ML20080L261
| ML20080L261 | |
| Person / Time | |
|---|---|
| Site: | Millstone  |
| Issue date: | 02/15/1995 |
| From: | Mckee P Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20080L265 | List: |
| References | |
| GL-90-06, GL-90-6, NUDOCS 9503020136 | |
| Download: ML20080L261 (33) | |
Text
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UNITED STATES g
g NUCLEAR REGULATORY COMMISSION.
WA6HINGTON, D.C. 20066 4 001 p
HORTHEAST NUCLEAR ENERGY COMPANY THE CONNECTICUT LIGHT AND POWER COMPANY THE WESTERN MASSACHUSETTS ELECTRIC COMPANY DOCKET NO. 50-336 MILLSTONE NUCLEAR POWER STATION. UNIT NO. 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.185 License No. DPR-65 1.
The Nuclear Regulatory Comission (the Commission) has found that:
A.
The application for amendment by Northeast Nuclear Energy Company, et al. (the licensee), dated April 25, 1994, supplemented September 21, 19F% complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Comission's rules and regulations set forth in 10 CFR Chapter I; B.
The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Comission; C.
There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Comission's regulations; D.
The issuance of this amer.dment will not be inimical to the common defense and security or to the health and safety of the public; and E.
The issuance of this amenimrat is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.
9503020136 950215 PDR ADOCK 05000336 p
PDR J
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s' 2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. DPR-65 is hereby amended to read as follows:
.(2)
Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No.185, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment is effective as of the date of issuance, to be implemented within 30 days of issuance.
FOR THE NUCLEAR REGULATORY COMISSION a
r Phillip F. McKee,' Director Project Directorate I-4 l
Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance:
February 15, 1995 i
I
s ATTACIMENT TO LICENSE AMENOMENT NO. ind FACILITY OPERATING LICENSE N0. DPR-65 DOCKET NO. 50-336 Replace the following pages of the Appendix A Technical Specifications with the enclosed pages. The revised pages are identified by amendment number and contain vertical lines indicating the areas of change.
Remove Insert IV IV V
V XI XI XII XII XIV XIV 3/4 1-4 3/4 1-4 3/4 1-8 3/4 1-8 3/4 1-9 3/4 1-9 3/4 1-11 3/4 1-11 3/4 1-12 3/4 1-12 3/4 1-13 3/4 1-13 3/4 1-18 3/4 1-18 3/4 4-Id 3/4 4-2 3/4 4-2 3/4 4-3 3/4 4-3 3/4 4-3a i
3/4 4-17 3/4 4-17 3/4 4-21a 3/4 4-21a 3/4 4-21b 3/4 4-21b 3/4 5-7 3/.4 5-7 3/4 5-7a 3/4 9-8a 3/4 9-8a B 3/4 1-1 B 3/4 1-1 B 3/4 1-3 B 3/4 1-3 P,3/4 1-3a B 3/4 4-2 3 3/4 4-2 B 3/4 4-2a B 3/4 5-2 8 3/4 5-2 B 3/4 9-2 B 3/4 9-2 B 3/4 9-2a
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LINITINE COMITIONS FOR OPERATION A M SURVEILLANCE REQUIREMENTS SECTION BK 3/4.0 APPLICABILITY........................
3/4 0-1 3/4.1 REACTIVITY CONTROL SYSTEMS 3/4.1.1 00 RATION CONTROL...................
3/4 1-1 Shutdown Margin - T.,,200*F 3/4 1-1 Shutdown Margin - T.,, 200*F 3/4 1-3 Boron Dilution.....................
3/4 1-4 Moderator Temperature Coefficient (NTC)........
3/41-5 Minimum Temperature for Criticality..........
3/41-7 3/4.1.2 80 RATION SYSTEMS....................
3/4 1-8 i
Flow Paths - Shutdown.................
3/4 1-8 Flow Paths - Operating 3/4 1-9 Charging Pump - Shutdown...............
3/4 1 - 11
]
Charging Pumps - Operating..............
3/4 1 - 13 Boric Acid Pumps - Shutdown 3/4 1 - 14 Boric Acid Pumps - Operating..............
3/4 1 - 15 Borated Water Sources - Shutdown...........
3/4 1 - 16 Borated Water Sources - Operating...........
3/41-18 3/4.1.3 MOVA8LE CONTROL ASSDSLIES..............
3/4 1 - 20 Full Length CEA Group Position............
3/4 1 - 20 Position Indicator Channels..............
3/41-24 CEA Drop Time 3/ 4 1 - 2 6 Shutdown CEA Insertion Limit.............
3/4 1 - 2 7 Regulating CEA Insertion Limits 3/4 1 - 28 Control Rod Drive Mechanisms 3/4 1 - 31 NILLSTONE - LNIIT 2 IV Amendment No. pp, Jpp, JJp, JJ7185 eine
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IIGEX LIMITING C01BITIONS FOR OPERATION ABB SURVEILLANCE REQUIREMENTS SECTION Egig 3/4.2 POWER DISTRIBUTION LIMITS 3/4.2.1 LINEAR HEAT RATE 3/4 2-1 3/4.2.2 Deleted T
3/4.2.3 TOTAL INTEGRATED RADIAL PEAKING FACTOR - F 3/4 2-9 7
3/4.2.4 AZIMUTHAL POWER TILT 3/4 2-10 3/4.2.5 Deleted 3/4.2.6 DNB MARGIN 3/4 2-13 3/4.3 INSTRUMENTATION 3/4.3.1 REACTOR PROTECTIVE INSTRUMENTATION 3/4 3-1 3/4.3.2 ENGINEERED SAFETY FEATURE ACTUATION SYSTE'M INSTRUMENTATION.................... 3/4 3-10 l
3/4.3.3 MONITORING INSTRUMENTATION 3/4 3-26 Radiation Monitoring 3/4 3-26 Incore Detectors 3/4 3-30 Seismic Instrumentation................. 3/4 3-32 Meteorological Instrumentation 3/4 3-36 Remote Shutdown Instrumentation.............
3/4 3-39 Fire Detection Instrumentation 3/4 3-43 Accident Monitoring...................
3/4 3-46 Radioactive Liquid Effluent Monitoring Instrumentation 3/4 3-50 Radioactive Gaseous Effluent Monitoring Instrumentation.
3/4 3-56 3/4.4 REACTOR COOLANT SYSTEM 3/4.4.1 COOLANT LOOPS AND COOLANT CIRCULATION..........
3/4 4-1 Startup and Power Operation............... 3/4 4-1 Hot Standby.......................
3/4 4-la j
Shutdown 3/4 4-lb Reactor Coolant Pumps - Shutdown 3/4 4-Id l
MILLSTONE - UNIT 2 V
Amendment No. 75, pp, pp, pp, etw pp, Jpp, JJp, Jpp,185
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IlEU BASES SECTION BE 3/4.0 APPLICABILITY
....................... B 3/4 0-1 3/4.1 REACTIVITY CONTROL SYSTEMS 3/4.1.1 B0 RATION CONTROL................... B 3/4 1-1 3/4.1.2 B0 RATION SYSTEMS................... B 3/4 1-2 3/4.1.3 MOVABLE CONTROL ASSEMBLIES
.............. B 3/4 1 - 3 a l
3/4.2 POWER DISTRIBtfTION LIMITS 3/4.2.1 LINEAR HEAT RATE................... B 3/4 2-1 3/4.2.2 Deleted 3/4.2.3 TOTAL INTEGRATED RADIAL PEAKING FACTOR - FT...... B 3/4 2-1 7
3/4.2.4 AZIMUTHAL POWER TILT................. B 3/4 2-1 3/4.2.5 Deleted 3/4.2.6 DNB MARGIN...................... B 3/4 2-2 3/4.3 INSTRUMENTATION 3/4.3.1 PROTECTIVE INSTRUMENTATION.............. B 3/4 3-1 3/4.3.2 ENGINEERED SAFETY FEATURE INSTRUMENTATION....... B 3/4 3-1 3/4.3.3 MONITORING INSTRUMENTATION.............. B 3/4 3-2 i
t MILLSTONE - UNIT 2 II Amendment No. U, M. J M,185 JMe one L
g BASES SECTIM
]$E 3/4.4 REAGTOR C0OLANT SYSTEM 3/4.4.1 COOLANT LOOPS Ale C0OLANT CIRCULATION.........
B 3/4 4-1 3/4.4.2 SAFETY VALVES B 3/4 4-1 3/4.4.3 RELIEF VALVES.....................
B 3/4 4-2 j
3/4.4.4 PRES $URIZER B 3/4 4-2a
~
3/4.4.5 STEAM GENERATORS B 3/4 4-2a 3/4.4.6 REACTOR C0OLANT SYSTEM LEAKAGE B 3/4 4-3
)
3/4.4.7 CHEMISTRY B 3/4 4-4 3/4.4.8 SPECIFIC ACTIVITY...................
B 3/4 4-4 3/4.4.9 PRESSURE / TEMPERATURE LIMITS..............
B 3/4 4-5 3/4.4.10 STRUCTURAL INTEGRITY..........'.......
B 3/4 4-7 l
1 3/4.4.11 REACTOR C0OLANT SYSTEM VENTS B 3/4 4-B 3/4.5 EE RGENCY CORE C0OLING SYSTEMS (ECCS) 3/4.5.1 SAFETY. INJECTION TABES B 3/4 5-1 1
3/4.5.2 and 3/4.5.3 ECCS SUBSYSTEMS B 3/4 5-1 3/4.5.4 REFUELING WATER STORAGE TALK (RMST)
B 3/4 5-2 3/4.6 CONTAllBIENT SYSTEMS l
3/4.6.1 PRIMARY CONTAllBIENT..................
B 3/4 6-1 j
3/4.6.2 DEPRESSURIZATION Als C0OLING SYSTEMS B 3/4 6-3 J
3/4.6.3 CONTAIIBENT ISOLATION VALVES B 3/4 6-3 3/4.6.4 co muSTIBLE GAS CONTROL B 3/4 6-4 3/4.6.5 sEC0lGARY CONTAllMENT.................
B 3/4 6-5 NILLSTOIE - IBl!T 1 XII Amendment 11o. pp, pp. 72 157.177.185 l
mso
llML BASES SECTION 3GE 3/4.9.9 and 3/4.9.10 CONTAlletENT AND RADIATION NONITORING AND CONTAINNENT PURGE VALVE ISOLATION SYSTEN B3/49-2 3/4.9.11 and 3/4.9.12 WATER LEVEL - REACTOR VESSEL A W STORAGE P00L WATER LEVEL B 3/4 9-ta l
3/4.9.13 STORAGE P0OL RADIATION MONITORING B 3/4 9-3 1
3/4.9.14 and 3/4.9.15 STORAGE P00L AREA VENTILATION SYSTEN B 3/4 9-3 3/4.9.16 SNIELDED CASK.....................
B 3/4 9-3 3/4.9.17 NOVENENT OF FUEL IN SPENT FUEL P0OL........,..
B 3/4 9-3 3/4.9.18 SPENT FUEL POOL - REACTIVITY CONDITION B 3/4 9-3 3/4.9.19 SPENT FUEL P00L - STORAGE PATTERN B 3/4 9-4 3/4.9.20 SPENT FUEL P0OL - CONSOLIDATION............
B 3/4 9-4 3/4.10 SPECIAL TEST EXCEPTIONS 3/4.10.1 SHUTDOWN NARGIN....................
B 3/4 10-1 3/4.10.2 GROUP HEIGHT Als INSERTION LINITS...........
B 3/4 10-1 3/4.10.3 PRESSURE / TEMPERATURE LINITATION -
REACTOR CRITICALITY..................
B3/410-1 3/4.10.4 PHYSICS TESTS B 3/4 10-1 3/4.10.5 CENTER CEA NISALIGl01ENT................
B 3/4 10-1 3/4.11 RADI0 ACTIVE EFFLUENTS 3/4.11.1 LIQUID EFFLUENTS B 3/4 11-1 3/4.11.2 GASE0GS EFFLUENTS...................
B 3/4 11-2 3/4.11.3 TOTAL D0SE B 3/4 11-4 i
NILLSTONE - UNIT 2 XIV Amendment No. M. J M. J M. JJ7.
om JM.JM.185
REACTIVITY CONTROL SYSTDts BORON DILINIM LIMITING COM ITION FOR OPERATION 3.1.1.3 The flow rate of reactor coolant through the core shall be 21000 gpa whenever a reduction in Reactor Coolant System boron l
concentration is being made.
APPLICABILITY: ALL MODES.
ACTION:
With the flow rate of reactor coolant through the core < 1000 gps, l
immediately suspend all operations involving a reduction in boron concentration of the Reactor Coolant System.
SURVEILLANCE REQUIRENENTS 4.1.1.3 The reactor coolant flow rate through the core shall be determined to be 21000 gpa prior to the start of and at least once l
per hour during a reduction in the Reactor Coolant System boron concentration by either:
a.
Verifying at least one reactor coolant pump is in operation, or b.
Verifying that at least one low pressure safety injection pump is in operation and supplying 2 1000 gpa through the core.
MILLSTONE - WIT 2 3/4 1 4 Amendment No.185 0107
REACTIVITY CG mt0L SYSTDis 3/4.1.2 BORATION SYSTDtp ELOW PATHS - BRITD004l LINITING COMITION FOR OPERATION 3.1.2.1 As a minimum, one of the following boron injection flow paths shall be OPERABLE:
a.
A flow path with a piping temperature of greater than 55'F from the boric acid storage tank via either a boric acid pump or a gravity feed connection and a charging pump to the Reactor Coolant System if only the boric acid storage tank in Specification 3.1.2.7a is OPERABLE, or b.
The flow path from the refueling water storage tank via a charging pump and a high pressure safety injection pump to the Reactor Coolant System if only the refueling water storage tank in Specification 3.1.2.7b is OPERA 8LE.
APPLICABILTIY: NDDES 5 and 6.
ACTION:
With none of the above flow paths OPERABLE, suspend all operations involv-ing CORE ALTERATIONS or positive reactivity changes until at least one injection path is restored to 0PERABLE status.
SEVEILLANCE REQUIREMENT 4.1.2.1 At least one of the above required flow paths shall be demon-strated OPERABLE:
a.
At least once per 7 days by exercising all testable power operat-ed valves in the flow path required for boron injection through at least one complete cycle, b.
At least once per 31 days by verifying the correct position of all manually operated valves in the boron injection flow path not locked, sealed or otherwise secured in position.
c.
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 boric acid piping temperature is greater than 55'F. This may be accom-plished by verifying that the ambient temperature in the vicinity of the boric acid piping on elevations (-)5'-0" and (-)25'-6" is greater than 55'F.
MILLSTONE - WIT 2 3/4 1-8 Amendment No. JM,185 me
REACTIVITY Colmt0L $YSTpts FLOW PATHS - SPERATIlg LIMITING Cof5! TION FOR OPERATION 3.1.2.2 The following boron injection flowpaths to the RCS via the charging pump (s) shall be OPERABLE:
a.
At least one of the following combinations:
1)
One boric acid storage tank, with the tank contents in accor-dance with Figure 3.1-1 and a piping temperature greater than 55'F, its associated gravity fetd valve, and boric acid pump.
2)
Two boric acid storage tanks, with the weighted average of the combined contents of the tanks in accordance with Figure 3.1-1 and a piping temperature greater than 55'F, their associated gravity feed valves, and boric acid pumps.
3)
Two boric acid storage tanks, each with contents in accordance with Figure 3.1-1 and a piping temperature greater than 55'F, at least one gravity feed valve, and at least one boric acid Pump.
b.
The flow path from an OPERABLE Refueling Water Storage Tank, as per Specification 3.1.2.8.b.
APPLICABILITY: MODES 1, 2, 3, and 4.
ACTION:
With fewer than the above required boron injtetion flow paths to the Reactor Coolant System OPERABLE, restore the required boron injection flow paths to the Reactor Coolant System to OPERABLE status within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> or make the reactor subcritical within the next 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> and borate to a SHUTDon MARGIN equivalent to at least 3.6% A k/k at 200*F; restore the required flow paths to l
OPERABLE status within the next 7 days or be in COLD SHUTDOW within the next 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />, MILLSTONE - UNIT 2 3/4 1-g Amendment No. JJ7,185 me 1
e d-REACTIVITY CONTROL SYSTDis GERSilE PWF - SMITD0lAl LINITING COM ITION FOR OPERATION 3.1.2.3 One charging _ pump and one high pressure safety injection pump
- in the boron injection flow path required OPERABLE pursuant to Specification 3.1.2.1 shall be OPERABLE and capable of being powered from an OPERABLE emergency bus. One additional charging pump and high pressure safety passiveventof22.8in[RABLEprovidedthattheRCSisventedthrougha injection pump may be OP APPLICABILITY: N00ES 5 and 6.
KJ18:
P a.
With less than the minimum required pumps OPERABLE, suspend all l
operations involving CORE ALTERATIONS or positive reactivity changes until at least one of the required pumps is restored to OPERABLE status.
b.
With more than the maximum allowed pumps OPERABLE take immediate action to comply with 3.1.2.3.
SEVEILLANCE REQUIREMENTS 4.1.2.3.1 The above required charging pump and high pressure safety l
injection pump shall be demonstrated OPERABLE at least once per 31 days by:
a.
Starting (unless already operating) the pump from the control
- room, b.
Verifying pump operation for at least 15 minutes, and c.
Verifying that the pump is aligned to receive electrical power from an OPERA 8LE emergency bus.
4.1.2.3.2 All charging pumps, except for the above OPERABLE pump (s),
shall be demonstrated inoperable at 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 motor circuit breakers are in the open position.
4.1.2.3.3 All high pressure safety injection pumps, except for the above OPERABLE pump (s), shall be demonstrated inoperable at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> by either:
(a) verifying that the estor circuit breakers have been disconnected from their power supply circuits, or (b) shutting and tagging the discharge valve with the key lock on the control panel (2-51-654 or 2-51-656).
i When in NODE 6 with the reactor vessel head removed then only one charging pump is required.
4 MILLSTONE - MIT 2 3/4 1-11 Amendment No.185 0100 1-WrwT-
SURVEILLANCE REQUIREMENTS (continued) 4.1.2.3.4.
The RCS passive vent (s) of greater than or equal to 2.8 square inches shall be verified to be open at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />
- whenever the vent (s) is being used for overpressure protection.
1 l
1
\\
Except when the vent pathway is provided by a valve which is locked, sealed, or otherwise secured in the open position, or by having the reactor head removed, then verify these open at least once per 31 days.
N,1,LLSTONE - LMIT 2 3/4 1-12 Amendment No.185
REACTIVITY CMTROL SYSTDis CHARRIM PIBFS - OPERATIS LINITING COMITION FM OPERATIM 3.1.2.4 At least two** charging pumps shall be OPERABLE.
l APPLICABILITY: NODES 1, 2, 3 and 4.
EI1Qti:
With only one charging pump OPERABLE, restore at least two charging pumps to OPERA 8LE status within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> or be in HOT STANDBY within the next 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />; restore at least two charging pumps to OPERABLE status within the next 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> or be in COLD SWTDOWN within the next 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />. '
SEVEILLANCE REQUIRENENTS 4.1.2.4.1 Two charging pumps shall be demonstrated OPERABLE at least once l
per 31 days on a STAGGERED TEST BASIS by:
a.
Starting (unless already operating;) each pump from the control room, and b.
Verifying that each pump operates for at least 15 minutes.
4.1.2.4.2 One charging pump shall be demonstrated inoperable at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> whenever the temperature of one or more of the RCS cold legs is < 300*F by verifying that the motor circuit breaker is in the open position.
l i
j NILLSTONE - WIT 2 3/4 1-13 Amendment No.185 0100
Rf. ACTIVITY CONTROL SYSTEMS B0 RATED WATER SOURCES - OPERATING i
LINITING COWITION FOR OPERATION 3.1.2.8 Both of the following borated water sources shall be OPERABLE:
a.
At least one of the following Boric Acid Storage Tank (s) combinations:
- 1) One boric acid storage tank, with the tank contents in accordance with Figure 3.1-1 and a minimum temperature of 55'F, its associated gravity feed valve, and boric acid Pump, or
- 2) Two boric acid storage tanks, with the weighted' average of the combined contents of the tanks in accordance with Figure 3.1-1 and a minimum temperature of 55'F, their associated gravity feed valves, and boric acid pumps, or
- 3) Two boric acid storage tanks, each with contents in accordance with Figure 3.1-1 and a minimum temperature of 55'F, at least one gravity feed valve, and at least one boric acid pump.
and
- b. The refueling water storage tank with:
- 1. A minimum contained volume of 370,000 gallons of water,
- 2. A minimum boron concentration of 1720 ppe,
- 3. A minimum solution temperature of 50*F when in MODES 1 and 2, and
- 4. A minimum solution temperature of 35'F when in MODES 3 and 4.
APPLICABILITY:
MODES 1, 2, 3 and 4.
ACTION:
j With only one borated water source OPERABLE, restore at least two borated water sources to OPERABLE status within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> or make the reactor suberitical within the next 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> and borate to a SHUTD0WN MARGIN equivalent to at least 3.6% Ak/k at 200*F; restore at least two borated water sources to OPERABLE status within the next 7 days or be in COLD SHUTDOWN within the next 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />.
MILLSTONE - L511T 2 3/4 1-18 Amendment No. JJ7185 cito
.+
i REACTOR C00LMT SYSTEN REACTOR C00LAEf PLAFS - SitlTD0tBI S M fDotAl LIMITING COMITION FOR OPERATION 3.4.1.4 A maximum of two reactor coolant pumps shall be OPERABLE.
APPLICABILITY: NODE 5 EIl0H:
With more than two reactor coolant pumps OPERABLE, take immediate action to comply with Specification 3.4.1.4.
SURVEILLANCE REQUIRENENTS 4.4.1.4 Two reactor coolant pumps shall be demonstrated inoperable at 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 motor circuit breakers have been disconnected from their electrical power supply circuits.
NILLSTONE - UNIT 2 3/4 4-Id Amendment No.185" 0111
I
~
REACTOR C0OLANT.SYSTM SAFETY VALVES LIMITING COMITION FOR OPERATION 3.4.2.1 A minimum of one pressurizar code safety valve shall be OPERABLE with a lift setting of 2500 PSIA i 15.
1 APPLICABILITY: MODE 4 when the temperature of any RCS cold leg is greater than 275*F.
ACTION:
l With no pressurizer code safety valve OPERABLE, immediately suspend all operations involving positive reactivity changes and place an OPERABLE shutdown cooling loop into operation.
3.4.2.2 All pressurizer code safety valves shall be OPERABLE with a lift setting of 2500 PSIA 1 1%.
APPLICABILITY: N00ES 1, 2 and 3.
ACTION:
With one pressurizer code safety valve inoperable, either restore the inoperable l
valve to OPERABLE status within 15 minutes or be in HOT SWTDOWN within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
SURVEILLANCE REQUIREMENTS 4.4.2 Each pressurizer code safety valve shall be demonstrated OPERABLE with a lift setting of 2500 PSIA t 1%, in accordance with Specification 4.0.5.
MILLSTONE - IMIT 2 3/4 4-2 Amendment No. pp. #7,185 sese
O REACTOR C0OLANT SYSTEN RELIEF VALVE 5 LINITING COMITION FOR OPERATION 3.4.3 toth power operated relief valves (PORVs) and their associated block l
valves shall be OPERABLE.
APPLICABILITY: N00ES 1, 2, and 3.
ACTION:
a.
With one or both PORVs inoperable and capable of being manually cycled, within I hour either restore the PORV(s) to OPERABLE status or close the associated block valve (s) with power maintained to the block valve (s): otherwise, be in at least HOT STAMBY 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 SHUTDOW within the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
b.
With one P0RV inoperable and not capable of being manually cycled, within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> either restore the PORV to OPERABLE status or close its associated block valve and remove power from the block valves restore the PORV to 0PERABLE status within the following 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or be in HOT STAM BY 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 SETD0WN within the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
c.
With both P0RVs inoperable and not capable of being manually cycled, within I hour either restore at least one PORV to OPERABLE status or close the associated block valves and remove power from the block valves and be in at least NOT STAE8Y 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 H0T SHUTDOW within the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
d.
With one or both block valves inoperable, within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> restore the block valve (s) to 0PERABLE status or place its associated P0RV(s) controls in the 'close" position. Restore at least one block valve to OPERABLE status within the next hour if both block valves are inoperable: restore any remaining inoperable block valve to 0PERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> otherwise be in at least HOT STA E8Y 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 SWTDOW within the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
)
NILLSTONE - WIT 2 3/4 4-3 Amendment No. JJ. 77, pp. JJJ,185 onee
O REACTOR C00LANT SYSTEN SURVEILLANCE REQUIREMENTS 4.4.3.1 In addition to the requirements of Specification 4.0.5, each PORY l
shall be demonstrated OPERABLE:
I a.
Once per 31 days by performance of a CHAIGIEL FMCTIONAL TEST, excluding valve operation, and b.
Once per 18 months by performance of a CHAMEL CALIBRATION.
c.
Once per 18 months the P0RVs shall be bench tested at conditions representative of N0 DES 3 or 4.
4.4.3.2 Each block valve shall be demonstrated OPERABLE once per 92 days by operating the valve through one complete cycle of full travel. This demonstration is not requ< red if a PORY block valve is closed and power removed to meet Specification 3.4.3 b or c.
l 1
i i
MILLSTONE - UNI 7 2 3/4 4-3a Amendment No. pp, pp,185 esos
~
Rf. ACTOR C00LAN SYSTEp 1/LL1_ERF.5EEE/TDrERATURE LIMITS REACTOR C00UNT SYST5ll LIMITING COMITION TOR OPERATION i
3.4.9.1 The Reactor Coolant System (except the pressurizer) temperature and pressure shall be limited in accordance with the limit lines shown on Figure 3.4-2 during heatup, cooldown, criticality, and inservice leak and hydrostatic testing with:
A maximum heatup of 20*F in any one hour period with T, a.
at or below 110'F, 30*F in any one hour period with T at or below 140*Fandabove110*F,and50*FinanyoE hour period with T, above 140*F.
b.
A maximum cooldown of 80*F in any one hour period with T above300*Fandamaximumcooldownof30*Finanyonehou7 periodwithT*EperiodwithT at or below 300*F and above.200*F, and 20*F in any one hou at or below 200*F and above 120*F, and 5'F in any one hou Pperiod with T at or below 120'F.
c.
A maximum temperature change of 5'F in any one hour period, during hydrostatic testing operations above system design pressure.
APPLICABILITY: NODES 1, 2*, 3, 4 and 5.
EIIQli:
With any of the above limits exceeded, restore the temperature and/or pressure to within the limit within 30 minutes; perform an engineering evaluation to determine the effects of the out-of-limit condition on the structural integrity of the Reactor Coolant System; determine that the Reactor Coolant System remains acceptable for continued operations or i
be in at least HDT STAW8Y within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and reduce the RCS T and pressure to less than 200*F and 500 psia, respectively, withi h he following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
l
- See Special Test Exception 3.10.3.
l NIgLSTONE-IMIT2 3/4 4-17 Amendment No. 9, M. JU,185 l
REACT 0K COOLANT SYSTEM QVERPRESSURE PROTECTION SYSTEMS LINITING C0leITION FOR OPERATION I
3.4.9.3 Both power operated relief valves (PORVs) shall be OPERABLE with a i
lift setting of less than or equal to 450 psig.
APPLICABILITY: N00E 4 when the temperature of any RCS cold leg is less t'han or equal to 275'F. MODE 5 and N00E 6 when the head is on the reactor vessel and the RCS is not vented through a 2.8 square inch or larger vent.
1 ACTION:
a.
With one P0RV inoperable in N00E 4 restore the inoperable PORY to l
l OPERABLE status within 7 days or depressurize and vent the RCS through a 21.4 square inch vent (s) within the next 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.
l b.
With one PORV inoperable in N0 DES 5 or 6, either (1) restore inoperable PORY to OPERABLE status within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, or (2) complete depressurization and vent the RCS through at least a 1.4 square inch vent within a total of 32 hours3.703704e-4 days <br />0.00889 hours <br />5.291005e-5 weeks <br />1.2176e-5 months <br />.
c.
With both PORVs inoperable, complete depressurization and vent the RCS through at least a 22.8 square inch vent (s) within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.
d.
With the RCS vented per ACTIONS a, b, or c. verify the vent pathway at least once per 31 days when the pathway is provided by a valve (s) that is locked, sealed, or otherwise secured in the open positions otherwise, verify the vent pathway every 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
e.
IntheeventeitherthePORVsortheRCSvent(s)areusedto mitigate an RCS pressure transient, a Special Report shall be prepared and submitted to the Commission pursuant to Specification 6.9.2 within 30 days. The report shall describe the circumstances initiating the transient, the effect of the PORVs or RCS vent (s) on the transient, and any corrective action necessary to prevent recurrence.
MILLSTONE - UNIT 2 3/4 4-21a Amendment No. 5, UJ,185 ones C
1 SURVEILLANCE REQU1AEM NT 4.4.9.3.1 Each PORY shall be demonstrated OPERABLE by:
a.
Performarca of a
CHANNEL FUNCTIONAL TEST on the PORY actuation channel, but excluding valve operation, within 31 days prior to entering a condition in which the PORV is reqvired OPERABLE and at least once per 31 days thereafter when the PORV is required OPERABLE.
b.
Performance of a CHANNEL CALIBRATION on the PORV actuation channel at least once per 18 months.
c.
Verifying the PORY block valve is open at least once per 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> l
when the PORV is being used for overpressure protection.
d.
Testing in accordance with the inservice test requirements of Specification 4.0.5.
MILLSTONE - int!T 2 3/44-21b Amendment No. 5, #7 185 esse
EMERGENCY CORE C00 LIM SYSTEMS ECCS SUBSYSTEMS - T
< 300*F LINITING CONDITION FOR OPERATION 3.5.3 As a minimum, one ECCS subsystem comprised of the following shall be OPERABLE:
a.
One ' OPERABLE high-pressure safety injection pump, and b.
An OPERABLE flow path capable of taking suction from the refuel-ing water storage tank on a safety injection actuation signal and automatically transferring suction to the containment sump on a sump recirculation actuation signal.
APPLICABILITY: MODES 3* and 4.
ACTION:
a.
With no ECCS subsystem OPERABLE, restore at least one ECCS subsystem to CPERABLE status within one hour or be in COLD SHUTDOWN within the next 20 hours2.314815e-4 days <br />0.00556 hours <br />3.306878e-5 weeks <br />7.61e-6 months <br />.
b.
In the event the ECCS is actuated and injects water into the Reactor Coolant System, a Special Report shall be prepared and submitted to the Commission pursuant to Specification G.9.2 within 90 days describing the circumstances of the actuation and the total accumulated actuation cycles to date.
l c.
With two or more high pressure safety injection pumps OPERABLE and the temperature of one or more of the RCS cold legs s 275'F take immediate action to have a maximum of one high pressure safety injection pump OPERABLE.
SURVEILLANCE REQUIREMENTS 4.5.3.1 The ECCS subsystem shall be demonstrated OPERABLE per the applicable Surveillance Requirements of 4.5.2.
With pressurizer pressure < 1750 psia.
A maximum of one high-pressure safety injection pump shall be OPERABLE whenever the temperature of one or more of the RCS cold legs is s 275'F.
NILLSTONE - UNIT 2 3/4 5-7 Amendment No. #,185 0113
DIERREEY CORE COOLING SYSTDt3 BRVEILLANCE REQUIRDIENS (continued) 4.5.3.2 All high-pressure safety injection pumps, except the above required OPERA 8LE pump, shall be demonstrated inoperable at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> whenever the temperature of one or more of the RCS cold legs is 1 275'F by either:
(1) verifying that the motor circuit breakers have been disconnected from their power supply circuits; or (2) shutting and tagging the discharge valve with the key lock on the control panel (2-SI-654 or 2-SI-656).
l MILLSTONE - IMIT 2 3/4 5-7a Amendment No. 77 185 ens
REFUELING GPERATIONS SURVEILLANCE REQUIRENENTS 4.9.8.1 At least one shutdown cooling loop shall be verified to be in operation and circulating reactor coolant at a flow rate greater than or equal to 1000 gpa and consistent with decay heat requirements at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
4.9.8.2 Once per 7 days, the required shutdown cooling loops, if not in operation, shall be determined OPERABLE by verifying correct breaker align-ments and indicated power availability for pump and shutdown cooling valves, or:
Verifying that the reactor vessel water level is at or above the vessel flange, the reactor vessel pit seal is installed, and greater than 370,000 gallons of water is available as a heat sink, as indicated by either:
a.
refuel pool level greater than 23 feet above the reactor vessel flange, or b.
the combined volume of the refuel pool and refueling water storage tank exceeds 370,000 gallons and a flow path is available from the refueling water storage tank to the refuel pool.
NILLSTONE - UNIT 2 3/4 9-8a Amendment No. JP,185 0114
3/4.1 REACTIVITY CONTROL SYSTDt3 BAAE1 3/4.1.1 B0 RATION CONT ltDL 1/4.1.1.1 and 3/4.1.1.2 SHUTDOWN MARGIN A sufficient SHitTDOWK MARGIN ensures that 1) the reactor can be made subcritical from all operating conditions, 2) the reactivity transients associated with postulated accident conditions are controllable within acceptable limits, and 3) the reactor will be maintained sufficiently subcritical to preclude inadvertent criticality in the shutdown condition.
SHL1TDOWN MARGIN requirements vary throughout core life as a function of fuel depletion, RCS boron concentration, and RCS T. Tne most restrictive condition occurs at E0L, with T at no load operating temperature, and is associated with a postulated steam line break accident and resulting i
uncontrolled RCS cooldown.
In the analysis of this accident, the minimum SHLITDOWN MARGIN specified in the CORE OPERATING LIMITS REPORT is initially l
required to control the reactivity transient. Accordingly, the SHllTDOWN MARGIN required by Specification 3.1.1.1 is based upon this limiting condition and is consistent with FSAR accident analysis assumptions.
For ear ter periods during the fuel cycle, this value is conservative. With T.,1200'F, the reactivity transients resulting from any postulated accident are minimal ed the reduced SHUTD0WN MARGIN specified in the CORE OPERATING LINITS REPORT provides adequate protection.
3/4.1.1.3 B0RON DILUTION AND ADDITION A minimum flow rate of at least 1000 GPM provides adequate mixing, prevents i
stratification and ensures that reactivity changes will be gradual durits boron concentration changes in the Reactor Coolant System. This was done to prevent vortexing in the SOCS when in mid-loop operation, while being consistent with boron dilution analysis assumptions. A flow rate of at least 1000 GPM will circulate the full Reactor Coolant System volume in approximately 90 minutes. With the RCS in mid-loop operation, the Reactor Coolant System volume will circulate in approximately 25 minutes. The reactivity change rate associated with boron concentration changes will be within the capability for operator recognition and control.
3/4.1.1.4 DEBERATOR TENERATURE C0 EFFICIENT (MTC)
The limitations on MTC are provided to ensure that the assumptions used in the accident and transient analyses remain valid through each fuel cycle. The surveillance requirements for measurement of the M"C during each fuel cycle are adequate to confirm the MTC value since this coefficient changes slowly due principally to the reduction in RCS boron concentration associated with fuel burnup. The confirmation that the measured MTC value is within its limit provides assurance that the coefficient will be maintained within acceptable values throughout each fuel cycle.
NILLSTONE - LSIIT 2 5 3/4 1-1 Amendment No. J M, JM, 185 ens
BASES 3/4.1.2 B0 RATION SYSTEMS (Continued)
The analysis to determine the boration requirements assumed that the Reactor Coolant System is borated concurrently with cooldown.
In the limiting situation when letdown is not available, the cooldown is assumed to be initiated within 26 hours3.009259e-4 days <br />0.00722 hours <br />4.298942e-5 weeks <br />9.893e-6 months <br /> and cooldown to 220*F, is completed in the next 28 hours3.240741e-4 days <br />0.00778 hours <br />4.62963e-5 weeks <br />1.0654e-5 months <br />.
With the RCS temperature below 200*F, one injection system is acceptable without single failure consideration on the basis of the stable reactivity condition of the reactor and the additional restrictions prohibiting CORE ALTERATIONS and positive reactivity change in the event the single injection system becomes inoperable.
The boron capability required below 200*F is based upon providing a SHt1TDOWN MARGIN within the limit specified in the CORE OPERATING LIMI"S REPORT at 140*F after xenon decay. This condition requires either 3750. gallons of 2.5% boric acid solution from the boric acid tanks or 57,300 gallons of 1720 ppe borated water from the refueling water storage tank.
The maximum boron concentration require;sei3 (3.5%) and the minimum temperature requirement (55'F) for the Boric Acid Storage Tank ensures that boron does not precipitate in the Boric Aci1 System..The daily surveillance requirement provides sufficient assurance that the temperature of the tank will be maintained higher than 55'F at all times.
A minimum boron concentration of 1720 ppe is required in the RWST at all times in order to satisfy safety analysis assumptions for boron dilution incidents and other transients using the RWST as a borated water source as well as the analysis assumption to determine the boration requirement to ensure adequate shutdown margin.
A maximum of two charging pumps OPERABLE, when RCS temperature is less than 300'F, ensures that the maximus inadvertent dilution flow rate as assumed in the boron dilution analysis is 80 gallons per minute.
The requirements for maximum pumping capability to reduce shutdown risk and low temperature overpressure protection are met by balancing Ge number of OPERABLE pumps with PORVs and RCS vents. An LTOP accident scenario assumes all DPERABLE s start, one relief path fails, and RCS pressure then must remain less the 10CFR50, Appendix G limits. For shutdown risk reduction, it is desirable to have the maximum pump capacity and maintain the RCS full (notvented). The scenarios considered by these technical specifications are as follows:
(1) A minimum pumping capability of I charging and 1 HPSI pump with relief from 2 PORVs (to account for single failure); (2) pumping capacity of 2 charging pumps and 1 HPSI pump or 2 charging pumps and 2 HPSI pumps with relief from an RCS passive vent of greater than or equal to 2.8 square inches.
To further reduce shutdown risk by maximizing pumping capacity, a HPSI pump may be made inoperabh but available at short notice by shutting its discharge valve with the key lock on the control panel.
MILLSTONE - UNIT 2 B 3/4 1-3 Amendment No. 17 pl. 72. IJf.
lie Ill.Iffe'85 one i
18111 3/4.1.3 MOVEABLE CONTROL ASSEMBLI_ES The specifications of this section ensure that (1) acceptable power distribution limits are maintained, (2) the minimum SHUTDOWN MARGIN is maintained, and (3) the potential effects of a CEA ejection accident are limited to acceptable levels.
The ACTION statements which permit limited variations from the basic requirements are accompanied by additional restrictions which ensure that the original criteria are met.
The ACTION statements applicable to an immovable or untrippable CEA and to a large misalignment (120 steps) of two or more CEAs, require a prompt shutdown of the reactor since either i
s NILLSTONE - UNIT 2 B 3/4 1-3a Amendment No. JJ. 117,185 l
ens
REACTOR C00LAlfT SYSTDI BASES During operation, all pressurizer code safety valves must be OPERA 8tE to prevent the RCS from being pressurized above its safety limit of 2750 psia.
The combined relief capacity of these valves is sufficient to limit the Reactor Coolant System pressure to within its Safety Limit of 2750 psia following a complete loss of turbine generator load while operating at RATED THERMAL POWER and assuming no reactor trip until the first Reactor Protective System trip setpoint (Pressurizer Pressure-High) is reached (i.e., no credit is taken for i
a direct reactor trip on the loss of turbine) and also assuming no operation of the pressurizer power operated relief valve or steam dump valves.
3/4.4.3 RELIEF VALVES The power operated relief valves (PORVs) operate to relieve RCS pressure below the setting of the pressurizer code safety valves. These relief valves have remotely operated block valves to provide a positive shutoff capability should a relief valve become inoperable. The electrical power for both the relief valves and the block valves is capable of being supplied from an emer-t gency power source to ensure the ability to seal this possible RCS leakage path.
j i
With the PORV inoperable and capable of being manually cycled, either the 1
PORV must be restored, or the flow path isolated within I hour. The block valve
{
should be closed, but the power must be maintained to the associated block valve, i
since removal of power would render the block valve inoperable. Although the PORV may be designated inoperable, it may be able to be manually opened and closed and in this manner can be used to perform its function.
PORV inoper-ability may be due to seat leakage, instrumentation problems, automatic control problems, or other causes that do not prevent manual use and do not create a l
possibility for a small break LOCA. Operation of the plant may continue with the PORY in this inoperable condition for a limited period of time not to exceed the next refueling outage, so that maintenance can be performed on the PORVs to eliminate the degraded condition. The PORVs should normally be available for automatic mitigation of overpressure events and should be returned to 0PERABLE status prior to entering MODE 4 after a refueling outage.
Quick access, to the PORV for pressure control can be made when power remains on the closed block valve.
If one block valve is inoperable, then it must be restored to OPERABLE status, or the associated PORV placed in the closed position. The prime importance for the capability to maintain closed the block valve is to isolate a stuck open PORV.
Therefore, if the block valve cannot be restored to 0PERABLE status within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />, the required action is to place the associated PORV in the closed position to preclude its automatic opening for an overpressure event and to avoid the potential for a stuck open PORV at a time that the block valve is inoperable.
Althouqh the block valve may be designated inoperable, it may be able to be manual'y opened and closed and in this manner can be used to perform its func-tion. Block valve inoperability may be due to seat leakage, instrumentation problems, automatic control problems, or other causes that do not prevent manual use and do not create a possibility for a small break LOCA. This condition is MILLSTONE-LNIIT 2 B 3/4 4-2 Amendment No. JJ, F, M, M. R,18E em
Eg&[ TOR COOLANT SYSTEM BASES only intended to permit operation of the plant for a limited period of time not to exceed the next refueling outage so that maintenance can be performed on the block valve to eliminate the seat leakage condition or other similar concern.
The block valve should normally be available to allow PORY operation for auto-matic mitigation of overpressure events. The block valves should be returned to OPERABLE status prior to entering MODE 4 after a refueling outage.
If more than one PORY is inoperable and not capable of being manually cycled, it l
is necessary to either restore at least one valve within the completion time of I hour or isolate the flow path by closing and removing the power to the associ-ated block valve, cooldown, depressurize, and vent the RCS.
3/4.4.4 PRESSURIZER An OPERABLE pressurizer provides pressure control for the reactor coolant system during operations with both forced reactor coolant flow and with natural circulation flow. The minimum water level in the pressurizer assures the pressurizer heaters, which are required to achieve and maintain pressure control, remain covered with water to prevent failure, which occurs if the heaters are energized uncovered. The maximum water level in the pressurizer ensures that this parameter is maintained within the envelope of operation assumed in the safety analysis. The maximum water level also ensures that the RCS is not a hydraulically solid system and that a steam bubble will be pro-
-vided to accommodate pressure surges during operation. The steam bubble also protects the pressurizer code safety valves and power operated relief valve against water relief. The requirement that a minimum number of pressurizer heaters be OPERABLE enhances the capability of the plant to control Reactor i
Coolant System pressure and establish and maintain natural circulation.
The requirement that 130 kW of pressurizer heaters and their associated controls be capable of being supplied electrical power from an emergency bus provides assurance that these heaters can be energized during a loss of off-site power condition to maintain natural circulation at HDT STAE8Y.
3/4.4.5 STEAM GENERATORS The Surveillance Requirements for inspection of the steam generator tubes ensure that the structural integrity of this portion of the RCS will be unintained. The program for inservice inspection of steam generator tubes is based on a modification of Regulatory Guide 1.83, Revision 1.
Inservice inspection of steam generator tubing is essential in order to maintain surveillance of the conditions of the tubes in the event that there is MILLSTONE-UNIT 2 8 3/4 4-2a Amendment No. JJ, J7, JJ, 55, 57,185 osco
EMERRENCY CORE C00LINB SYSTEMS BASES I
The purpose of the ECCS throttle valve surveillance requirements is to provide assurance that proper ECCS flows will be maintained in the event of a LOCA.
Maintenance of proper flow resistance and pressure drop in the piping system to each injection point is necessary to:
(1) prevent total pump flow from exceeding runout conditions when the system is in its minimum resistance configuration,(2) provide the proper flow split between injection points in accordance with the assumptions used in the ECCS-LOCA analyses, and (3) provide an acceptable level of total ECCS flow to all injection points equal to or above that assumed in the ECCS-LOCA analyses.
Only one HPSI pump may be OPERABLE in MODE 4 with RCS temperatures less than or equal to 275'F due to the restricted relief capacity with Low-Temperature Overpressure Protection System. To reduce shutdown risk by having additional pumping capacity readily available, a HPSI pump may be made inoperable but available at short notice by shutting its discharge valve with the key lock on the control panel.
3/4.5.4 REFUELING WATER STORAGE TAf0( (RWST)
The OPERABILITY of the RWST as part of the ECCS ensures that a sufficient supply of borated water is available for injection by the ECCS in the event of a LOCA. The limits on RWST minimum volume and boron concentration ensure that
- 1) sufficient water is available within containment to permit recirculation cooling flow to the core, and 2) the reactor will remain subcritical in the cold condition following mixing of the RWST and the RCS water volumes with all control rods inserted except for the most reactive control assembly. These assumptions are consistent with the LOCA analyses, l
1 NIL! STONE - LS11T 2 B 3/4 5-2 Amendment No. (), J77,185 esie
REFUELIM OPERATIONS BASES 3/4.9.6 CRANE OPERABILITY - CONTAlletENT BUILDING The OPERABILITY requirements of the cranes used for movement of fuel assen-blies ensures that:
- 1) each crane has sufficient load capacity to lift a fuel element, and 2) the core internals tnd pressure vessel are protected from exces-sive lifting force in the event they are inadvertently engaged during lifting operations.
3/4.9.7 CRANE TRAVEL - SPENT FUEL STORAGE BUILDING The restriction on movement of loads in excess of the nominal weight of a 4
fuel assembly and CEA over irradiated fuel assemblies ensures that no more than the contents of one fuel assembly will be ruptured in the event of "a fuel hand-ling accident. Specific analysis has been performed for the drop of a consoli-dated fuel storage box on an intact fuel assembly. This assumption is consistent j
with the activity release assumed in the accident analyses.
3/4.9.8 SHUTDOW COOLING AE C0OLANT CIkCULATION The requirement that at least one shutdown cooling loop be in operation at
[
2 1000 gpa ensures that (1) sufficient cooling capacity is available to remove I
decay heat and maintain the water in the reactor pressure vessel below 140*F as required during the REFUELING MODE, (2) sufficient coolant circulation is
[
maintained through the reactor core to minimize the effects of a boron dilution incident and prevent. boron stratification, and (3) is consistent with boron dilution analysis assumptions.
The requirement to have two shutdown cooling loops 0PERABLE when the refuel pool is unavailable as a heat sink ensures that a single failure of the operating shutdown cooling loop will not result in a complete loss of decay heat removal capability. With the reactor vessel water level at or above the vessel flange, the reactor vessel pit seal installed, and a combined available volume of water in the refueling pool and refueling water storage tank in excess of 370,000 gallons, a large heat sink is readily available for core cooling. Adequate time is thus available to initiate emergency procedures to provide core cooling in the event of a failure of the operating shutdown cooling loop.
3/4.9.9 and 3/4.$.19 CONTAllelENT RADIATION ENITORING AE CONTAlle4ENT PURGE VALVE ISOLATIGH SYSTEN The OPERABILITY of these systems ensures that the containment purge valves will be automatically isolated upon detection of high radiation levels within the containment.
The OPERABILITY of these systems is required to restrict the release of radioactive material from the containment atmosphere to the environment.
NIgLSTONE-WIT 2 8 3/4 9-2 Amendment No. 77, 71. 177,185
e BASES (Continued) 3/4.9.11 and 3/4.9.12 WATER LEVEL-REACTOR VESSEL AND STORAGE P0OL WATER LEVEL The restrictions on minimum water level ensure that sufficient water depth is available to remove 99% of the assumed 105 iodine gap activity released from 1
the rupture of an irradiated fuel assembly. The minimum water depth is consistent cith the assumptions of the accident analysis.
i
[IjLST0NE-IMIT2 8 3/4 9-2a Anemhent No.185 l
.