ML20058L661
| ML20058L661 | |
| Person / Time | |
|---|---|
| Site: | Yankee Rowe |
| Issue date: | 08/02/1990 |
| From: | Nerses V Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20058L601 | List: |
| References | |
| GL-88-17, NUDOCS 9008070374 | |
| Download: ML20058L661 (17) | |
Text
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UNITED s rA7ES ey, NUCLE AR REGULA)03Y T.OM.'4lSSION 5-j WASHINGTON, D. C. 206$5 k,.v /
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YANKEE ATOM' ' ELECTRIC COMPANY DOCKET.40. 50-H YANKEE NUCLEAR POWER STATION AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.134 License No. DPR-3 1.
The Nuclear Regulatory Comission (the Comission or the NRC) has found that:
A.
The apolication for amendment filed by Yankee Atomic Electric Company (the licensee) dated A)ril 20, 1990 as suppleme ted I
June 27, 1990, complies with tie standards and reouirL.ients af 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; I
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 set forth in 10 CFR Chapter I; D.
The issuance of this amendment will not be inimical to the comon defense and security or to the health and safety of the public; and i
E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.
L2.
Accordingly, the license is amended by changes to the Technical Specifica-tions as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. OPR-3 is hereby L
amended to reed as follows:
L (2) Technical Specifications l
The Technical Specifications contained in Appendix A, as revised i
through Amendment No.
, are hereby incorporated in the license.
The licensee shall operate the facility in accordance with the Technical Specifications.
l 9008070374 900802 PDR ADOCK 05000029 P
PDC l
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-2 August 2, 1990 3.
This license amendment is effective as of its date of issuance.
FOR THE NUCl. EAR REGULATORY COMMISSION
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UM 4 Victor Herses, Acting Director
[d Project Directorate 1-3 Division of Reactor Projects 1/11 Office of Huclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Da+.c of issuancet August 2, 1990
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ATTACHMENT TO LICFNSE AMENDMENT NO.134 i
FACILITY OPERATING LICENSE NO. OPR-3 DOCKET NO.50-029 Peplace the following pages of the Appendix A Technical Specifications with the attached pages. The revised pages are identified by Amendment number and contain vertical lines indicating the area of change, Remove Insert Vill VIII Vill-a Vill-a X11 XII 1-6 1-6 3/4 1-13 3/4 1-13 3/4 1-14 3/4 1-14 3/4 5-9 3/4 5-9 3/4 5-12 3/4 5-12 3/4 10-5 3/4 10-5 3/4 10-6 3/4 10-6 3/4 10-7 3/4 10-7 3/4 10-8.
3/4 10-8 3/4 10-9 3/4 10-9 B 3/4 10-2 B 3/4 10-2
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INDEX LIMITING CONDITIONE FOR OPERATION AND SURVEILLANcr REOUIREMENTS SECTION PAGE 3/4.9.12 SPENT TUEL PIT BUILDING IS0LATION........................
3/4 9-13
]
3/4.10 SPECIAL TEST EXCEPTIONS 3/4.10.1 SHUTDOWN MARGIN..........................................
3/4 10 1 3/4.10.2 CONTROL ROD OPERABILITY AND INSERTION LIMITS.............
3/4 10-2 3/4.10.3 PRESSURE / TEMPERATURE LIMITATION - REACTOR CRITICALITY....
3/4 10-3 e
3/4.10.4 PHYSICS TESTS............................................
1/4 10-4 3/4.10.5 REDUCED LEVEL OPERATION k'ITHOUT COLD LEG OPENING.........
3/4 10-5 3/4.10.6 REDUCED LEVEL OPERATION FOR COLD LEG OPENING.............
3/4 10-7 3/4.10.7 REDUCED LEVEL OPERATION FOR COLD LEG OPENING WITH LOW DECAY HEAT...............................................
3/4 10-9 3/4.11 RADIOACTIVE EFFLUENTS 3/4.11.1 LIQUID EFFLUENTS Concentration............................................
3/4 11-1 Dose.....................................................
3/4 11-4 Liquid Radwaste Treatment................................
3/4 11-5 Liquid Holdup Tanks......................................
3/4 11-6 J/4.11.2 GASEOUS EFFLUENTS Dose rate................................................
3/4 11-7 Dose: Noble Gases.......................................
3/4 11-10 Dose:
Iodine-131. Tritium, and Radionuclides in Particular,e Form..................................
3/4 11-11 Gaseous Radwaste Treatment...............................
3/4 11-12 Explosive Gas "ixture....................................
3/4 11-13 Cas Storage Tank.........................................
3/4 11-14 3/4.11.3 SOLID RADIOACTIVE WASTE..................................
3/4 11-15 l
YANKEE-ROWE VIII Amendment No. 80,134 l
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INDEX 3
LIMITING CONDITIONS EOR OPERATION AND SLfRVEfttANCE RE0ttIREMENTS r.
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SECTION PAGE 3/4.11.4 TOTAL D0SE...............................................
3/4 11-16 3/4.12 RADIOLOGICAL ENVIRONMENTAL MONITORING t
3/4.12.1 MONITORING PR0 GRAM.......................................
3/4 12-1 3/4.12.2 LAND USE CENSUS..........................................
3/4 12-9 3/4.12.3 INTERCOMPARISON PR0 GRAM..................................
3/4 12-10 6
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YK IEE-ROWE VIII-a Amendment No. 80,134
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INDEX s
RAsrs SECTION PAGE 3/4.9.3 D E CAY T I ME............................................... B 3 / 4 9 - 1 o
.3/4.9.4 CONTAINMENT BUILDING PENETRATIONS........................B 3/4 9-1 4
I 3/4.9.5 COMMUNICATIONS...........................................B 3/4 9-1 3/4.9.6 SHIELD TANK CAVITY MANIPULATOR CAANE OPERABILITY.........B 3/4 9-2 lt 3/4.9.7 C RANE TRAVE L - S P ENT FUEL P I T............................ B 3 / 4 9-2 e
3/4.9.8 RESIDUAL HEAT REMOVAL AND COOLANT CIRCULATION............B 3/4 9-2 3/4.9.9 CONTAINMENT PURGE FAN SHUTDOWN SYSTEM.....................B 3/4 9-2 3/4.9.10 and 3/4.9.11 WATER LEVEL - REACTOR VESSEL AND SPENT FUEL PIT..........B 3/4 9-2 3/4.9.12 SPENT FUEL PIT BUILDING IS0LATION........................ B 3/4 9-3 3/4.10 SPECIAL TEST EXCEPTIONS 3/4.10.1 SHUTDOWN MARGIN..........................................B 3/4 10-1 3/4.10.2 CONTROL ROD OPERABILITY AND INSERTION LIMITS.............B 3/4 10-1 3/4.10.3 PRESSURE / TEMPERATURE LIMITATIONS - REACTOR CRITICALITY...B 3/4 10-1.
3/4.10.4 P H YS I CS T E S TS............................................ B 3 / 4 10-1 3/4.10.5, 3/4.v,.6, and 3/4.10.7 REDUCGD LEVEL 0PERATION..................................B 3/4 10-2 g
3/4.11 RADIOACTIVE EFFLUENTS l
3/4.11.1 LIQUID EFFLUENTS.........................................B 3/4 11-1 3/4.11.2 CASEOUS EFFLUCNTS........................................B 3/4 11-2 3/4.11.3 SOLID RADI0 ACTIVE WASTE..................................B 3/4 11-5 3/4.11.4 D0SE.....................................................B 3/4 11-6 3/4.12 RADIOLOGICAL ENVIRONMENTAL MONITORING 3/4.12.1 MONITORING PR0 GRAM.......................................B 3/4 12-1 l
3/4.12.2 LAND USE CENSUS..........................................B 3/4 12-1 3/4.12.3 INTERCOMPARISON PR0 GRAM..................................B 3/4 12-2 YANKEE-ROWE XII Amendment No. 46, 47, 66, 80, 134 t
DEFINITIONS PURGE - PURGING 1.32 PURGE or PURGINO is the controlled process of discharging air or gas from a confinement to maintain temperature, pressure, humidity, concentration, or other operating condition, in such a manner that replacement air or gas is required to purify the confinement.
MEMBER (S) 0F THE PUBLIC 1.33 MEMBER (S) 0F THE PUBLIC shall include all persons who are not occupationally associated with the plant.
This category does not include employees of the utility, its contractors, or vendors. Also excluded from this category are persons who enter the site to service equipment or to make deliveries. This category does include persons who use portions of the site for recreational, occupational, or other purposes not associated with the production of electricity.
SITE BOUNDARY 1.34 The SITE BOUNDARY shall be that line beyond which the land is not owned, leased, or otherwise controlled by the licensee.
Any area within the site boundary used for residential quarters or recreational purposes shall be considered to be beyond the site boundary for purposes of meeting gaseous ef fluent dose specifications.
(Realistic occupancy factors shall be applied at these locations for the purposes of dose calculations.)
SOLIDIFICATION 1.35 SOLIDIFICATION shall be the conversion of wet wastes into a form that meets shipping and burial ground requirements.
CORE OPERATING LIMITS REPORT 1.36 CORE OPERATING LIMITS REPORT - This report is the unit-specific document that provides the core operating limits for the current operating reload cycle.
These cycle-specific operating limits shall be determined for each reload cycle in accordance with Specification 6.9.4 Plant operation within these operating limits is addressed in individual specifications.
REDUCED LEVEL OPERATION 1.37 REDUCED LEVEL OPERATION shall be the condition that exists whenever the reactor vessel water level is lower than 2 feet below the reactor vessel flange and irradiated fuel is in the reactor.
L YANKEE-ROWE 1-6 Amendment No. 80, ZZB, 134 l
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,.,,'kEICTIVITYCONTROLSYSTEMS j
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-CHARGING PUMPS - RETUELING 6 9..)DR OPERATION 3.1.2.4 At least two charging pumps in the boron injection flow path required by Specification 3.1.2.1 shall be OPERABLE.
l APPLICABILITY: MODE 6*.
ACTIONt With less than two charging pumps OPERABLE, suspend all operations involving CORE ALTERATIONS or positive reactivity changes until at least two charging pumps are restored to OPERABLE status.
)
SURVEILLANCE REOUIREMENTS 4.1.2.4 At least the above required charging pumps shall be demonstrated OPERABLE at least once per 31 days by:
a.
Starting (unless already operating) each pump from the Control Room, b.
Verifying that each pump develops a discharge flow 126 gpm, c.
Verifying pump operation for at least 15 minutes.
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- See Special Test Exceptions 3.10.5 and 3.10.7 for REDUCED LEVEL OPERATION.
l YANKEE-ROWE 3/4 1-13 Amendment No. 134 l
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.. REACTIVITY CONTROL SYSTEMS CEARGING PUMPS - SHUTDOWN
-EfMITING COMDITION FOR OPERATION 3.1.2.5 At least one charging pump in the boron injection flow path required by Specification 3.1.2.2 shall be OPERABLE.
APPLICABILITY:
MODE $*.
ACTION:
With no charging pump OPERABLE, suspend all operations involving positive reactivity changes until at least one charging pump is restored to OPERABLE.
- status, i
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stmv!ILIJLNCE REOU!REMENTS 4.1.2.5 At least the above required charging pump shall be demonstrated
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OPERABLE at least once per 31 days by:
I Sta.rting (unless already operating) the pump f rom the Control Room, a.
b.
Verifying that the pump delivers a flow 126 gpm to the Main Coolant System, and c.
Verifying pump operation for at least 15 minutes.
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- See Special Test Exceptions 3.10.5 and 3.10.7 for REDUCED LEVEL OPERATION.
l YANKEE-ROWE 3/4 1-14 Amendment No. 35, 134 i
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j EMERGENCY CORE COOLING SYSTEMS (ECCS)
ECCS SUBSYSTEMS LRiIIlNG CONDIIION FOR OPERATION The ECCS subsystems shall be OPERABLE with:
l 3.5.3 a*
As a minimum, one OPERABLE ECCS safety injection subsystem comprised of the following:
1.
One OPERABLE high pressure safety injection pump,#
2.
One OPERABLE low pressure safety injection pump,# and i
3.
An OPERABLE flow path ## capable of taking suction from the safety injection tank.
An.0PERABLE ECCS recirculation subsystem with an OPERABLE flo'w path b.*
capableoftakingsuctionfromthecontainmeggsumpand recirculating to the safety injection header c.*
An OPERABLE ECCS long term hot leg injection subsystem with an OPERABLE flow path capable of taking suction from the ECCS safety injection subsy## stem and discharging to the Main Coolant System loop 4 hot leg.
APPLICABILITY: MODE 4 and 5.
- Main coolant pressure < 1000 psig but > 300 psig.
- A maximum of one HPSI pump and one LPSI pump shell be OPERABLE whenever MCS temperature is between 200'T and 324'F.
All HPSI pumps and LPSI pumps shall be inoperable whenever MCS temperature is 1200*F, except that:
- a. One LPSI pump may be energized for surveillance testing requirements or for mixing the safety injection tank provided that either:
1.
The reactor vessel head is removed, or 2.
The LPSI pump recirculation valve (s) are open to limit pump discharge pressure to i 280 psig.
- b. Two HPSI pumps may be energized for surveillance testing requirements provided that either:
1.
The reactor vessel head is removed, or 2.
At least one pressurizer code safety valve is removed.
- c. Two HPSI pumps and one LPSI pump, lined up for series operation with discharge to the MCS hot legs, may be OPERABLE for REDUCED LEVEL OPERATION (as required by Special Test Exception 3.10.6) provided that:
1.
At least one pressurizer code safety valve is removed, or 2.
The pressurizer manway is removed.
- '4henever the MCS temperature is i 324'F, the reactor vessel head is bolted on and both pressurizer code safety valves are installed, all four loop injection MOV's and all four LPSI MOV's shall be closed and the LPSI pump recirculation valve shall be open, except that loop SI system header the isolation valves to the MCS cold legs may be open provided that associated MCS loop isolation valves are closed or when required to be open to perf orm Surveillance Requirements 4.5.2.a.1, 4.5.2.e.3(a), and 4.5.2.f.
YANKEE-ROWE 3/4 5-9 Amendment No. 49, 52, 59,.134
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EMERGENCY CORE COOLING SYSTEMS l
EAFETY INJECTION IANK LIMITING CONDITION FOR OPERATION 3.5.4 The Safety Injection Tank (SIT) shall be OPERABLE with:
a.
A minimum contained borated water voluee of 117,000 gallons, equivalent to a level of 225.5 feet.
b.
A minimum boron concentration of 2,200 ppm, and c.
A water temperature of 120'T to 130'F.Ed APPLICABILITY: MODES 1, 2, 3, 4*, 5*#, and 6#.
ACTION:
With the safety injection tank inoperable, restore the tank to OPERABLE. status within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> 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 HOT SHUTDOWN with main coolant pressure <300 psig within the fo11owing.12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
SURVEILLANCE REOUIREMENTS 4.5.4 The SIT shall be demonstrated OPERABLE:
a.
At least once per 7 days by:
1.
Verifying the contained' borated water volume in the tank, and 2.
Verifying the boron concentration of the water.
b.
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 the SIT temperature.##
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- Main coolant pressure 2300 psig.
- Whenever Special Test Exceptions 3.10.5, 3.10.6, or 3.10.7 for REDUCED LEVEL l
OPERATION are applicable.
- Not required for REDUCED LEVEL OPERATION.
YANKEE-ROWE 3/4 5-12 Amendment No. 49, 59, 92, 134 l=
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, EPEEIAL TEST EKcEPTIONS ernUEED LEVEL OPrRATION WITHOUT COLD LEC OPENING LIMITING CONDITION FOR OPERATION 3.10.5 The limitations of Specifications 3.1.2.4 and 3.1.2.5 shall be replaced by the following during REDUCED LEVEL OPERATION without a cold leg opening:
The Main Coolant System shall be vented by removing one of the a.
pressurizer code safety valves or removing the pressurizer manway, b.
As a minimum, two charging pumps with an OPERABLE flow path capable of taking suction fr. -
he safety injection tank and discharging only to the cold a em, a4'1 be OPERABLE, 4
c.
The c..re exit e m A.
a
.M1 be less than or equal to 100'F, d.
A maximum of onc
. solation valve, or its equivalent
.w (total area of a i 2
.nings less than or equal to 2
0.84 f t ), may be v' os e.
No cold leg openings may exist simultaneously with any hot leg openings, and f.
Shutdown time shall be greater than or equal to 60 hours6.944444e-4 days <br />0.0167 hours <br />9.920635e-5 weeks <br />2.283e-5 months <br />.
APPLICABILITY: MODES 5 and 6.
ACTION:
a.
With less than two charging pumps OPERABLE, restore the OPERABLE pumps within two hours, or b.
Close all hot leg openings and increase the water level higher than two f eet below the vessel flange.
SURVEILIANCE REOUIREMENTS 4.10.5.1 The two charging pumps shall be demonstrated OPERABLE within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> prior to entering REDUCED LEVEL OPERATION by a.
Starting (unless already operating) each pump from the Control Room, b.
Verifying that each pump delivers a flow 126 gpm to the Main Coolant System, and c.
Verifying pump operation for at least 15 minutes.
YANKEE-ROWE 3/4 10-5 Amendment No.
134
,'SPECfAf. TEST EXCEPTIONE RrnUctD LEVEL OPERATION WITHOUT COLD LE0 OPL*NING SURVEILLANCE REOUI_R M S (continued) 4.10.5.2 Verify that at least two of the following valve sets are in the indicated positions at least once per 12 hour1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />s:
Valve Set Valve Number Valve Penitien Set 1 (Loop 1)
SI-MOV-25 Open CS-MOV-536 Open MC-MOV-326 Open MC-MOV-501 Closed Set 2 (Loop 2)
SI-MOV-24 Open 8
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CS-MOV-537 Open MC-MOV-302 Open MC-MOV-502 Closed i
Set 3 (Loop 3)
SI-MOV-23 open CS-MOV-538 Open MC-MOV-310 Open MC-MOV-503 Closed Set 4 (Loop 4)
SI-MOV-22 Open CS-MOV-539 Open MC-MOV-318 open MC-MOV-504 Closed i
4.10.5.3 Verify that the following valves ate in the indicated positions at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> j
Valve Numbat Valve Func t ion Valve Pesitien a.
CH-MOV-523 Charging Line Isolation Closed b.
CH-MOV-522 Charging to SI and Loop Fill Open i
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i YANKEE-ROWE 3/4 10-6 Amendment No. 134
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'S7[0?AT. TEET EXCEPTIONS l.
arnUcED LEVEL OPERATION FOR COLD LEG OPENING
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LIMITING 00NDITION FOR OPEPATION 3.10.6 The limitations of Specification 3.5.3 shall be replaced by the fo110 wing during REDUCED LEVEL OPERATION with a cold leg opening when the core decay heat is >500 kW:
a.
The Main Coolant System she.11 be vented by removing one of the 4
pressurizer code safety valves or removing the pressurizer manway, b.
The ECCS subsystems shall be OPERABLE with two OPERABLE HPSI pumps and one OPF?asLE LPSI pump with an OPERABLE flow path capable of taking ;oction from safety injection tank and discharging only to the Main Coolant System Loop 4 hot leg, (MCS shall be vented before the ECCS subsystems are made operable),
c.
The core exit temperature shall be less than or equal to 100*E, d.
A maximum of one cold leg loop isolation valve, or its equivalent (total arer of all cold leg openings less than or equal to 2
0.84 ft ), may be removed, No hot leg openings may exist simultaneously with any cold leg e.
openings, and f.
Shutdown time shall be greater than or equal to 60 hours6.944444e-4 days <br />0.0167 hours <br />9.920635e-5 weeks <br />2.283e-5 months <br />.
I APPLI0 ABILITY: MODES 5 and 6
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ACTION:
i a.
With one of the required SI pumps inoperable, restore the inoperable pump to OPERABLE status within two hours, or b.
Close all cold leg openings and increase the water level higher than two feet below the vessel flange.
SURVEILIE 0E REOUIREMENTS 4.10.6.1 The above required ECCS subsystem shall be demonstrated OPERABLE within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> prior to creating cold leg opening by:
1.
Verifying that each OPERABLE HPSI pumps a) Starts from the control room.
b) Develops a discharge pressure of 1850 psig ou recirculation i
flow to the safety injection tank.
c) Operates for at least 15 minutes.
YANKEE-ROWE 3/4 10-7 Amendment No.134 1
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SPECIAL TEST EXCEPTTONS
' REDUCED LEVEL OPERATION FOR COLD LEC OPENING U_'RVEILLANCE REGUIREMENTS (Continued) 2.
Verifying that the OPERABLE LP 'I pump:
a) Starts from the control room.
b) Develops a discharge pressure of 2250 psig on recirculation flow through CS-MOV-532.
c) Operates for at least 15 minutes.
4.10.6.2 The following valves shall be verified to be in the indicated positions at least once per 12 hour1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />s:
Valve Valve Number Valve Function Position
- h. SI-MOV-515 Hot Lc4 Injection Isolation Open
- i. SI-MOV-514 Hot seg Injection Isolation Open
- 1. SI-MOV-46 HPSI Isolation Closed
- m. SI-MOV-520 HPSI Flow Control Closed
- r. CS-MOV-539 SI Heade,- Isolation to Cold Leg Closed
- s. MC-MOV-319 MCS Loop Isolation Closed t.
CH-MOV-524 Charging Hot Leg Injection Open
- u. CH-MOV-550 Charging Line Isolation Open
- v. PR-MOV-548 Auxiliary Pressurizer Spray Closed w.
PR-MOV-549 Auxiliary Pressurizer Spray Closed YANKEE-ROWE 3/4 10-8 Amendment No. 134
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RFyUCED LEVEL OPFRATION FOR__ COLD LEC OPENfNG W?TH LOW DECAY,gg&I
([,i.IsITINGCONDITIONFOROPERATION
-3.10.7 The limitations of-Specifications 3.1.2.4 and 3.1.2.5 shall be-replaced by-the following during REDUCED LEVEL OPERATION with a cold leg opening when the core decay heat.t500 kW:
a.
The Main Coolant System shall be vented by removing one of the pressurizer code safety valves or removing the pressuriser manway, b.
At least two charging pumps with an OPERABLE flow path capable of taki.a suction from safety injection tank and discharging to the Loop 4 het leg-shall-be OPERABLE, c.
The core exit temperature shall be less than or equal to 100'F, c.
A maximum of one cold les loop ieolation valve, or its equivalenti (total area of'all cold leg openings less than or equal to 0.84 ft2), may be removed, and e.
No het leg openings may exist simultaneously with any cold leg
'openin e,*.
6PPLICAEILITY:, MODES 5 and 6.
ACTION:
With less than two charging pumps OPERABLE, restore two OPERABLE
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a.
pumps within two' hours, or-b.
Close all cold leg openings and incresse the water level higher chan two feet below the vessril flange.
SURVEILLANCE REOUI'REMENTS 4.10.7.1 The two' charging pumps shall be demonstratsd OPERABLE within 2h hours prior to entering REDCUED LEVEL OPERATIO by:
a.
Starting (unless already operating) each pump from the control room, b.
Verifying that each pump delivers a flow 126 gpm to the Main Coolant System, and c.
Verifying pump operation for at least 15 minutes.
4.10.7.2 The Jollowing valves shal'. be verified to be in the indicated positions at least once per 12 hour1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />s:
Valve Number Valve FunctiSH Valve Position a.
CH-MOV-522 Charging to SI and Loop Fill Closed
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- b..CH-MOV-523 Charging Line Isolation Open c.
CH-MOV-524 Charging Line Isolation Open
-d.
CH MOV-550 Charging Line Isolation Open e.
PR-MOV-548 Auxiliary Pressurizer Spray Closed f.
PR-MOV-549 Auxiliary ?ressurizer Spray closed g.
MC-MOV-319 MCS Loop Isolation Closed YANKEE-ROWE 3/L 1. 4 Amendment No.134 1
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3/4.10 SPECIAL TEST EXCEPTIONS
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'l BAEEE 2/4.10.5. 3/4 10.6. and 3/4.10.7 RCDUCED LEVEL OPERATION
- This special tr at exception for REDUCED LEVEL OPERATION requires OPERABLE charging pumps and SI pumps, which is different from the normal requirements.
If Shutdown Cooling (SDC) is lost while at a reduced MCS level with a large hot leg opening, core uncovery may be caused by a combination of boilcff and water swept out the hot' leg opening by the steam-water mixture.
To prevent core uncovery charging pumps injecting to the cold leg is needed.
For a large cold leg opening, water could be forced out the cold leg opening by reactor vessel pressurization if core boiling begins.
The uncovery time in this case is much shorter than the hot leg opening case.
To prevent core uncovery, SI flow injecting to hot leg is needed for the cold leg opening case.
If the decay heat is sufficiently reduced, the SI flow may be substituted by charging pumps.
In either the hot or cold leg opening case water is injected to the opposite leg f rom the opening to ensure that the injected water does not bypass the core and flow out the loop opening.
To prevent LTOP, an adequate vent path, such as removing the pressurizer code safety valve, should be available during reduced level operation.
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l l-YANKEE-ROWE B 3/4 10-2 Amendment No. 134 l
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