ML20128Q744
| ML20128Q744 | |
| Person / Time | |
|---|---|
| Site: | FitzPatrick  |
| Issue date: | 10/11/1996 |
| From: | POWER AUTHORITY OF THE STATE OF NEW YORK (NEW YORK |
| To: | |
| Shared Package | |
| ML20128Q734 | List: |
| References | |
| NUDOCS 9610210156 | |
| Download: ML20128Q744 (11) | |
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Attachment i Updated Pages for Proposed Change to the Technical ,
Specifications Regard'"- Extension of Instrumentation and Miscellaneous Surveillence Test Interv6 4 Accommodate 24 Month Cycles (JPTS 95 0010)
Request for Amendment Submitted Under JPN 96-003 r
Panes 183 185 226 239 9610210156 961011 PDR ADOCK 05000333 P PDR
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o JAFNPP .
' 3.7 (cont'd) 4.7 (cont'd) ,
- e. Once per 24 months, manual operability of the bypass valve for filter cooling shall be demonstrated.
- f. Standby Gas Treatment System Instrumentation Calibration:
differential Once per 24 Months I pressure switches
- 2. From and after the date that one circuit of the Standby 2. When one circuit of the Standby Gas Treatment Gas Treatment System is made or found to be inoperable System becomes inoperable, the operable circuit for any reason, the following would apply: shall be verified to be operable immediately and daily thereafter.
- a. If in Start-up/ Hot Standby, Run or Hot Shutdown mode, reactor operation or irradiated fuel handling is permissible only during the succeeding 7 days unless such circuit is sooner made operable, provided that during such 7 days all active components of the other Standby Gas Treatment Circuit shall be operable.
- b. If in Refuel or Cold Shutdown mode, reactor operation or irradiated fuel handling is permissible only during the succeeding 31 days unless such circuit is sooner made operable, provided that during such 31 days all active components of the other Standby Gas Treatment Circuit shall be operable.
- 3. If Specifications 3.7.B.1 and 3.7.B.2 are not met, the 3. Intentionally Blank reactor shall be placed in the cold condition and i irradiated fuel handling operations and operations that could reduce the shutdown margin shall be prohibited.
Amendment No. 10,SS,'48,154,232, 183
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3.7 (cont'd) 4.7 (cont'd) ,
- c. Secondary containment capability to maintain a 1/4 in. of water vacuum under calm wind conditions with a filter train flow rate of not more than 6,000 cfm, shall be demonstrated once per 24 months p.-ior to refueling.
D. Primary Containment Isolation Valves D. Primary Containment Isolation Valves
- 1. Whensvar primary containment integrity is required per 1. The primary containment isolation valves surveillance 3.7.A.2, containment isolation valves and all instrument shall be performed as follows:
line excess flow check valves shall be operable, except as specified in 3.7.D.2. The containment vent and purge a. Once per 24 months, the operable isolation valves valves shall be limited to opening angles less than or that are power operated and automatically initiated .
equal to that specified below: shall be tested for simulated automatic initiation and for closure time.
Valve Number Maximum Openino Anale 27AOV-111 40 b. Once per 24 months, the instrument line excess 1 27AOV-112 400 flow check valves shel be tested for proper 27AOV-113 40 operation.
27AOV-114 50 27AOV-115 50* c. At least once per quarter:
27AOV-116 50 27AOV-117 50" (1.) All normally open power-operated isolation 27AOV-118 500 valves (except for the main stream line and Reactor Building Closed Loop Cooling Water System (RBCLCWS) power-operated isolation valves) shall be fully closed and reopened.
Amendment No. 151,'73,195,232, 185
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4.9 BASES (cont'd)
D. Not Used followed by a constant discharge current (temperature corrected) for the performance test.
E. Battery System I
The purpose of the modified performance test is to Measurements and electrical tests are conducted at specified demonstrate the battery has sufficient capacity to meet the ,
intervals to provide indication of cell condition and to system design requirements and to provide trandabie determine the discharge capability of the batteries. performance date to contpare the available capacity in the Performance and service tests are conducted in accordance battery to previous capacity test results. The modified !
with the recommendations of IEEE 450-1995. performance test may be performed in lieu of the battery i service test. j Tha battery service (duty cycle) test demonstrates the ;
capacity of the battery to meet the system design The station batteries are required for plant operation, and requirements. When a service test is used on a regular basis, performing the station battery service test and performance (or it will reflect maintenance practices. The FitzPatrick design modified performance) test requires the reactor to be shut duty cycie loads are determined by a LOCA concurrent with a down.
loss of normal and reserve power.
F. 1.PCI MOV Independent Power Sunolv The performance (discharge) test is a test of the constant current capacity of a battery and can be conducted with the Measurement and electrical tests are conducted at specified ,
battery in an as-found condition after being subjected to an intervals to provide indication of cell condition, to determine equalizing charge. If performance testing is to be used to the discharge capability of the battery. Performance and ,
reflect baselined battery trending capacity, then special service tests are conducted in accordance with the conditions (including equalizing) artm;;uired to establish the recommendations of IEEE 450-1995.
battery in an as known condition prie to the test. If ;
performance testing is to be used to reflect maintenance G. Reactor Protection Power Sunolies l practices as well as trending, the equalizing charge can be omitted. Functional tests of the electrical protection assemblies are conducted at specified intervals utilizing a built-in test device The modified performance test is a composits test which and once per 24 months by performing an instrument I envelopes both the service test and performance test calibration which verifies operation within the limits of Section requirements. The modified performance test discharge 4.9.G.
current envelopes the peak duty cycle loads of the service test .
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Amendment No. '^ " ' i 226
JAFNPP .
3.11 (cont'd) 4.11 (cont'd) .
B. DELETED B. DELETED C. Battery Room Ventilation C. Battery Room Ventilation Battery room ventilation shall be operable on a continuous Battery room ventilation equipment shall be demonstrated basis whenever specification 3.9.E is required to be satisfied. operable once/ week.
- 1. From and after the date that one of the battery room 1. When it is determined that one battery room ventilation ventilation systems is made or found to be inoperable, system is inoperable, the remaining ventilation system shall its associated battery shall be considered to be be verified operable and daily thereafter.
inoperable for purposes of specification 3.9.E.
- 2. Temperature transmitters and differential pressure switches shall be calibrated once per 24 months. I Amendment No. 48, S2,125,134, 'iS,15S. 231, 239
Att chmInt 11 4
Updated Psges for Proposed Change to the Technical Specifications Regarding Response Time Testing Requirements (JPTS 96-006)
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Request for Amendment Submitted Under JPN-96-024 i
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JAFNPP ,
3.1 LIMITING CONDITIONS FOR OPERATION 4.1 SURVEILLANCE REQUIREMENTS 3.1 REACTOR PROTECTION SYSTEM 4.1 REACTOR PROTECTION SYSTEM Acolicability: Anolicability:
Applies to the instrumentation and associated devices which Applies to the surveillance of the instrumentation and associated initiate the reactor scram. devices which initiate reactor scram.
Obiective: Obiective:
To assure the operability of the Reactor Protection System. To specify the type of frequency of surveillance to be applied to the protection instrumentation.
Specification: Specification:
A. The setpoints and minimum number of instrument A. Instrumentation systems shall be functionally tested and calibrated channels per trip system that must be operable for each as indicated in Tables 4.1-1 and 4.1-2 respectively.
s tion of the reactor mode switch, shall be as shown in g ; ;
listed below shall be demonstrated to be within its limit once per 24 months. Neutron detectors are exempt from response time testing. Each test shall include at least one channel in each trip system. All channels in both trip systems shall be tested within two test intervals.
- 1. Reactor High Pressure (02-3PT-55A, B, C, D)
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- 2. Drywell High Pressure (05PT-12A, B, C, D)
- 3. Reactor Water Level-Low (L3) (02-3LT-101 A, B, C, D)
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- 4. Main Steam Line isolation Valve Closure (29PNS-80A2, B2, C2, D2)
(29PNS-86A2, B2, C2, D2)
- 5. Turbine Stop Valve Closure (94PNS-101,102,103,104)
- 6. Turbine Control Valve Fast Closure (94PS-2OOA, B, C, D)
- 7. APRM Fixed High Neutron Flux
- 8. APRM Flow Referenced Neutron Flux
- Sensor is eliminated from response time testing for the RPS actuation logic circuits. Response time testing and conformance to the test acceptance criteria for the remaining channel components includes trip unit and relay logic.
Amendment No. 427,233, 3Og
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JAFNPP ,
r 4.1 BASES (cont'd) .
The individual sensor response time may be measured by B. The MFLPD is checked once per day to determine if the simulating a step change of the particular parameter. This APRM scram requires adjustment. Only a small number of i method provides a conservative value for the sensor control rods are moved daily arvt thus the MFLPD is not ,
response time, and confirms that the instrument has expected to change significantig and thus a daily check of f retained its specified electromechanical characteristics. the MFLPD is adequate. j When sensor response time is measured independently, it is necessary to also measure the remaining portion of the The sensitivity of LPRM detectors decreases with exposure response time in the logic train up to the time at which the to neutron flux at a slow and approximately constant rate.
scram pilot valve solenoids de-energize. The channel This is compensated for in the APRM system by calibrating i response time must include all component delays in the twice a week using heat balance data and by calibrating ;
response chain to the ATTS output relay plus the design individual LPRM's every 1000 effective full power hours, j allowance for RPS logic system response time. A response using TIP traverse data. l time for the RPS logic relays in excess of the design allowance is acceptable provided the overall response time i
does not exceed the response time limits specified in the UFSAR. The basis for excluding the neutron detectors from i response time testing is provided by NRC Regulatory Guide f i
1.118, Revision 2, section C.5.
The sensors for the Reactor High pressure and Reactor >
Water Level - Low (L3) trip functions are exempted from response time testing based on analyses provided in NEDO-32291-A, " System Analyses for the Elimination of Selected-Response Time Testing".
i Two instrument channels in Table 4.1-1 have not been included in Table 4.1-2. These are: mode switch in '
shutdown and manual scram. All of the devices or sensors associated with these scram functions are simple on-off switches and, hence, calibration during operation is not applicable.
Amendment No. 44,39,134,183, 227,'233, 38 1 !
JAFNPP .
.l, 3.2 LIMITING CONDITIONS FOR OPERATION 4.2 SURVEILLANCE REQUIREMENTS
. 3.2 INSTRUMENTATION 4.2 INSTRUMENTATION Acolicability: j Acolicability:
Appliss to the plant instrumentation which either (1) initiates and Applies to the surveillance requirement of the instrumentation which controls a protective function, or (2) provides information to aid either (1) initiates and controls protective function, or (2) provides - '
the operator in monitoring and assessing plant status during information to aid the operator in monitoring and assessing plant normal and accident conditions. status during normal and accident conditions.
Obiective: Obiective:
To cssure the operability of the aforementioned instrumentation. To specify the type and frequency of surveillance to be applied to the aforementioned instrumentation.
Specifications: Specifications: \
A. Primary Containment isolation Functions A. Primary Containment isolation Functions When primary containment integrity is required, the limiting instrumentation shall be functionally tested and calibrated as conditions of operation for the instrumentation that initiates indicated in Table 4.2-1. System logic shall be functionally primary containment isolation are given in Table 3.2-1. tested as indicated in Table 4.2-1.
'r The response time of the main steam isolation valve actuation '
instrumentation isolation trip functions listed below shall be demonstrated to be within their limits once por 24 months.
Each test shall include at least one channel in each trip system.
All channels in both trip systems shall be tested within two test intervals.
- 1. MStV Closure - Reactor Low Water Level (L1)
(02-3LT-57A,B and 02-3LT-58A,B)
- 2. MSIV Closure - Low Steam Line Pressure *
(02PT-134A,B,C,D)
- 3. MSIV Closure - High Steam Line Flow *
(02DPT-1 16 A-D, 1 17A-D, 1 18 A-D, 1 19 A-D)
- Sensor is eliminated from response time testing for the MSIV actuation logic circuits. Response time testing and conformance to the test acceptance criteria for the remaining channel components includes trip unit and relay logic.
Am:ndment No. 130,183,227,233, 49
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Attachment 111 i
Updated Pages for Proposed Change to the Technical 1 Specifications Regarding implementation of BWROG Option 1 D Long Term Solution for Thermal Hydrauiic Stability (JPTS 96-005)
Request for Amendment Submitted Under JPN-96-009
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r JAFNPP TABLE OF CONTENTS (Cont'd) f Eilaft F. ECCS Cold Condition F. 122 j
, G. Maintenance of Filled Discharge Pipe G. 122a H. Average Planar Linear Heat Generation Rate H. 123 i (APLHGR)
- l. Linear Heat Generation Rate (LHGR) 1. 124 J. Thermal Hydraulic Stability DELETED 124a K. Single-Loop Operation NONE 124a SURVEILLANCE LIMITING CONDITIONS FOR OPERATION REQUIREMENTS i
- 3.6 Reactor Coolant System 4.6 136
- A. Pressurization and Thermal Limi s A. 136 B. DELETED C. Coolant Chemistry C. 139 D. Coolant Leakage D. 141 E. Safety and Safety / Relief Valves E. 142a F. Structural integrity F. 144 G. Jet Pumps G. 144 H. DELETED
- 1. Shock Suppressors (Snubbers) 1. 145b 3.7 Containment Systems 4.7 - 165 A. Primary Containment . A. 165 B. Standby Gas Treatment System B. 181 C. Secondary Containment C. 184 D. Primary Containment Isolation Valves D. 185 l 3.8 Miscellaneous Radioactive Material Sources 4.8 214 3.9 Auxiliary Electrical Systems 4.9 215 A. Normal and Reserve AC Power Systems A. 215 1 B. Emergency AC Power System B. 216 l C. Diesel Fuel C. 218 i D. Diesel-Generator Operabiluy D. 220 E. Station Batteries E. 221 F. LPCI MOV Independent Power Supplies F. 222a G. Reactor Protection System Electrical Protection G. 222c Assemblies 3.10 Core Alterations 4.10 227 A. Refueling interlocks A. 227 B. Core Monitoring B. 230 C. Spent Fuel Storage Pool Water Level C. 231 D. Control Rod and Control Rod Drive Maintenance D. 231 3.11 Additional Safety Related Plant Capabilities 4.11 237 A. Main Control Room Ventilation A. 237 B. DELETED C. Battery Room Ventilation C. 239 Amendment No. 20,13.90,*13,1SS,231, ii w