ML20198C336
| ML20198C336 | |
| Person / Time | |
|---|---|
| Site: | Yankee Rowe |
| Issue date: | 05/14/1986 |
| From: | Lear G Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20198C327 | List: |
| References | |
| NUDOCS 8605220395 | |
| Download: ML20198C336 (22) | |
Text
{{#Wiki_filter:* YANKEE ATOMIC ELECTRIC COMPANY DOCKET NO. 50-029 YANKEE NUCLEAR POWER STATION AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 92 License No. DPR-3
- 1. The Nuclear Regulatory Commission (the Commission) has found that:
A. The application for amendment by Yankee Atomic Electric Company (the licensee) dated May 26, 1981 as revised January 23, 1984 . and February 26, 1985 complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission'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 Commission; 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 Commission's regulations; D. The issuance of this amendment 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 amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied. 6 P
- 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-3 is hereby amended to read as follows:
(2) Technical Specifications The Technical Specifications contained in Appendix A as revised through Amendment No. 92 , 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 its issuance.
FOR THE NUCLEAR REGULATORY COMMISSION Geo g Lear, Director Project Directorate #1 Division of PWR Licensing-A
Attachment:
Changes to the Technical Specifications Date of Issuance: May 14, 1986 E _m
ATTACHMENT TO LICENSE AMENDMENT NO. 92 FACILITY OPERATING LICENSE N0. DPR-3 . DOCKET NO. 50-029 Revise Appendix A Technical Specifications by removing the pages ',dentified below and inserting the enclosed pages. The revised pages are identified by the captioned amendment number and contain marginal lines indicating the area of change. REMOVE INSERT 3/4 1-21 3/4 1-21 3/4 1-22 3/4 1-22 3/4 3-18 3/4 3-18 3/4 3-32 3/4 3-32 3/4 3-33 3/4 3-33 3/4 4-5 ,3/4 4-5* 3/4 4-Sa ' 3/4 4-Sa 3/4 5-3 3/4 5-3* 3/4 5-4 3/4 5-4 3/4 5-11 3/4 5-11* 3/4 5-12 3/4 5-12 3/4 7-35 3/4 7-35 3/4 8-8 3/4 8-8 3/4 8-11 3/4 8-11 B 3/4 4-9 8 3/4 4-9 8 3/4 4-10 B 3/4 4-10* B 3/4 5-1 B 3/4 5-1* B 3/4 5-2 B 3/4 5-2 6-7 5-7
*0verleaf page provided to maintain document completeness. No changes contained on this page.
. REACTIVITY CONTROL SYSTEMS BORATED WATER SOURCES - OPERATING
~ '
. LIMITING CONDITION FOR OPERATION .
3.1.2.11 Each of the following borated water sources shall,be OPERABLE:
- a. The' boric acid mix tank *and associated heat traci'ng with:
- 1. A minimum contained borated water volume of 1500 gallons, equivalent 'to a tank level of > 3.6 feet,
- 2. 12 to 12.5% by weight boric acid solution,
- 3. A minimum solution temperature of 150 F.
- b. The safety injection tank (SIT) with:
- 1. A minimum contained borated' water volume of 117,000 gallons .
of water, equivalent to a tank level of >25.5 feet, j 2. A minimum boron concentration of 2200 ppm, and 3 ,- A solution temperature of 120 F to 130 F. l APPLICABILITf: MODES 1, 2, 3 and 4. ACT' ION: With either the boric acid mix tank or the safety injection tank inoperable, provided the other required source is OPERABLE, restore the inoperable tank to OPERABLE status within 72 hours or be in
.at least HOT STANDBY within the next 6 hours and borated to a SHUTDOWN MARGIN (all control rods inserted) equivalent to at least
. 5% ak/k at 200 F; restore the inoperable tank to OPERABLE status within the next 7 days or be in COLD SHUTDOWN within the next 30 hours.
SURVEILLANCE REQUIREMENTS l l 4.1.2.11 Each borated water source shall be demonstrated OPERABLE: l . l i I i l i VANKEE-ROWE 3/4 1-21 Amendment No. 49, 92
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"- REACTIVITY , CONTROL SYSTEMS - '# SURVE*1'. LANCE REQUIREMENTS (Continuedy -
. a. At least once per 7 days by: .
~
~
- 1. Verifying the boron concentration of the safety injection
~* tank wate: , and the boric acid concentration of the boric -
acid mix tank water, ,
- 2. EVerifyingthecontainedboratedwatervolumeofeachwater
, source, and I
- 3. IVerifying the boric acid six tank solution temperature. !
l
- b. At least once per 24 hours by verifying the SIT temperature.
/
/
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? l l . YANKEE-ROWE 3/4 1-22 Amendment No. ///9, 92
TABLE 3.3-4 .
*C .
RADIATION HONITORING INSTRUMENTATION , e 5 HINIMUM Il CHANNELS APPLICABLE , ALARM HEASURENENT . INSTRUMENT OPERABLE HODES SETPOINT RANCE ACTION
- 1. AREA HONITORS
- a. Spent Fuel Pit Area .. .
- 1) Fuel Manipulator 1 * < 5 mr/hr or'2 x 1.0 - 50 mR/hr* 11 Eackground, which-ever is greater
- b. Containment
. 1) Fuel Manipulator 1
- jt_10 ar/hr or 2 x 1.0 - 1000 mR/hr* 12 l background, which- -
1[ ever is greater . s. i' g 2. PROCESS HONITORS
- a. Containment
- 1) Hain Coolant System 1 1, 2, 3, & 4 NA 10 - 106 ep. 13 Leakage Air Par-ticulate Monitor
- b. Radioactive Liquid Monitors -
- 1) Steam Generator 1(1) 1, 2, 3, & 4 $ 6,000 cpm or 2x 10 - 10 cpa, or 14 Blowdown Honitors background, whichever 10 - 10l cpm
. is greiter * -
- g. .
3 3. ACCIDENT-EMERCENCY NONITORS , R- *
@ a. High Level Radiation - " Honitor 1 At all times --< 5 R/hr 1.0 - 1000 R/hr* 14 z
O ' *
*
- Indicated upper end of measurement range is minimum re, quired. Actual measurement range may exceed
$h.
that statrA 1. M3 .**s m .
INSTRUMENTATION ,
- RADIOACTIVE LIOUID EFFLUENT INSTRUMENTATION LIMITING CONDITION FOR OPERATION i
3.3.3.6 The radioactive liquid effluent monitoring instrumentation channels shown in Table 3.3-8 shall be OPERABLE with their alarm / trip setpoints set to ensure that the limits of Specification 3.11.1.1 are not exceeded. The alarm / trip setpoints of these channels shall be determined in accordance with the Offsite Dose Calculation Manual (ODCM). APPLICABILITY As shown in Table 3.3-8. ACTION
- a. With a radioactive liquid effluent monitoring instrumentation channel alarm / trip setpoint less conservative than a value which will ensure that the limits of Specification 3.11.1.1 are met,
, without delay, take actions to suspend the release of radioactive liquid effluents monitored by the affected channel, or declare the channel inoperable, or change the setpoint so it is acceptably conservative. With the successful completion of the requirements of the ACTION statement, the provisions of Specification 6.9.4 for the preparation and submittal of Licensee Event Reports are not applicable.
- b. With less than the minimum number of radioactive liquid effluent monitoring instrumentation channels OPERABLE gtake the ACTION shown in Table 3.3-8. Exert reasonable efforts to return the ,
instrument (s) to OPERABLE status within 30 days and if unsuccessful, , in lieu of Licensee Event Report, explain in the next Semiannual Radioactive Effluent Release Report the reason for delay in, correcting the inoperability.
- c. The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.
SURVEILLANCE REOUIREMENTS
- 4.3.3.6 Each radioactive liquid effluent monitoring instrumentation channel shall be demonstrated OPERABLE by performance of the CHANNEL CHECK, SOURCE CHECK, CEANNEL CALIBRATION, and CRANNEL FUNCTIONAL TEST operations during the MODES and at the frequencies shown in Table 4.3-6.
i YANKEE ROWE 3/4 3-32 AMENDMENT No. 8d> 92
-,-. - v- -, -- , ,,
TABLE 3.3-8 , RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION MINIMUM CRANNELS INSTR UMENT OPERABLE APPLICABILITY ACTION
- 1. Grows Radioactivity Monitors Providing Automatic Isolation
- a. Liquid Radwaste Effluent Line (1) At all times 15
- b. Steam Generator Blowdown Tank Effluent Line (1) At all times 16
- 2. Continuous Composite Samplers a.- Steam Generator Blowdown Tank Effluent Line (1)
- 16
- b. Secondary Coolant and Condensate Leakage (1)
- 16
- c. Turbine Building Sump (1)
- 16
- 3. Flow Rate Measurement Devices
- a. Liquid Radweste Effluent Line+ (1)
- 17
- b. Circulating Water System Discharge + (1)
- 17
- c. Steam Generator Blowdown Tank Effluent (1) 17
+ Pump curves may be utilized to estimate flow, in such cases, ACTION Statement ,
is not required.
*During releases via this pathway.
Yankee Rowe 3/4 3-33 Amendment No.(fp 92 1
.- _ =.
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NAfr COOLANT SYST E k l SAFETY VALVES - SHUTDOWN , LIMITING CONDITION FOR OPERATION 3.4.2 At least the following safety and/or relief valves shall be OPERABLE;
- a. A minimaa of one pressurizer code safety valve shall be .
OPERABLE with a lift setting of 2485 psig +3%, -3% or 2560 psig !
+3%, -3%.
- b. The Main Coolant System (MCS) pressurizer Power-operated Relief j Valve (PORV) PR-30V-90 shall be OPERABLE in the low pressure !
I mode whenever MCS temperature is 1 324'F. l
- c. Shutdown Cooling System (SCS) Safety Valves SV-204 and SV-205 i shall be OPERABLE whenever MCS temperature is 1 3000F.
APPLICABILITY: MODES 4 and 5. . I l l ACTION: l
~
. a. With no pressurizer code safety valve OPERABLE, inunediately suspend -
all operations involving positive reactivity changes and place the Shutdown Cooling System into operation.
~5 b. With PR-80V-90 inoperable and MCS temperature between 300*F and )
0 ',/ 3240F:
- 1. Within 8 hours, either;
- a. Raise the MCS temperature to > 3240F, or l l
.,b. Lower the MCS temperature to 1 3000F and place the SCS l safety valves into operation by: l
- 1. Opening SC-MOV-551, 552, 553, and 554; and
- 2. Verifying that the safety valves are lined up to
- discharge to either the Low Pressure Surge Tank (LPST) or the Primary Drain Collecting Tank (PDCT);
and
- 2. Restore PR-30V-90 to OPERABLE status within 7 days; or
- 3. Within the next 8 hours, depressurize and vent the MCS to the )
atmosphere, the LPST, or the PDCT.
. YANEEE-ROWE 3/4 4-5 Amendment No. If, 66, M, 92 1
- l MAIN COOLANT SYSTEM LIMITING CONDITION FOR OPERATION ACTION (Continued) '
- c. With one SCS safety valve or PR-SOV-90 inoperable and.MCS temperature f 300 F, res' tore the inoperable valve to OPERABLE status within 7 days or depressurite and vent the MCS to the" atmosphere, the LPST o'r the PDCT'.within the next 8 hours. l
- d. With more than one pressurizer PORV and/or SCS safety valve inoperable and MCS temperature is f 300'F, depressurize and vent the MCS to the atmosphere, the LPST or the PDCT within 8 hours.
SURVEILLANCE REQUIREMENTS 4.4.2.1 The pressurizer code safety valve shall be demonstrated OPERABLE
- j per Surveillance Requirement 4.4.3.
4.4.2.2 The MCS pressurizer PORV PR-SOV-90 low setpoint system shall be demonstrated OPERABLE at least once per:
- s. 12 hours by verifying the low setpoint syrtem keylock switch to
- be in the armed position.
- b. 31 days by verifying valve PR-MOV-512 to be open.
- c. 18 renths by performance of a CHANNEL CALIBRATION and verifying that the PORV opens at 500 j; 30 psig and closes at 470 j; 30 psig. .
- \
9 4.4.2.3 The SCS safety valves shall be demonstrated OPERABLE: a.. At least once per 31 days by verifying that:
! 1. Valves SC-MOV-551, 552, 553 and 554 are locked open.
- 2. Safety valves SV-204 and 205 are lined up to discharge to either i
the LPST or the PDCT.
- b. Per ASME Section XI, Summer 1975 Addenda with a setpoint of 425 -
Psig j; 3%. : 4 3/4 4-Sa Amendment No. ff, M, 92 YANKEE-ROWE v .-- ,, ,.r. , . . , - - - . . . - - - , , . . . - . _ - - - - - - - - , - , .- , - - , . .
I
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EMERGENCY CORE COOLING SYSTEMS ECCS SUBSYSTEMS LIMITING CONDITION FOR OPERATION i 3.5.2 The ECCS subsystems shall be OPERABLE with:
- a. Three OPERABLE independent ECCS safety injection subsystems with each subsystem comprised of:
- 1. One OPERABLE high pressure safety injection pump,
- 2. One OPERABLE low pressure safety injection pump, .
- 3. An OPERABLE flow path capable of taking suction from the safety injection tank on a safety injection signal. .
- b. An OPERABLE ECCS recirculation subsystem with an OPERABLE flow l path capable of taking suction from the containment sump and 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 subsystem and discharging to the Main Coolant System #4 hot leg.
APPLICABILITY: MODES 1, 2, 3, 4* and 5* l ACTION! i a. With one ECCS safety injection subsystem inoperable, restore the inoperable subsystem to OPERABLE status within 72 hours or ' be in at least HOT SHUTOOWN with Main Coolant pressure < 1000 psig within the next 12 hours. 1
- b. In the event the ECCS is actuated and injects water into the Main Coolant System, a Special Report shall be prepared and submitted to the Commission pursuant to Specification 6.9.6 within 90 days describing the circumstances of the actuation and the total accumulated actuation cycles to date. The pro-visions of Specification 3.0.3 are not applicable.
- Main coolant pressure > 1000 psig.
\ -
YANKEE-ROWE 3/4 5-3 Amendment No. af, 92 i um s o w. m r. - w. ,m m e. ., . -
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EMERGENCY CORE COOLIhG SYSTEMS SURVEILLANCE REQUIREMENTS l 4.5.2 Each ECCS safety injection subsystem, the recirculation subsystem, and the long-term hot leg injection subsystem shall be demonstrated OPERABLE:
- a. At least once per.31 days on a STAGGERED TEST H ASIS .by:
Verifying that each high pressure safety injection pump: 1. a) Starts (unless already operating) from the control room. b) Develops a discharge pressure of > 850 psig on recirculation flow to the safety injection tank. c) Operates for at least 15 minutes.
- 2. Verifying that each low pressure safety injection pump:
a) Starts (unless already operating) from the control room. b) Develops a discharge pressure of > 250 psig on recirculation flow through CS-MOV-532, c) _ Operates for at least 15 minutes. _
- b. XIt' least once per 31 days by:
- 1. Verifying that the following valves are in the indicated positions with power to the valve operators removed by opening at least two breakers in series: -
Valve Number Valve Function Valve Position
'a. CH-MOV-522 a. Charging Header /LPSI a. Closed Isolation
- b. CH-MOV-524 b. Charging Header / Loop b. Open l
4 Hot Leg Injection Long-Term Recirculation . l YANKEE-ROWE 3/4 5-4 Amendment No. [f, A&, 92
EMERGENCY CORE COOLING SYSTEMS SURVEILLANCE REQUIREMENTS 4.5.3.l* The ECCS subsystems shall be demonstrated OPERABLE per the ap- l plicable Surypillance Requirements of 4.5.2. 4.5.3.2 The above specified HPSI and LPSI pumps shall be verified to be inoperable at least once per 12 hours whenever MCS temperature is . 3,324*F by determining that the associated power supply breakers are open and locked in the racked-out position or are removed from the cubicle. ,' 4.5.3.3 The following valves shall be verified to be in the indicated positions at least once per 12 hours whenever MCS temperature is 3,324*F. the reactor vessel head is bolted on and both pressurizer - code safety valves are installed as specified above.
. Valve Number Valve Position
' CS-MOV-536 Closed CS-MOV-537 Closed CS-MOV-538 Closed CS-MOV-539 Closed SI-MOV-22 Closed SI-MOV-23 Closed SI-MOV-24 Closed SI-MOV-25 Closed CS-MOV-532 Open
- Main coolant pressure < 1000 psig but > 300 psig. ,
I YANKEE-ROWE 3/4 5-11 Amendment No./HL 92 1
-r w-,, - -
EMERGENCY CORE COOLING SYSTEMS e
. V SAFETY INJECTION TANK .
i;. LIMITING CONDITION FOR OPERATION ' 3.5.4 The -aafety injection t' nka (SIT) shall be OPERABLE with:
. a. A minimum conta'ined borated water volume of 117;000 gallons, equivalent to a level of 125.5 feet. ,
- b. A minimum boron concentration of 2200 ppm, a'nd-
- c. A' water tempe,rature of 1200 F to 130 F.
APPLICABILITY: MODES 1, 2, 3, 4* and 5* ACTION:--- . With the safety injection tank inoperable, restore the tank to OPERABLE status within 1 hour or b'e in at least HOT STANDBY within 6 hours and in HOT SHUTDOWN with main coolant pressure < 300 psig within the following l 12 hours. SURVEILLANCE REQUIREMENTS 4.5.4 The SIT shall be demonstrated OPERABLE:
- s. sat 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 hours by verifying the SIT temperature. l u .
~
- Main coolant pressure >300 psig.
YANKEE-ROWE 3/4 5-12 AmendmentNo.//,97,92
'. a ,
PLANT SYSTEMS r HICH PRESSURE C09 SYSTEM LIMITING CONDITIONS FOR OPERATION 3.7.10.3 The high pressure CO2 system located in Manhole No. 3 shall be OPERABLE with at least 90% of full charge weight in the main and auxiliary CO2 cylinders. APPLICABILITY: Whenever equipment in the high pressure CO2 protected area is required to be OPERABLE. Exception: Automatic initiation of the high pressure CO2 system may be disabled to allow maintenance activities within Manhole No. 3 providing a continuous fire watch is established and the high pressure CO2 system remains capable of being
- manually initiated.
ACTION:
- a. With the above required high pressure CO2 system inoperable, establish a continuous fire watch with backup fire suppression equipment for the unprotected area within 1 hour; restore the system to OPERABLE status within 14 days or, in lieu of any other report required by Spe.2fication 6.9, prepare and submit a Special Report to the Commission pursuant to Specification 6.9.6 within the next 30 days outlining the action taken, the cause of the inoperability and the plans and schedule for restoring the system to OPERABLE status,
- b. The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.
SURVEILLANCE REOUIREMENTS 4.7.10.3 The above required high pressure CO2 systems shall'be demonstrated OPERABLE:
- a. At least once per 6 months by verifying CO2 cylinder weight.
- b. At least once per 18 months by:
- 1. Verifying the system valves actuate automatically.
- 2. Performance of a flow test through headers and nozzles to assure no blockage.
m YANKEE R0WE 3/4 7-35 Amendment No. Ag, A7, 56, g4,92
ELECTRICAL POWER SYSTEMS , A.C. DISTRIBUTION - SHUTDOWN LIMITING CONDITION FOR OPERATION ___ 3.8.2.2 As a minimum, the following ac electrical busses shall be OPERABLE and energized from sources of power other than a diesel generator but aligned to an OPERABLE diesel generator,
- s. 1 - 2400 volt Bus #2 or #3
- b. 2 - 480 volt Busses #4-1, #5-2, or #6-3
- c. 1 - 480 volt Emergency Bus #1, #2, or #3
- d. 2 - 480 volt Busses, Emergency MCC #1 and Emergency MCC #2
- e. 1 - 480 volt Bus, Emergency MCC #3 or Emergency MCC #4
- f. 1 - 480 volt Bus, Emergency MCC #5 or Emergency MCC #6
- g. 2 - 120 volt Vital Busses #1 and #2 APPLICABILITY: MODES 5 and 6 ACTION:
With less than the above complement of ac busses OPERABLE and energized, establish integrity in accordance with Section 3.9.4 within 8 hours. SURVEILLANCE REOUIREMENTS 4.8.2.2 The specified ac busses shall be determined OPERABLE and energized I from ac sources other than the diesel generators at least once per 7 days by verifying correct breaker alignment and indicated power availability. l D 1
+
YANKEE ROWE 3/4 8-8 Amendment No.j{}' 92
ELECTRICAL POWER SYSTEMS , D.C. DISTRIBUTION - SHUTDOWN LIMITING CONDITION FOR OPERATION 3.8.2.4 As a minimum, the following D.C. electrical equipment shall be energized and OPERABLE: 2 - 125-volt D.C. distribution switchboards, and 2 - 125-volt battery banks and chargers associated with the above D.C. distribution switchboards. APPLICABILITY: Modes 5 and 6. ACTION: With less thsn the above complement of D.C. equipment OPERABLE, establish integrity in accordance with Section 3.9.4 within 8 hours. SURVEILLANCE REQUIREMENTS 4.8.2.4.1 The above required 125-volt D.C. distribution switchboards shall be determined OPERABLE and energized at least once per 7 days by verifying correct breaker alignment and indicated power availability. 4.8.2.4.2 The above required 125-volt battery banks and chargers shall be demonstrated OPERABLE per Surveillance Requirements 4.8.2.3.2.
, YANKEE ROWE 3/4 8-11 Amendment No. 92
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; SHIFT IN RT NOT AS A FUNCTION OF VESSEL FLUENCE FOR WELD METAL,1/4t AND 3/4t ,
m BASES FIGURE B3/4 4-2' i 1 i ~
3/4.5 EMERGENCY CORE COOLING SYSTEMS BASES 3/4.5.1 ACCUMULATOR l The OPERABIL'ITY of the accumulator ensures that a sufficient volume of borated water will be innediately forced into the reactor core through each of the cold legs in the event the Main Coolant System pressure falls below the pressure of the accumulator. This initial surge of water into the core provides the initial cooling mechanism during large . Main Coolant System pipe ruptures. The limits on accumulator volume, boron concentration and pressure ensure that the assumptions used for accumulator injection in the acci , dent analysis are met. A minimum useable water volume of 700 cubic feet require accumulator water volume to be at least 850 cubic feet. - The limits for operation with the accumulator inoperable for any reason . except an isolation valve closed or pressurization system inoperable minimizes the time exposure of the plant to a LOCA event occurring concurrently. which may result in unacceptable peak cladding tempera-tures. If a closed isolation valve cannot be immediately opened, the full capability of the accumulator is not available and prompt action is required to place the reactor in a MDDE where this capability is not l required. 3/4.5.2 and 3/4.5.3 ECCS SUBSYSTEMS The OPER' ABILITY of three independent ECCS safety injection subsystems, the recirculation subsystem, and the long term hot leg injection sub-system ensures that sufficient emergency core cooling capability will be I available in the event of a LOCA assuming the loss of one safety in-jection subsystem. Two safety injection subsystems operating in con- l Junction with the accumulator are capable of supplying sufficient core cooling to limit the peak cladding temperatures within acceptable limits for all postulated break sizes ranging from the double ended break of the largest Main Coolant System cold leg pipe downward. In addition, the safety injection subsystems, the recirculation subsystem and the long term hot leg injection subsystem provide long term core cooling and boron mixing capability during the accident recovery period. l YANKEE-ROWE B 3/4 5-1 Amendment No. 43, (f, 92 W
- - EMERGENCY CORE _C0dLING SYSTEMS T - EASES ,
4 T, o 3 g ECCS SUBSYSTEMS (Continued) , , With the Main Coolant System temperature and pressure'below 330 F, and 1000 psis, respectively, one OPERABLE ECCS safety injection subsystem, with the - OPERABLE reci,rculation subsystem and the OPERABLE long . term hot leg injection subsystem', is, acceptable without single failure considerati'on on the basis 3 of the stable reactivity condition of the reactor, the decre,ased probability ! j of a LOCA and the limited core cooling requirements because of the negligible energy stored in the primary coolant under these conditions. '- The Surveillance Requirements provided to ensure OPERABILITY of each component ensures that, at a minimum, the assumptions used in the safety analyses are met and that subsystem OPERABILITY is maintained. Complete system tests cannot be performed when the reactor is operating - because of their inter-relation with operating systems. The method of assuring operability of these systems is a combination of complete system - tests performed during refueling shutdowns and monthly tests of active system components (pumps and valves) during reactor operation. The test interval i ^ is based on the judgement that more frequent testing would not significantly increase reliability. Some subsystems power operated valves fail to meet single failure criteria . and removal of power to these valves is required l
- In order to eliminate potential for reactor vessel low temperature overpressurization by the inadvertent operation of ECCS pumps, the pump ,,
circuit breakers are opened and locked in the racked-out position or removed
- f rom the breaker cubicles.
Also selected SIS isolation valves are positioned l to remove the possibility of an overpressurization event during that portion . c of MCS heatup and cooldown when an inadvertent , injection could result in
- an overpressure event. . ,
3/4.5.4 SAFETY INJECTION TANK The OPERABILITY of "the Safety Injection Tank (SIT) as part of the ECCS. T ensures' that a suf ficient supply of borated water is available for injectio.n by the ECCS in the event of a LOCA. The limits on SIT 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 suberitical in the cold condition following mixing of the SIT and the Main Coolant System water volumes with all control rods inserted 'except for the most reactive control assembly. These assumptions are consistent with the LOCA analyses, which is based on allowing a minimum
- i. of 77,000 gallons to be injected by.the safety injection subsystems.before ,
the recirculation is manually established. LOCA analyses show that an ,y injection of 77,000 gallons is sufficient to limit core temperatures and l containment pressure for the full spectrum of pipe ruptures. This leaves up to 40,000 gallons in the SIT as reserve. The boron concentration of The SIT 2200 ppa is the highest value assumed in any accident analysis. ! j water temperature of 120*F - 130 F ensures that the reactor vessel is not subjected to conditions that could exceed the NUT provisions of the ASME Code after a severe transient. i YANKEE-ROWE B 3/4 5-2 Amendment No.' $f, Ah, 92 i e _,,,,# y_.-._ . . - . -, , , , , , , - , , , . - ~ -
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't ADMINISTRATIVE CONTROLS 6.5 REVIEW AND AUDIT 6.5.1 PLANT OPERATION REVIEW COMMITTEE FUNCTION 6.5.1.1 The Plant Operation Review Committee (PORC) shall function to advise the Plant Superintendent on all matters related to nuclear safety.
COMPOSITION
- 6. 5.1. 2 The Plant Operation Review Committee shall be composed of the:
Chairman: Plant Superintendent Vice Chairman: Assistant Plant Superintendent Vice Chairman: Technical Director j Member : Plant Operations Manager Member: Plant Maintenance Manager Member : Reactor Engineering Manager
- Member : Plant Chemistry Manager Member : Instrument and Control Supervisor Member: Radiation Protection Manager Member Maintenance Supervisor Member: Technical Services Supervisor i ALTERNATES
- 6. 5.1. 3 All alternate members shall be appointed in writing by the PORC Chairman to serve on a temporary basis; however, no more than two alternates shall participate as voting members in PORC activities or count toward a PORC quorum at any one time.
l NEETINC FREQUENCY l
- 6. 5.1. 4 The PORC shall meet at least once per calendar month and as convened by the PORC Chairman or Vice Chairman.
QUORQ4 l l 6. 5.1. 5 A quorum of the PORC shall consist of a minimum of six people as ! follows: l
- a. The Chairsan or Vice Chairman plus five members, or
- b. The Chairman and Vice Chairman plus four members, or
- c. The Chairman and two Vice Chairmen plus three members, or I
- d. The two Vice Chairmen plus four members. _
RESPONSIBILITIES
- 6. 5.1. 6 The Plant Operation Review Committee shall be responsible for:
- a. Review of: 1) all procedures required by Specification 6.8 and changes thereto, 2) any other proposed procedures or changes thereto as determined by the Plant Superintendent to affect nuclear safety.
; YANKEE ROWE 6-7 Amendment NO.I // , f, h, W, 92
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