These reaction by-products are expected to cause reactor coolant conductivity to approach 10umho/cm.
Studies and observations have indicated that the relatively low temperature, the limited time frame of application and the non-aggressive ionic species resulting from noble metal injection have little threat of any enhanced crack initiation in the resulting high conductivity environment.
TRM 3.6 and 4.6 Reactor Coolant System B. Coolant Chemistry (Continued)
The conductivity of the reactor coolant is continuously monitored.
The samples of the coolant which are taken every 96 hours0.00111 days <br />0.0267 hours <br />1.587302e-4 weeks <br />3.6528e-5 months <br /> will serve as a reference for calibration of these monitors and is considered adequate to assure accurate readings of the monitors. If conductivity is within its normal range, chlorides and other impurities will also be within their normal ranges. The reactor coolant samples will also be used to determine the chlorides. Therefore, the sampling frequency is considered adequate to detect long-term changes in the chloride ion content.
The conductivity of the feedwater is continuously monitored and alarm set points, consistent with Regulatory requirements given in Regulatory Guide 1.56, "Maintenance of Water Purity in Boiling Water Reactors," have been determined. The results from the conductivity monitors on the feedwater can be correlated with the results from the conductivity monitors on the reactor coolant water to indicate demineralizer breakthrough and subsequent conductivity levels in the reactor vessel water.
VYNPS TRM TRM 3.7 TRM LIMITING CONDITIONS FOR TRM 4.7 TRM SURVEILLANCE REQUIREMENTS OPERATION TRM 3.7 STATION CONTAINMENT SYSTEMS TRM 4.7 STATION CONTAINMENT SYSTEMS Applicability: Applicability:
Applies to the operating status Applies to the primary and of the primary and secondary secondary containment system containment systems. integrity.
Objective: Objective:
To assure the integrity of the To verify the integrity of the primary and secondary containment primary and secondary systems. containments.
Specification:
D. Primary Containment Isolation Valves
- 1. Surveillance of the primary containment isolation valves should be performed as follows:
- a. The operable isolation valves that are power operated and automatically initiated shall be tested for automatic initiation and the closure times specified in Table TRM 4.7.2 at least once per operating cycle.
VYNPS TRM TABLE TRM 4.7.2 POWER OPERATED PRIMARY CONTAINMENT ISOLATION VALVES WITH GROUP ISOLATION SIGNALS Maximum Isolation Operating Normal Group (1) Valve Identification Time (sec) Position Main Steam Line Isolation (2-80A-D 5 (Note 2) Open 1 & 2-86A-D)
Main Steam Line Drain (2-74, 2-77) 35 Closed 1
Recirculation Loop Sample Line 5 Closed (2-39, 2-40) 2 (A)
RHR Discharge to Radwaste (10-66) 25 Closed 2 (A)
Drywell Floor Drain (20-82, 20-83) 20 Open 2 (A)
Drywell Equipment Drain (20-94, 20 Open 20-95) 2 (A)
TIP Probe (BV-7-1, 2, 3) 5 Closed 2 (A)
TIP PURGE (SOV-7-107) 5 Open 2 (B)
RHR Return to Suppression Pool 70 Closed (10-39A, B) 2 (B)
RHR Return to Suppression Pool 120 Closed (10-34A, B) 2 (B)
RHR Drywell Spray (10-26A, B & 70 Closed 10-31A, B) 2 (B)
RHR Suppression Chamber Spray 45 Closed (10-38A, B) 3 Drywell Air Purge Inlet (16-19-9) 10 Closed 3
Drywell Air Purge Inlet (16-19-8) 10 Closed 3
Drywell Purge & Vent Outlet 10 Closed 3 (16-19-7A)
Drywell Purge & Vent Outlet Bypass 10 Closed (16-19-6A) 3 Drywell & Suppression Chamber Main 10 Closed Exhaust (16-19-7) 3 Suppression Chamber Purge Supply 10 Closed 3 (16-19-10)
Suppression Chamber Purge & Vent 10 Closed Outlet (16-19-7B)
VYNPS TRM TABLE TRM 4.7.2 (Cont'd)
POWER OPERATED PRIMARY CONTAINMENT ISOLATION VALVES WITH GROUP ISOLATION SIGNALS Maximum Isolation Operating Normal Group (1) Valve Identification Time (sec) Position 3 Suppression Chamber Purge & Vent 10 Open Outlet Bypass (16-19-6B) 3 Exhaust to Standby Gas Treatment 10 Open System (16-19-6) 3 Containment Purge Supply (16-19-23) 10 Closed 3 Containment Makeup Supply (16-20-22A) 5 Closed 3 Containment Makeup Supply (16-20-20, 5 Open 16-20-22B) 3 Containment Air Sampling (VG 23, 5 Open VG 26, 109-76A&B) 3 Containment Air Compressor Suction 20 Open (72-38A, B) 3 Containment Air Dilution (VG-22A, B) 20 Closed 3 Containment Air Dilution (VG-9A, B; 5 Closed NG-lIA, B; NG-12A, B; NG-13A, B) 4 RHR Shutdown Cooling Supply (10-18, 28 Closed 10-17) 5 Reactor Cleanup System (12-15, 12-18) 25 Open 6 HPCI (23-15, 23-16) 55 Open 6 RCIC (13-15, 13-16) 20 Open VY TRM Revision 18 3.7ý-3
VYNPS TRM TABLE TRM 4.7.2 NOTES
- 1. Isolation signals are as follows:
Group 1: The valves in Group 1 are closed upon any one of the following conditions:
- 1. Low-low reactor water level
- 2. High main steam line flow
- 3. High main steam line tunnel temperature
- 4. Low main steam line pressure (run mode only)
- 5. Condenser low vacuum Group 2(A): The valves in Group 2(A) are closed upon any one of the following conditions:
- 1. Low reactor water level
- 2. High drywell pressure Group 2(B) : The valves in Group 2(B) are closed upon any one of the following conditions:
- 1. Low-low reactor water level with low reactor pressure
- 2. High drywell pressure Group 3: The valves in Group 3 are closed upon any one of the following conditions:
- 1. Low reactor water level
- 2. High drywell pressure
- 3. High/low radiation - reactor building ventilation exhaust plenum or refueling floor Group 4: The valves in Group 4 are closed upon any one of the following conditions:
- 1. Low reactor water level
- 2. High drywell pressure
- 3. High reactor pressure Group 5: The valves in Group 5 are closed upon low reactor water level.
Group 6: The valves in Group 6 are closed upon any signal representing a steam line break in the HPCI system's or RCIC system's respective steam line. The signals indicating a steam line break for the respective steam line are as follows:
- 1. High steam line space temperature
- 2. High steam line flow
- 3. Low steam line pressure
- 4. High temperature in the main steam line tunnel (30 minute delay for the HPCI and the RCIC)
- 2. The closure time shall not be less than 3 seconds.
VYNPS TRM TRM 3.10 TRM LIMITING CONDITIONS FOR TRM 4.10 TRM SURVEILLANCE REQUIREMENTS OPERATION TRM 3.10 AUXILIARY ELECTRICAL POWER TRM 4.10 AUXILIARY ELECTRICAL POWER SYSTEMS SYSTEMS Applicability: Applicability:
Applies to the auxiliary Applies to the periodic testing electrical power systems. requirements of the auxiliary electrical power systems.
Objective:
Objective:
To assure an adequate supply of electrical power for operation To verify the operability of the of those systems required for auxiliary electrical power reactor safety. systems.
Specification:
B. Operation With Inoperable Components Whenever the reactor is in Run Mode or Startup Mode with the reactor not in the Cold Condition, the requirements of Technical Specification 3.10.A shall be met except:
- 2. Batteries
- d. From and after the date that the AS-2 125 Volt battery system is made or found to be inoperable for any reason, continued reactor operation is permissible provided a fire watch is established to inspect the cable vault a minimum of every two hours.
VYNPS TRM TRM 3.13 TRM LIMITING CONDITIONS FOR TRM 4.13TRM SURVEILLANCE REQUIREMENTS OPERATION TRM 3.13 FIRE PROTECTION SYSTEM TRM 4.13 FIRE PROTECTION SYSTEM Applicability: Applicability:
Applies to the operational Applies to the surveillance status of the fire protection requirements of the fire systems. protection systems.
Objective: Objective:
To assure adequate capability to To verify the operability of the detect and suppress a fire which fire protection systems.
could affect the safe shutdown of the reactor.
Specification: Specification:
A. Fire Detection A. Fire Detection
- 1. Except as specified in 1. Each of the sensors TRM Specification specified in TRM 3.13.A.2 below, the TRM 3.13.A.1 and their minimum number of fire associated instruments detection sensors and including the their associated supervisory circuitry instrument for each shall be demonstrated location shall be operable at least once operable in accordance per 24 months.
with Table TRM 3.13.A.1, whenever the equipment it protects is required to be operable.
- 2. From and after the date that less than the minimum number of sensors or their associated instruments are found to be operable, a fire watch shall be established to inspect the location with the inoperable sensor or instruments at least once every hour.
VYNPS TRM TRM 3.13 TRM LIMITING CONDITIONS FOR TRM 4.13 TRM SURVEILLANCE REQUIREMENTS OPERATION B. Vital Fire Suppression Water B. Vital Fire Suppression Water System System
- 1. Except as specified in 1. The Vital Fire TRM Specification Suppression Water System TRM 3.13.B.2 and shall be demonstrated TRM 3.13.B.3 below, the operable:
Vital Fire Suppression Water System shall be a. At least once per operable with: month by starting each pump and
- a. Both fire pumps operating it for operable and lined 15 minutes.
up to the fire suppression loop. b. At least once per 6 months by verifying
- b. Water available from each valve in the the Connecticut flow path is in its River. correct position.
(For electrically
- c. An operable flow supervised valves, path capable of adequate taking suction from verification is a the Connecticut visual check of River and electrical transferring the indication. Also water through the see B.l.e.3) distribution piping with operable c. At least once per sectionalizing year by performance control or isolation of a system flush of valves to the yard the yard fire loop.
hydrant curb valves and the hose station d. At least once per isolation valves. 12 months by cycling each testable valve
- 2. From and after the date in the flow path that less than the above through at least one required equipment is complete cycle of operable, restore the full travel.
component to operable status within 7 days or e. At least once per initiate an Operability 18 months:
Determination (OD) to be approved within 30 days 1) By performing a if the equipment is not system first restored to functional test operable status. The OD by simulating shall outline the plans sequential and procedures to be automatic start used to provide for the of the fire loss of redundancy in pumps as this system. applicable.'to maintain the Vital Fire Suppression Water System pressure of at least 125 psig.
VYNPS TRM TRM 3.13 TRM LIMITING CONDITIONS FOR TRM 4.13 TRM SURVEILLANCE REQUIREMENTS OPERATION
- 3. With both fire pumps 2) By verifying inoperable, OR with a that each pump total loss of the supply will develop a water from the flow of at Connecticut River, OR a least 2500 gpm complete loss of a flow at a discharge path to all fire pressure of at suppression systems, least 115 psig THEN; corrected for river water
- a. Establish a backup level.
fire suppression water system within 3) By cycling and 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. verifying the correct
- b. If a. above cannot position of be fulfilled, place each valve in the reactor in hot the flow path standby within the that is not next six (6) hours testable during and in cold shutdown plant operation with the following through at thirty (30) hours. least one complete cycle of full travel.
- f. At least once per 3 years by performing a flow test in accordance with Chapter 5, Section II, of the Fire Protection Handbook, 14th Edition, published by the National Fire Protection Association.
- 2. The fire pump diesel engine shall be demonstrated OPERABLE:
- a. At least once per month by verifying;
- 1) The fuel storage tank contains at least 150 gallons of fuel, and
- 2) The diesel starts from ambient conditions and operates for at least 20 minutes.
VYNPS TRM TRM 3.13 TRM LIMITING CONDITIONS FOR TRM 4.13 TRM SURVEILLANCE REQUIREMENTS OPERATION
- b. At least once per quarter by verifying that a sample of diesel fuel from the fuel storage tank is within the acceptable limits specified in Table 1 of ASTM D975-02 with respect to viscosity, water content, and sediment.
- c. At least once per 18 months by verifying the diesel starts from ambient conditions on the auto-start signal and operates for
> 20 minutes while loaded with the fire pump.
- 3. The fire pump diesel starting 24-volt battery bank and charger shall be demonstrated OPERABLE:
- a. At least once per week by verifying that:
- 1) The electrolyte level of each battery is above the plates, and
- 2) The overall battery voltage is > 24 volts.
- b. At least once per quarter by verifying that the specific gravity is appropriate for continued service of the battery.
- c. At least once per 18 months by verifying that:
VYNPS TRM TRM 3.13 TRM LIMITING CONDITIONS FOR TRM 4.13 TRM SURVEILLANCE REQUIREMENTS OPERATION
- 1) The batteries, cell plates and battery racks show no visual indication of physical damage or abnormal deterioration, and
- 2) The battery-to-battery and terminal connections are clean, tight, free of corrosion and coated with anti-corrosion material.
C. Fire Hose Stations C. Fire Hose Stations
- 1. Except as specified in 1. Each fire hose station TRM 3.13.C.2 below, ýall shall be verified to be hose stations inside the operable:
Reactor Building, Turbine Building, and a. At least once per 6 those inside the months by visual Administration Building inspection of the which provided coverage station to assure of the Control Room all equipment is Building shall be available, except as operable whenever allowed by TRM equipment in the areas 4.13.C.l.f below.
protected by the fire hose stations is b. At least once per required to be operable. 18 months by removing the hose
- 2. With one or more of the for inspection and fire hose stations replacing degraded specified in coupling gaskets and TRM 3.13.C.1 above reracking.
inoperable, route an additional equivalent c. At least once per 24 capacity fire hose to months by the unprotected area(s) hydro-statically from an operable hose testing each outside station within one hour. hose at 250 lbs.
- d. At least once per 3 years by.
hydro-statically testing inside hose at 150 lbs.
VYNPS TRM TRM 3.13 TRM LIMITING CONDITIONS FOR TRM 4.13 TRM SURVEILLANCE REQUIREMENTS OPERATION
- e. At least once per 3 years, partially open hose station valves to verify valve operability and no blockage.
- f. At least once per 18 months by visual inspection of the station to assure all equipment is available for areas that are not testable during plant operation.
- 1. Except as specified in 1. The CO2 systems located Specification in the cable vault, east TRM 3.13.D.2, the CO2 and west switchgear systems located in the rooms, and diesel fire cable vault, east and pump day tank room shall west switchgear rooms, be demonstrated and diesel fire pump day operable.
tank room shall be operable, whenever a. At least once per 24 equipment in the area months by verifying protected by the system each CO 2 cylinder is required to be associated with the operable. cable vault and diesel fire pump day
- 2. From and after the date tank room CO2 systems that the CO 2 system in does not contain the cable vault or a less than 90% of its switchgear room is initial charge.
inoperable, within one hour a fire watch shall b. At least once per 18 be established to months by verifying inspect the location at that the system, least once every hour, including associated provided that the fire ventilation dampers, detection system is will actuate operable in accordance automatically to a with TRM 3.13.A. If the simulated actuation fire detection system is signal.
also inoperable, within one hour a continuous c. Deleted.
fire watch shall be established with backup d. At least once per fire suppression 7 days by verifying equipment. the CO2 storage tank associated with the switchgear rooms does not contain less than 50% level and a minimum pressure of 270 psig.
VYNPS TRM TRM 3.13 TRM LIMITING CONDITIONS FOR TRM 4.13 TRM SURVEILLANCE REQUIREMENTS OPERATION
- 3. From and after the date that the C0 2 system in the diesel fire pump day tank room is inoperable, within one hour a fire watch shall be established to inspect the location at least once every hour.
E. Vital Fire Barrier E. Vital Fire Barrier Penetration Fire Seals Penetration Fire Seals
- 1. Except as specified in 1. Vital fire barrier TRM Specification penetration seals shall TRM 3.13.E.2 below, be verified to be vital fire barrier functional by visual penetration seals inspection at least once protecting the Reactor every four operating Building, Control Room cycles (approximately Building, and Diesel 25% per operating cycle)
Generator Rooms shall be and following any intact. repair.
- 2. From and after the date a vital fire barrier penetration fire seal is not intact, within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> either a) establish a continuous fire watch on at least one side of the affected penetration, or b) IF an operable fire detection system is on at least one side of the affected penetration, THEN establish an hourly fire watch. The hourly fire watch will be established on at least one side of the affected penetration.
VYNPS TRM TRM 3.13 TRM LIMITING CONDITIONS FOR TRM 4.13 TRM SURVEILLANCE REQUIREMENTS OPERATION F. Sprinkler Systems F. Sprinkler Systems
- 1. Except as specified in TRM 1. Each of the sprinkler Specification TRM 3.13.F.2 systems specified in Table below, those sprinkler TRM 3.13.F.1 shall be systems listed in demonstrated operable:
Table TRM 3.13.F.1 shall be operable whenever equipment a. At least once per in the area protected by 12 months by cycling those sprinklers is required each testable valve in to be operable. the flow path through at least onecomplete cycle
- 2. From and after the date that of full travel.
one of the sprinkler systems specified in Table b. At least once per 6 TRM 3.13.F.1 is inoperable, months by verifying each a fire watch shall be valve in the flow path established within one hour is in its correct to inspect the location with position. (For the inoperable sprinkler electrically supervised system at least once every valves, adequate hour. verification is a visual check of electrical indication.)
- c. Perform the following:
- 1. Cycle each valve in the flow path that is not testable during plant operation through at least one complete cycle of full travel once per 18 months.
- 2. Visually inspect the sprinkler headers to verify their integrity once per 24 months.
- 3. Visually inspect each nozzle's spray area to verify that the spray pattern is not obstructed once per 24 months.
- 4. Verify that automatic valves actuate to their correct position from a test signal once per 18 months.
- d. At least once per 3 years by performing a flow test through each open head sprinkler header and verifying each open head sprinkler nozzle is unobstructed.
VYNPS TRM TRM 3.13 TRM LIMITING CONDITIONS FOR TRM 4.13 TRM SURVEILLANCE REQUIREMENTS OPERATION G. Foam Systems G. Foam Systems
- 1. Except as specified in 1. The foam system TRM Specification specified in TRM 3.13.G TRM 3.13.G.2 below, the shall be demonstrated Recirculation M.G. Set operable.
Foam System shall be operable with its foam a. At least once per concentrate tank full 12 months by cycling (150 gallo~ns) whenever each testable valve the Recirculation M.G. in the flow path Sets are operating. through at least one complete cycle of
- 2. From and after the date full travel.
that the Recirculation M.G. Set Foam System is b. Perform the inoperable, a fire watch following:
shall be established to inspect the location at 1. Cycle each least once every hour; valve in the and a foam nozzle shall flow path that be brought to the is not testable Reactor Building during plant elevation containing the operation Recirculation M.G. through at Sets. A 150 gallon foam least one concentrate supply shall complete cycle be available on site. of full travel once per 18
- 3. Except as specified in months.
TRM Specification TRM 3.13.G.4 below, the 2. Visually Turbine Building Foam inspect the System shall be operable foam system and with its foam equipment to concentrate tank full verify (150 gallons). integrity once per 24 months.
- 4. From and after the date that the Turbine 3. Visually Building Foam System is inspect the inoperable a portable Recirculation foam nozzle shall be M.G. Set Foam brought to the Turbine System foam Building Foam System nozzle area to location. A 150 gallon verify that the foam concentrate supply spray pattern shall be available is not on-site. obstructed once per 24 months.
- 4. Foam concentrate samples shall be taken and analyzed for acceptability once per 18 months.
- c. Deleted.
VYNPS TRM TABLE TRM 3.13.A.1 FIRE DETECTION SENSORS Minimum No. of Sensors Required to Be Operable Sensor Location Heat Flame Smoke 1 . Cable Spreading Room & Station Battery Room - - 23
- 2. Switchgear Room (East) - - 10
- 3. Switchgear Room (West) - - 10
- 4. Diesel Generator Room (A) 3
- 5. Diesel Generator Room (B) 3
- 6. Intake Structure (Service Water) 1 1 1
- 7. Recirc Motor Generator Set Area 3 8 8.a Control Room Zone 1 (Control Room Ceiling) 14 8.b Control Room Zone 2 (Control Room Panels) 18 8.c Control Room Zone 3 (Control Room Panels) 25 8.d Control Room Zone 4 (Control Room Panels) 10 8.e Control Room Zone 5 (Exhaust & Supply 2 Ducts) 9.a Rx Bldg. Corner Rm NW 232 1 9.b Rx Bldg. Corner Rm NW 213 (RCIC) 1 9.c Rx Bldg. Corner Rm NE 232 1 9.d Rx Bldg. Corner Rm NE 213 1 9.e Rx Bldg. Corner Rm SE 232 1 9.f Rx Bldg. Corner Rm SE 213 1 9.g Rx Bldg. Corner Rm SW 232 1
- 10. HPCI Room 8 ii. Torus area 12 16
- 12. Rx Bldg. Cable Penetration Area 7
- 13. Refuel Floor 13
- 14. Diesel Oil Day Tank.Room (A) 13 1*
- 15. Diesel Oil Day Tank Room (B) 1* 1*
- 16. Turbine Loading Bay (vehicles) 3
- NOTE: The Diesel Day Tank Rooms require only one detector operable (1 flame or 1 smoke).
VYNPS TRM TABLE TRM 3.13.F.1 SPRINKLER SYSTEMS
- 1. Reactor Building Penetration Area Preaction System
- 2. Diesel Generator Room A System
- 3. Diesel Generator Room B System
- 4. Turbine Loading Bay System
TRM 3.13 & TRM 4.13 FIRE PROTECTION SYSTEMS On May 11, 1976, Vermont Yankee received a letter from the NRC requesting that an in-depth evaluation of the existing fire protection systems be performed using Branch Technical Position (BTP) APCSB 9.5-1 as a guide.
Concurrent with this evaluation a fire hazards analysis of the entire plant complex was required. In an effort to clarify the BTP an Appendix A was subsequently issued to specifically address operating plants.
Enclosed with this Appendix the NRC requested that proposed Technical Specifications on fire protection also be submitted. The subject section TRM 3.13/4.13 and the following specific bases are those specifications evolving from these efforts.
A. The smoke, heat and flame detectors provide the early warning fire detection capability necessary to detect problems in vital areas of the plant. Surveillance requirements assure these sensors and their associated instruments to be operable. When the equipment protected by the detectors is not required to be operable, specifications covering the sensors and instruments do not apply.
B,C, The Vital Fire Suppression Water System, CO 2 systems, sprinkler D,F, systems and foam systems specifications are provided to meet and pre-established levels of system operability in the event of a G fire. These systems provide the necessary protection to assure safe reactor shutdown. Periodic surveillance testing provides assurance that vital fire suppression systems are operable.
The east and west switchgear rooms low pressure CO 2 storage tank TRM Specification minimum level of 50% provides for sufficient CO2 quantity to achieve and maintain design concentration, in accordance with NFPA 12 (1993), in the east or west switchgear rooms. The TRM Specification minimum tank pressure of 270 psig will provide the minimum pressure to meet system design.
E. Vital fire barrier penetration fire seals are provided to assure that the fire resistance rating of barriers is not reduced by a penetration. Surveillance inspections shall be performed to insure that the integrity of these seals is maintained.
The diesel fire pump has a design consumption rate of 18 gallons of fuel per hour; therefore, 150 gallons provides for greater than 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> of operation. Additional fuel can be delivered in about one hour and additional fuel is on site. When the equipment protected by the fire protection systems is not required to be operable, the specifications governing the fire protection system do not apply.
The fire protection testing frequencies have been adjusted to utilize performance based testing. The goal is to achieve an availability factor of 99.0%. Based on this goal, the test frequencies may be increased up to the limits indicated, if the testing data supports the goal of a 99.0% availability factor. The Fire Protection Engineer will review test data to ensure that a 99.0% availability factor is met or exceeded and to recommend additional testing when this goal is not achieved.
VYNPS TRM TRM 6.0 ADMINISTRATIVE CONTROLS Administrative controls are the wriftten rules, orders, instructions, procedures, policies, practices, and the designation of authorities and responsibilities by the management to obtain assurance of safety and quality of operation and maintenance of a nuclear power reactor.
These controls shall be adhered to.
TRM 6.1 ORGANIZATION D. Conduct of operations of the plant will be in accordance with the following.
- 2. Minimum shift staffing on-site shall be in accordance with Table TRM 6.1.1.
- 3. A dedicated, licensed Senior Operator shall be in charge of any reactor core alteration.
- 4. The plant-specific titles of those personnel fulfilling the responsibilities of the positions delineated in Technical Specifications are documented in Table TRM 6.1.2.
- 7. If the Manager, Operations does not possess a Senior Operator License, then an Assistant Operations Manager shall be designated that does possess a Senior Operator License. All instructions to the shift crews involving licensed activities shall then be approved by designated Assistant Operations Manager.
E. A Fire Brigade of at least 5 members shall be maintained on-site at all times.# This excludes 2 members of the minimum shift crew necessary for safe shutdown of the plant and any personnel required for other essential functions during a fire emergency.
Fire Brigade composition may be less than the minimum requirements for a period of time not to exceed 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> in order to accommodate unexpected absence of Fire Brigade members provided immediate action is taken to restore the Fire Brigade to within the minimum requirements.
VYNPS TRM TABLE TRM 6.1.1 Vermont Yankee staff positions that shall be filled by personnel holding Senior Operator and Operator licenses are indicated in the following table:
Title License Requirements Manager, Operations Licensed Senior Operator (Except as specified in TRM Specification 6.1.D.7)
Manager, Shift Licensed Senior Operator Control Room Supervisor Licensed Senior Operator Control Room Operator Licensed Operator CONDITIONS Cold.Shutdown Plant Startup or Refueling and Normal With Fuel in the MINIMUM SHIFT STAFFING ON-SITE Operation (Note 1) Reactor (Note 2)
Manager, Shift 1 1 Control Room Supervisor 1 -
Control Room Operator 2 1 Auxiliary Operator 2 1 Shift Technical Advisor 1 NOTES:
(1) At least one Senior Licensed Operator and one Licensed Operator, or two Senior Licensed Operators, shall be in the Control Room.
(2) At least one Licensed Operator, or one Senior Licensed Operator, shall be in the Control Room.
Table TRM 6.1.2 The following table provides the link between TS generic position titles and Vermont Yankee plant-specific position titles, as specified in TS 6.2.A.l.
Generic Title Plant-Specific Title plant manager General Manager, Plant Operations shift supervisor Manager, Shift site vice president Site Vice President operations manager Manager, Operations assistant operations manager Assistant Operations Manager shift engineer Shift Technical Advisor radiation protection manager Manager, Radiation Protection
Reference:
License Amendment No. 214, NVY 03-19, dated 2/27/03.
4 VYNPS TRM TRM 6.'3 ACTION TO BE TAKEN IN THE EVENT OF A REPORTABLE OCCURRENCE IN PLANT OPERATION Applies to administrative action to be followed in the event of a reportable occurrence in plant operation.
Any reportable occurrence shall be reported to the Site Vice President, reviewed by the On-site Safety Review Committee and approved by the General Manager, Plant Operations.
Copies of all such reports shall be submitted to the Safety Review Committee for review.
TRM 6.4 ACTION TO BE TAKEN IF A SAFETY LIMIT IS EXCEEDED If a safety limit is exceeded, an immediate report shall be made to the Site Vice President. A complete analysis of the circumstances leading up to and resulting from the situation together with recommendations by the On-site Safety Review Committee shall also be prepared. This report shall be submitted to the Site Vice President and the Safety Review Committee.
Reactor operation shall not be resumed until authorized by the U.S.
Nuclear Regulatory Commission.
- TRM 6.5 PLANT OPERATING PROCEDURES A. Detailed written procedures, involving both nuclear and non-nuclear safety, including applicable check-off lists and instructions, covering areas listed below shall be prepared and approved.
All procedures shall be adhered to.
- 7. Fire protection program implementation including minimum fire brigade requirements and training. The training program shall meet or exceed the requirements of 10CFR50 Appendix R with NFPA 27 1976 as reference.
F. "Licensed radioactive sealed sources shall be leak tested for contamination. Tests for leakage and/or contamination shall be performed by the licensee or by other persons specifically authorized by the Commission or an agreement state as follows:
- 1. Each licensed sealed source, except startup sources previously subjected to core flux, containing radioactive materials, other than Hydrogen 3, with half-life greater than thirty days and in any form, other than gas, shall be tested for leakage and/or contamination at intervals not to exceed six months.
- 2. The periodic leak test required does not apply to sealed sources that are stored and are not being used. The sources exempted from this test shall be tested for leakage prior to any use or transfer to another user unless they have been leak tested within six months prior to the date of use or transfer. In the absence of a certificate from a transferrer indicating that a leak test has been made within six months prior to the transfer, sealed sources shall not be put into use until tested.
- 3. Each sealed startup source shall be tested within 31 days prior to being subjected to core flux and following repair or maintenance to the source.
The leakage test shall be capable of detecting the presence of 0.005 microcurie of radioactive material on the test sample.
If the test reveals the presence of 0.005 microcurie or more of removable contamination, it shall immediately be withdrawn from use, decontaminated, and repaired, or be disposed of in accordance with Commission regulations.
Notwithstanding the periodic leak tests required by this section, any licensed sealed source is exempt from such leak test when the source contains 100 microcuries or less of beta and/or gamma emitting material or 5 microcuries or less of alpha emitting material.
A special report shall be prepared and submitted to the Commission within 90 days if source leakage tests reveal the presence of >0.005 microcuries of removable contamination.
-TRM 6.7 REPORTING REQUIREMENTS In addition to the applicable reporting requirements of Title 10 Code of Federal Regulations, the following identified reports shall be submitted to the Director of the appropriate Regional Office of Inspection and Enforcement unless otherwise noted.
A. l.. Startup Report A summary report of plant startup and power escalation testing shall be submitted following (1) receipt of an operating license, (2) amendment to the license involving a planned increase in power level, (3) installation of fuel that has a different design or has been manufactured by a different fuel supplier, and (4) modifications that may have significantly altered the nuclear, thermal or hydraulic performance of the plant. The report shall address each of the tests identified in the FSAR and shall, in general, include a description of the measured values of the operating conditions or characteristics obtained during the test program and a comparison of these values with design predictions and specifications. Any corrective actions that were required to obtain satisfactory operation shall also be described. Any additional specific details required in license conditions based on other commitments shall be included in this report.
VYNPS TRM Startup reports shall be submitted within (1) 90 days following completion of the startup test program, (2) 90 days following resumption of commencement of commercial power operation, or (3) 9 months following initial criticality, whichever is earliest. If the startup report does not cover all three events (i.e.,
initial criticality, completion of startup test program, and resumption or commencement of commercial power operation), supplementary reports shall be submitted at least every three months until all three events have been completed.
TRM 6.11 IODINE MONITORING A program which will ensure the capability to accurately determine the airborne iodine concentration in vital areas# under accident conditions will be implemented. This program shall include the following:
A. Training of personnel.
B. Procedures for monitoring.
C. Provisions for maintenance of sampling and analysis equipment.
TRM 6.12 PROCESS CONTROL PROGRAM (PCP)
A process control program shall contain the sampling, analysis, tests, and determinations by which wet radioactive waste from liquid systems is assured to be converted to a form suitable for off-site disposal.
A. Licensee initiated changes to the PCP:
- 1. Shall be submitted to the Commission in the Annual Radioactive Effluent Release Report for the period in which the change(s) was made. This submittal shall contain:
- a. Sufficiently detailed information to support the rationale for the change without benefit of additional or supplemental information.
- b. A determination that the change did not reduce the overall conformance of the dewatered spent resins/filter media waste product to existing criteria for solid waste shipments and disposal.
- c. Documentation of the fact that the change has been reviewed by OSRC and approved by the Site Vice President.
- 2. Shall become effective upon review by OSRC and approval by the Site Vice President.
Areas requiring personnel access for establishing hot shutdown conditions.