ML20005H022
| ML20005H022 | |
| Person / Time | |
|---|---|
| Site: | Seabrook  |
| Issue date: | 01/11/1990 |
| From: | PUBLIC SERVICE CO. OF NEW HAMPSHIRE |
| To: | |
| Shared Package | |
| ML20005G203 | List: |
| References | |
| NUDOCS 9001240054 | |
| Download: ML20005H022 (20) | |
Text
o
- .. g INDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION PAGE 3/4.9.4 CONTAINMENT BUILDING PENETRATIONS........
3/4.9.5 3/4 9-4 3/4.9.6 COMMUNICATIONS........................................... 3/4 9-5 3/4.9.7' REFUELING MACHINE........................................
................ 3/4 9-6 3/4.9.8 CRANE TRAVEL - SPENT FUEL STORAGE AREAS.................. 3/4 9-7 RESIDUAL HEAT REMOVAL AND COOLANT CIRCULATION High Water Level.........................................- 3/4 9-8 Low Water Leve1.......................................... 3/4 9-9 3/4.9.9 CONTAINMENT PURGE AND EXHAUST ISOLATION SYSTEM........... 3/4 9-10 3/4.9.10 WATER LEVEL - REACTOR VESSEL............................. 3/4 9-11 3/4.9.11 WATER LEVEL - STORAGE POOL .............................. 3/4 9-12 3/4.9.12 FUEL STORAGE BUILDING EMERGENCY AIR CLEANING SYSTEM...... 3/4 9-13 3/4.10 SPECIAL TEST EXCEPTIONS 3/4.10.1 SHUTDOWN MARGIN..........................................
-3/4.10.2 GROUP HEIGHT, INSERTION, AND POWER DISTRIBUTION LIMITS...
3/4 10-1
-3/4.10.3 PHYSICS TESTS............................................
3/4 10-2 3/4 10-3 3/4.10.4 REACTOR COOLANT L00PS.................................... 3/4 10-4 3/4.10.5 POSITION INDICATION SYSTEM - SHUT 00WN.................. . 3/4 10-5 3/4.10.6 REACTOR COOLANT L00PS.................................. . 3/4 10-6 3/4.11 RADIOACTIVE EFFLUENTS ,
3/4.11.1 LIQUID EFFLUENTS Concentration........................ .......... 3/4 11-1 Dose.........................................
Liquid Radwaste Treatment System.........................
3/4 11-2 3/4 11-3 Liquid Holdup Tanks...................................... 3/4 11-4 >
3/4.11.2 GASEOUS EFFLUENTS Dose Rate.................. ..... ....................... 3/4 11-5 Dose - Noble Gases....................................... 3/4 11-6 Dose - Iodine-131 Iodine-133, Tritium, and Radioactive Material in Particulate Form............................. 3/4 11-7 Gaseous Radwaste Treatment System.......... ............. 3/4 11-8 Explosive as Mixture - System........................... 3/4 11-9 3/4.11.3 SOLID RADIOACTIVE WASTES...... ..................... .... 3/4 11-10 3/4.11.4 TOTAL 00SE................................. ... ......... 3/4 11-12 3/4.12 RADIOLOGICAL ENVIRONMENTAL MONITORING 3/4.12.1 MONITORING PROGRAM............. .. ..... ....... . .. . 3/4 12-1 SEABROOK - UNIT 1 ix 9001240054 900111 PDR ADOCK 05000443 P PDR
S i
INDEX
, BASES '
4
.SECTION~
PAGE 3/4.9.8' RESIDUAL HEAT REMOVAL AND COOLANT CIRCULATION............. B 3/4 9-2 I
.3/4.9.9 CONTAINMENT PURGE AND EXHAUST ISOLATION SYSTEM............B 3/4 9-2 3/4.9.10 and 3/4.9.11 WATER LEVEL - REACTOR VESSEL and P00L............................................
STORAGE '
B 3/4 9-2 3/4.9.12 FUEL STORAGE BUILDING EMERGENCY AIR CLEANING SYSTEM....... B 3/4 9-2
^
3/4.10 SPECIAL TEST EXCEPTIONS i
3/4.10.1 SHUTDOWN MARGIN...........................................
- 3/4.10.2 GROUP HEIGHT,. INSERTION, AND POWER DISTRIBUTION LIMITS. . . .
B 3/4 10-1 !
3/4.10.3 PHYSICS TESTS.............................................
B 3/4 10-1
- B 3/4 10-1 3/4.10.4 REACTOR COOLANT L00PS..................................... B 3/4 10-1 3/4.10.5 POSITION INDICATION SYSTEM - SHUT 00WN................. ... B 3/4 10-1
.3/4.10.6 REACTOR COOLANT L00PS................................. ... B 3/4 10-1 ,
3/4.11 RADIOACTIVE EFFLUENTS 3/4.11.1 LIQUID EFFLUENTS.. ...............................
B 3/4 11-1 3/4.11.2 GASEOUS EFFLUENTS.................... ...................
3/4.11.3 SOLID RADI0 ACTIVE WASTES...............................
..... . B 3/4 11-2 ,
3/4,11.4 TOTAL B 3/4 11-5 '
00SE.............................................. B 3/4 11-5 3/4.12 RADIOLOGICAL ENVIRONMENTAL MONITORING 1
3/4.12.11 MONITORING PR0 GRAM....................................... B 3/4 12-1 ?
3/4.12.2 LAND.USE CENSUS.......................................... B 3/4 12-1 '
3/4.12.3 INTERLABORATORY COMPARISON PR0 GRAM....................... B 3/4 12-2 5.0. DESIGN FEATURES 5.1 SITE 5.1.1 EXCLUSION AREA.............................................. 5-1 5.1. 2 LOW POPULATION Z0NE.........................................
5,1. 3 MAPS DEFINING UNRESTRICTED AREAS AND SITE BOUNDARY FOR 5-1 RADI0 ACTIVE GASEOUS AND LIQUID EFFLUENTS.................... 5-1 FIGURE 5.1-1 SITE AND EXCLUSION AREA B0VNDARY..................... 5-3 FIGURE 5.1-2 LOW POPULATION 20NE.................................. 5-5 FIGURE 5.1-3 LIQUID EFFLUENT DISCHARGE LOCATION................... 5-7 5.2 CONTAINMENT 5.2.1 CONFIGURATION............................................... 5-1 5.2.2 DESIGN PRESSURE AND TEMPERATURE.......................... .. 5-9 SEABROOK - UNIT 1 xii
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- - REAC' TOR COOLANT SYSTEM e
a SAFETY VALVES
' OPERATING
' LIMITING CONDITION FOR OPERATION f
3.4.2.2 All' pressurizer Code safety valves'shall be OPERABLE with a lift setting of 2485 psig i 1%.*
h APPLICABILITY: MODES 1,'2, and 3# .
! ACTION:
y F
With one pressurizer Code safety valve inoperable, either restore the inoper-able valve. to OPERABLE status within 15 minutes or be in at least' HOT- STANDBY within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in at least HOT SHUTOOWN within the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
i, SURVEILLANCE REQUIREMENTS
[
4.4.2.2 No additional requirements other than those required by Specifica-7 tion 4.0.5.
L i
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- The lift setting pressure shall correspond to ambient conditions of the valve at nominal operating temperature and pressure.
- E ntry into'this MODE is permitted for up to 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> to perform post-modification or post-maintenance testing to verify OPERABILITY of components.
ACTION requirements shall not apply until OPERABILITY has been verified.
SEABROOK - UNIT 1 3/4 4-9
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o- 3/4:7 PLANT SYSTEMS
' 3/4.' 7.1 TURBINE CYCLE SAFETY VALVES LIMITING CONDITION FOR OPERATION 3.7.1.1 All main steam line Code safety valves associated with each steam generator shall be OPERABLE with lift settings as specified in Table 3.7-2.
APPLICABILITY: MODES 1, 2, and 3# .
ACTION:
With four reactor coolant loops and associated steam generators in operation and with one or more main steam line Code safety valves inoperable, operation in MODES 1, 2, and 3 may proceed, provided that within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> cither the in-operable valve is restored to OPERABLE status or the Power Range Neutron Flux High Trip Setpoint is reduced per Table 3,7-1; otherwise, be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
SURVEILLANCE REQUIREMENTS 4.7.1.1 No additional requirements other than those required by Specifica-tion 4.0.5.
l Entry into this MODE is permitted for up to 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> to perform post-modification or post-maintenance testing to verify OPERABILITY of components.
ACTION requirements shall not apply until OPERABILITY has been verified.
SEABROOK - UNIT 1 3/4 7-1
y
' PLAAT SYSTEMS
, TURBINE CYCLE MAIN STEAM LINE ISOLATION VALVES
-LIMITING CONDITION FOR OPERATION
- 3. 7.1. 5 Each main steam line inolation valve (MSIV) shall be OPERABLE.
APPLICABILITY: MODES 1, 2, and 3# .
-ACTION:
MODE 1:
With one MSIV inoperable but open, POWER OPERATION may continue provided !
the inoperable valve is restored to OPERABLE status within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />; otherwise be.in HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in HOT SHUTDOWN within the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
MODES 2 and 3:
1:
With one MSIV inoperable, subsequent operation in MODE 2 or 3 may proceed provided the isolation valve is maintained closed. Otherwise, be in HOT
' STANDBY.within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in HOT SHUTOOWN within the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
SURVEILLANCE REQUIREMENTS
- 4. 7.1. 5 Each MSIV shall be demonstrated OPERABLE by verifying full closure within 5.0 seconds-when tested pursuant to Specification 4.0.5. The provisions of Specification 4.0.4 are not applicable for entry into MODE 3.
l Entry into this MODE is permitted for up to 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> to perform post-modification or post-maintenance testing to verify OPERABILITY of components, j ACTION requirements shall not apply until OPERABILITY has been verified.
l- SEABROOK - UNIT 1 3/47-9
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PL NT SYSTEMS TURBINE CYCLE ATMOSPHERIC RELIEF VALVES .
LIMITING CONDITION FOR OPERATION
,, 3. 7.1. 6
' At least four atmospheric relief valves and associated manual controls including the safety related gas supply systems shall be OPERABLE.
[ APPLICABILITY: MODES 1, 2, 3# , and 4*# .
L EION:O l a.
, With one less than the required atmospheric relief valves OPERABLE, restore the required atmospheric relief valves to OPERABLE status within 7 days; or be in at least HOT STANDBY within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />, b.
With two less than the required atmospheric relief valves OPERABLE, restore at least three atmospheric relief valves to OPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
SURVEILLANCE REQUIREMENTS
- 4. 7.1. 6 Each atmospheric relief valve and associated manual controls including the safety-related gas supply systems shall be demonstrated OPERABLE:
a.
At least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> by verifying that the nitrogen accumulator tank is at a pressure greater than or equal to 500 psig.
- b. Prior to startup following any refueling shutdown or cold shutdown of 30 days or longer, verify that all valves will open and close fully by operation of manual controls.
- When steam generators are being used for decay heat removal.
- E ntry into this MODE is permitted for up to 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> a perform post-modification or post-maintenance testing to verify Or JABILITY of components.
ACTION requirements shall not apply until OPERABILITY has been verified.
SEABROOK - UNIT 1 3/4 7-10
, PL4NT SYSTEMS I
3/4.7.6 CONTROL ROOM EMERGENCY MAKEUP AIR AND FILTRATION SUBSYST LIMITING CONDITION FOR OPERATION !
3.7.6 Two independent Control Room Emergency Makeup Air and Filtration Subsystems shall be OPElABLE. l i
APPLICABILITY: All MC)iS ACTION:
MODES 1, 2, 3 and 4: i With one Control Room Emergency Makeup Air and Filtration Subsystem inoperable, restore the inoperable system to OPERABLE status within 7 days.or be thein at least 30 following HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTOOWN within hours.
MODES 5 and 6:
a.
With one Control Room Emergency Makeup Air and Filtration Subsystem ;
inoperable, restore the inoperable system to OPERABLE status within 7 days or initiate and maintain operation of the remaining OPERABLE Control Room Emergency Makeup Air and Filtration Subsystem in the filtration / recirculation mode.
- b.
With both Control Room Emergency Makeup Air and Filtration Subsystems
- inoperable, or with the OPERABLE Control Room Emergency Makeup Air and Filtration Subsystem, required to be in the filtration / recirculation mode by ACTION a., not capable of being powered by an OPERABLE emergency power source, suspend all operations involving CORE ALTERATIONS or positive reactivity changes. ,
SURVEILLANCE REQUIREMENTS 4.7.6 Each Control Room Emergency Makeup Air and Filtration Subsystem shall be demonstrated OPERABLE:
- a. At least least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> by verifying that the control room is maintained below the limiting equipment qualification temperature in the control room area,
- b. At least once per 31 days on a STAGGERED TEST BASIS by initiating, f rom the control room, flow through the HEPA filters and charcoal adsorbers and verifying that the system operates for at least 10 continuous hours with the heaters operating; 1.
l SEABROOK - UNIT 1 3/4 7-16 l-o
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4 PLANT SYSTEMS SURVEILLANCE REQUIREMENTS (Continued)
- c. At least once per 18 months or (1) after any structural maintenance on the HEPA filter or charcoal adsorber housings, or (2) following painting, fire or chemical release in any ventilation Ione communicating with the system by:
- 1) Verifying that the filtration system satisfies the in place penetration and bypass leakage testing acceptance criteria of i less than .05% and uses the test procedure guidance in Regulatory Position C.S.a, C.S.c. and C.S.d of Regulatory Guide 1.52, Revision 2 March 1978*, and the system flow rate is 1100 cfm i 10%;
- 2) Verifying, within 31 days after removal, that a laboratory analysis of a representative carbon sample obtained in ;
accordance with Regulatory Position C.6.b of Regulatory Guide 1.52, Revision 2, March 1978*, meets the laboratory testing criteria'of Regulatory Position C.6.a of Regulatory Guide 1.52, Revision 2, March 1978*, for a methyl iodide penetration of less than 1.0%; and
- 3) Verifying a system flow rate of 1100 cfm i 10% during system operation when tested in accordance with ANSI N510-1980. [
- d. ,
After every 720 hours0.00833 days <br />0.2 hours <br />0.00119 weeks <br />2.7396e-4 months <br /> of charcoal adsorber operation, by verifying, within 31 days after removal, that a laboratory analysis of a representative carbon sample obtained in accordance with Regulatory Position C.6.b of Regulatory Guide 1.52, Revision 2, March 1978*,
meets the laboratory testing criteria of Regulatory Position C.6.a '
of Regulatory Guide 1.52, Revision 2, March 1978*, for a methyl iodide penetration of less than 1.0%;
- e. At least once per 18 months by:
- 1) Verifying that the pressure drop across the combined HEPA filters and charcoal adsorber banks, for filter CBA-F-38, is less than 2.8 inches Water Gauge while operating the system at a flow rate of 1100 cfm i 10%; and verifying that the pressure drop across the combined HEPA filters and charcoal adsorber banks, for filter CBA-F-8038, is less than 6.3 inches Water Gauge while operating the system at a flow rate of 1100 cfm 10%.
- 2) Verifying that upon generation of an 'S' test signal, the following automatic system functions occur:
- a. The normal makeup air fan (s) trip off and the normal makeup air isolation damper (s) close;
- ANSI N510-1980 shall be used in place of ANSI N510-1975 as referenced in Regulatory Guide 1.52, Revision 2.
SEABROOK - UNIT 1 3/4 7-17
PLANT SYSTEMS SURVEILtANCE REQUIREMENTS (Continued)
- b. The control room exhaust subsystem isolation damper (s) close, and the exhaust fan trips off;
- c. The control room emergency makeup air and filtration subsystem actuates with flows through the HEPA filters and charcoal adsorber banks;
- 3) Verifying that upon generation of Remote Intake High Radiation test signal, the following automatic system functions occur:
- a. The normal makeup air fan (s) trip off and the normal makeup air isolation damper (s) close;
- b. The control room exhaust subsystem isolation damper (s) close, and the exhaust fan trips off;
- c. The control room emergency makeup air and filtration subsystem actuates with flows through the HEPA filters and charcoal adsorber banks;
- 4) Verifying that the Control Room Emergency Makeup Air and Filtration Subsystem maintains the control room at a positive pressu 9 of greater than or equal to 1/8 inch Water Gauge at less than or equal to a pressurization flow of 600 cfm relative to adjacent areas during system operation; and
- 5) Verifying that the heaters dissipate 3.6 1 0.36 kW when tested in accordance with ANSI N510-1980.
- f. After each complete or partial replacement of a HEPA filter bank, by verifying that the filtration system satisfies the in place penetration and bypass leakage testing acceptance criteria of less than .05% in accordance with ANSI N510-1980 for a 00P test aerosol while operating the system at a flow rate of 1100 cfm i 10%; and
- g. After each complete or partial replacement of a charcoal adsorber bank, by verifying that the filtration system satisfies the in place penetration and bypass leakege testing acceptance criteria of less than .05% in accordance with ANSI N510-1980 for a halogenated hydrocarbon refrigerant test gas while operating the system at a flow rate of 1100 cfm i 10%.
SEABROOK - UNIT 1 3/4 7-18 l
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U j,g, PLANT SYSTEMS 3/4.7.7 SNUB 8ERS i
- LIMITING CONDITION FOR OPERATION ~
1 3.7.7 All snubbers shall be OPERABLE. The only snubbers excluded from the
{
requirements.are those installed on nonsafety related systems'and then only :
if their failure or. failure of the system on which they are installed would i have no adverse effect on any safety-related system.
APPLICABILITY: MODES 1, 2, 3, and 4 1 systems required OPERABLE in those MODES. MODES 5 and 6 for snubbers located on !
ACTION:' '
i With one or more snubbers inoperable on any system, within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> replace or .
" restore the inoperable snubber (s) to OPERABLE status and perform an engineerin evaluation in accordance with the approved augmented inservice inspection pro g }
gram on the attached component or declare the attached system inoperable and !
follow the appropriate. ACTION statement for that system.
SURVEILLANCE REQUIREMENTS-- -t 4.7.7 Each snubber shall be demonstrated OPERABLE by- performance of the re-
~ quirements of an approved augmented inservice inspection program.
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SEABROOK UNIT 1 3/4 7-19 I
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- j. PLANT SYSTEMS 3/4.7.8 SEALED SOURCE CONTAMINATION LIMITING CONDITION FOR OPERATION 3.7.8 Each sealed source containing radioactive material either in excess of 100 microcuries of beta and/or gamma emitting material or 5 microcuries of alpha emitting material shall be free of greater than or equal to 0.005 micro-Curie of removable contamination.
APPLICABILITY: At all times.
ACTION:
- a. With a sealed source having removable contamination in excess of the above limits, immediately withdraw the sealed source from use and either:
- 1. Decontaminate and repair the sealed source, or
- 2. Dispose of the sealed source in accordance with Commission Regulations.
- b. The provisions of Specification 3.0.3 are not applicable.
SURVEILLANCE REQUIREMENTS 4.7.8.1 Test Requirements - Each sealed source shall be tested for leakage and/or contamination by:
- a. The licensee, or
- b. Other persons specifically authorized by the Cammission or an Agreement State.
The test method shall have a detection sensitivity of at least 0.005 microcurie per test sample.
- 4. 7. 8. 2 Test Frequencies - Each category of sealed sources (excluding startup sources and fission detectors previously subjected to core flux) shall be tested at the frequency described below,
- a. Sources in use - At least once per 6 months for all sealed sources containing radioactive materials:
- 1. With a half-life greater than 30 days (excluding Hydrogen 3),
and
- 2. In any form other than gas.
SEABROOK - UNIT 1 3/4 7-20
tn PLANT SYSTEMS SEALED SOURCE CONTAMINATION SURVEILLANCE' REQUIREMENTS 4.7.8.2 (Continued) b.
Stored sources not in use - Each sealed source and fission detector shall be tested prior to use or transfer to another licensee unless tested within the previous 6 months. Sealed sources and fission detectors transferred without a certificate indicating the last test date shall be tested prior to being placed into use; and
- c. Startup sources and fission detectors - Each sealed startup source and fission detector shall be tested within 31 days prior to being subjected to core flux or installed in the core and following repair or maintenance to the source.
4.7.8.3 Reports - A report shall be prepared and submitted to the Commission on an annual basis if sealed source or fission detector leakage tests reveal the presence of greater than or equal to 0.005 microcurie of removable contamination.
SEABROOK - UNIT 1 3/4 7-21 J
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i- ' PLANT SYSTEMS 3/4.7.10 AREA TEMPERATURE MONITORING LIMITING CONDITION FOR OPERATION 3.7.10 The temperature of each area shown in Table 3.7-3 shall not be exceeded for more than 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> or by more than 30'F.
i L APPLICABILITY:
Whenever the equipment in an affected area is required to be i ' ACTION:
{ a.
j With one or more areas exceeding the temperature limit (s) shown in Table 3.7-3 for more than 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />, prepare and submit to the l' Commission within 30 days, pursuant to Specification 6.8.2, a Special' Report that provides a record of the cumulative time and the amount by which the temperature in the affected area (s) exceeded the limit (s) and an analy:is to demonstrate the continued 1' OPERABILITY of the affected equipment. The provisions of Specifi-cation 3.0.3 are not applicable.
b.
! With one or more areas exceeding the temperature limit (s) shown in Tab'e 3.7-3 by more than 30*F, prepare and submit a Special Report as cequired by ACTION a. above and within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> either restore the area (s) to within the temperature limit (s) or declare the equip-ment in the affected area (s) inoperable.
SURVEILLANCE REQUIREMENTS 4.7,10 The temperature in each of the areas shown in Table 3.7-3 shall be determined to be within its limit at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
I i
i SEABROOK - UNIT 1 3/4 7-23 i
u _1
- s
.: TABLE 3.7-3 AREA TEMPERATURE MONITORING AREA TEMPERATURE LIMIT ('F)
- 1. Control Room 75
- 2. Cable Spreading Room- 104
- 3. Switchgear Room - Train A 104
- 4. Switchgear Room - Train B 104
- 5. Battery Rooms - Train A 97
- 6. Battery Rooms - Train B 97
- 7. ECCS Equipment Vault - Train A 104
- 8. ECCS Equipment Vault - Train B 104
- 9. Centrifugal Charging Pump Room - Train A 104
- 10. Centrifugal Charging Pump Room - Train B 104
- 11. ECCS Equipment Vault Stairwell - Train A 104
- 12. ECCS Equipment Vault Stairwell - Train B 104
- 13. PCCW Pump Area 104
- 14. Cooling Tower Switchgear Room - Train A 104
- 15. Cooling Tower Switchgear Room - Train B 104
- 16. Cooling Tower SW Pump Area 127
- 19. SW Pump Area 104
- 20. Diesel Generator. Room - Train A 120
- 21. Diesel Generator Room - Train B 120
- 22. EFW Pumphouse 104
- 23. Electrical Penetration Area - Train A 100
- 24. Electrical Penetration Area - Train B 85
- 25. Fuel Storage Building Spent Fuel Pool Cooling 104 Pump Area 26, Main Steam and Feedwater Pipe Chase - East 130
- 27. Main Steam and Feedwater Pipe Chase - West 130
- 28. Hydrogen Analyzer Room 104
- 29. MSFW East Pipe Chase Electrical Room 104 SEABROOK - UNIT 1 3/4 7-24
. SPECIAL~ TEST EXCEPTIONS 3/4.10.6 REACTOR COOLANT LOOPS LIMITING CONDITION FOR OPERATION 3.10.6 The limitations of Specification 3.4.1.2 may be suspended during the performance of testing involving natural circulation conditions for up to 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> in MODE 3 provided (1) at least two reactor coolant loops as listed in Specification 3.4.1.2 are OPERABLE, (2) no operations are permitted that would cause dilution of the reactor coolant system boron concentration, (3) the reactor trip breakers are open, and (4) core outlet temperature is maintained-at least 10'F below saturation temperature.
APPLICABILITY: During performance of testing involving natural circulation conditions.
ACTION:
With less than the above required reactor coolant loops OPERABLE during per-formance of testing involving natural circulation conditions comply with the provisions of the ACTION statements of Specification 3.4.1.2.
SURVEILLANCE REQUIREMENTS 4.10.6 At least the above required reactor coolant loops shall be determined OPERABLE within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> prior to initiation of testing involving natural circulation conditions and at least once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> during testing involving natural circulation conditions by verifying indicated power availability and by ver fying secondary side narrow range water level to be greater than or equal to 14%.
l l
SEABROOK - UNIT 1 3/4 10-6
(
3/4.10 SPECIAL TEST EXCEPTIONS BASES 3/4.10.1 SHUTOOWN MARGIN This special. test exception provides that a minimum amount of control rod worth is immediately available for reactivity control when tests are performed for control rod worth measurement. This special test exception is required to permit the periodic verification of the actual versus predicted core reactivity condition occurring as a result of_ fuel burnup or fuel cycling operations, 3/4.10.2 GROUP HEIGHT, INSERTION, AND POWER DISTRIBUTION LIMITS This special test exception permits individual control rods to be posi-tioned outside of their normal group heights and insertion limits during the performance of such PHYSICS TESTS as those required to: (1) measure control rod worth and-(2) determine the reactor stability index and damping factor under xenon oscillation conditions.
3/4.10.3 PHYSICS TESTS This special test exception permits PHYSICS TESTS to be performed at leis
'than or equal to 5% of RATED THERMAL POWER with the RCS T,yg slightly lower than nermally allowed 50 that the fundamental nuclear characteristics of the core and related instrumentation can be verified. In order for various charac-
, teristics to be accurately measured, it is at times necessary to operate outside the normal restrictions of these Technical Specifications. For instance, to measure the moderator temperature coefficient at BOL, it is necessary to position the various control rods at heights which may not normally be allowed by Specification 3.1.3.6 and the RCS T,yg may be below the minimum temperature of Specification 3.1.1.4 during the measurement.
3/4.10.4 REACTOR COOLANT LOOPS This special test exception permits reactor criticality under no flow conditions and is required to perform certain STARTUP and PHYSICS TESTS while at low THERMAL POWER levels.
3/4.10.5 POSITION INDICATION SYSTEM - SHUT 00WN This special test exception permits the Position Indication Systems to be inoperable during rod drop time measurements. The exception is required since the data necessary to determine the rod drop time are derived from the induced voltage in the position indicator coils as the rod is dropped. This induced voltage is small compared to the normal voltage and, therefore, cannot be observed if the Position Indication Systems remain OPERABLE.
3/4.10.6 REACTOR COOLANT LOOPS This special test exception permits all reactor coolant pumps to be de-energized for the performance of startup tests involving natural circulation conditions while the reactor is suberitical.
SEABROOK - UNIT 1 B 3/4 10-1
~
.)
,e PLANT SYSTEMS i BASES 3/4.7.2 STEAM GENERATOR PRESSURE / TEMPERATURE LIMITATION The limitation on steam generator pressure and temperature ensures that
'r the pressure-induced stresses in the steam generators do not exceed the maximum allowable fracture toughness stress limits. The limitations of 70'F and 200 psig are based on a steam generator RT prevent brittle fracture NDT f 60'F and are sufficient to 3/4.7.3 PRIMARY COMPONENT COOLING WATER SYSTEM
' The OPERABILITY of the Primary Component Cooling Water System ensures that sufficient cooling capacity is available for continued operation of safety-related equipment during normal and accident conditions. The redundant cooling capacity of this system, assuming a single failure, is consistent with the assumptions used in the safety analyses.
3/4.7.4 SERVICE WATER SYSTEM
~ The Service Water System consists of two independent loops, each of which can operate with either a service water pump train or a cooling tower pump train. The OPERABILITY of the Service Water System ensures that sufficient cooling capacity is available for continued operation of safety-related equip-ment during normal and accident conditions. The redundant cooling capacity of this system, assuming a single failure, is consistent with the assumptions used in the safety analyses, which also assumes loss of either the cooling tower or ocyf cooling.
J 3f b. Q ,'LTIMATE HEAT SINK The limitations on service water pumphouse level, and the OPERABILITY requirements for the mechanical draft cooling tower and the portable tower makeup pump system, ensure that sufficient cooling capacity is available to either: (1) provide normal cooldown of the facility or (2) mitigate the effects of accident conditions within acceptable limits. This cooling capabil-ity is provided by the Atlantic Ocean except during loss of ocean tunnel water flow, when the cooling capability is provided by the mechanical draft cooling tower with tower makeup using portable pumps. j The limitations on minimum water level and the requirements for mechanical i draft cooling tower OPERABILITY are based on providing a 30-day cooling water supply to safety-related equipment without exceeding its design basis tempera-ture and is consistent with the recommendations of Regulatory Guide 1.27,
" Ultimate Heat Sink for Nuclear Plants," March 1974.
3/4.7.6 CONTROL ROOM EMERGENCY MAKEUP AIR AND FILTRATION SUBSYSTEM The OPERABILITY of the Control Room Emergency Makeup Air and Filtration Subsystem ensures thet: (1) the allowable temperature for continuous-duty rating for the equipment and instrumentation cooled by this system is not exceeded; and (2) the control room will remain habitable for operations SEABROOK - UNIT 1 B 3/4 7-3 L A
~
,c PLANT SYSTEMS BASES l'
personnel during and following credible accident conditions. Cumulative p
operation of the system with the heaters on for 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> over a 31-day period is sufficient to reduce the buildup of moisture on the adsorbers and HEPA
!- filters. Heaters run continuously to maintain the relative humidity below
- 70%.
- The OPERABILITY of this system in conjunction with control room design i provisions is based on limiting the, radiation exposure to personnel occupying the control room to 5 rems or less whole body, or its equivalent. This limitation is consistent with the requirements of General Design Criterion 19 r
of Appendix A, 10 CFR Part 50. ANSI N510-1980 will be used as a procedural guide for surveillance testing.
3/4.7.7 SNUBBERS All snubbers are required OPERABLE to ensure that the structural integrity of the Reactor Coolant System and all other safety related systems is main-tained during and following a seismic or other event initiating dynamic loads.
size. Snubbers are classified and grouped by design and manufacturer but not by For example, mechanical snubbers utilizing the same design features of the 2-kip,10-kip and 100-kip capacity manufactured by Company "A" are of the same type. The same design mechanical snubbers manufactured by Company "B" for the purposes of this Technical Specification would be of a different type, as would hydraulic snubbers from either manufacturer.
A list of individual snubbers with detailed information of snubber location and size and of system affected shall be available at the plant in accordance with Section 50.71(c) of 10 CFR Part 50. The accessibility of Jach snubber shall be determined and approved by the Station Operation Review Committee (50RC). The determination shall be based upon the existing radiation levels and the expected time to perform a visual inspection in each snubber location as well as other factors associated with accessibility during plant operations (e.g., temperature, atmosphere, location, etc.), and the recommendations of Regulatory Guides 8.8 and 8.10. The addition or deletion of any hydraulic or mechanical Part 50. snubber shall be made in accordance witn Section 50.59 of 10 CFR Surveillance to demonstrate OPERABILITY is by performance of the require-ments of an approved inservice inspection program.
Permanent or other exemptions from the surveillance program for individual snubbers may be granted by the Commission if a justifiable basis for exemption is presented and, if applicable, snubber life destructive testing was performed to qualify the snubbers for the applicable design conditions at either the com-pletion of their f abrication or at a subsequent date. Snubbers so exempted shall be listed in the list of individual snubbers indicating the extent of the exemptions.
The service life of a snubber is established via manufacturer input and information through consideration of the snubber service conditions and SEABROOK - UNIT 1 B 3/4 7-4
- t. -
e .
^
v._
3 NT SYSTEMS BASES 3/4.7.7 SNVBBERS (Continued) '
associtted installation and maintenance records (newly installed snubbers, seal replaced, spring replaced, in high radiation area, in high temperature area, etc.). The requirement to monitor the snubber service life is included to ensure that the snubbers periodically undergo a cerformance evaluation.in view of their age and operating conditions. These records will provide statistical bases for future consideration of snubber service life. ,
3/4.7.8 SEALED SOURCE CONTAMINATION The limitations on removable contamination for sources requiring leak testing, plutonium.
including alpha emitters, is based m 10 CFR 70.39(a)(3) limits for This limitation will ensure that leakage from Byproduct, Source, '
and Special Nuclear Material sources will not exceed allowable intake values.
Sealed sources are classified into three groups according to their use, with Surveillance Requirements commensurate with the probability of damage to a source in that group. Those sources which are frequently handled are required to be tested more often than those which are not. Sealed sources which are ,
continuously enclosed within a shielded mechanism (i.e., sealed sources within radiation monitoring or boron measuring devices) are considered to be stored and need not be tested unless they are removed from the shielded mechanism.
3/4.7.9 (This specification number is not used.)
3/4.7.10 AREA TEMPERATURE MONITORING The area temperature limitations ensure that safety-related equipment will not be subjected to temperatures in excess of their environmental qualification temperatures. Exposure to excessive temperatures may degrade equipment and can cause a loss of its OPERABILITY. The temperature limits include an allowance for instrument error of 1 4.5 F.
I SEABROOK - UNIT 1 B 3/4 7-5 l
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