ML20212G478
| ML20212G478 | |
| Person / Time | |
|---|---|
| Site: | Waterford  |
| Issue date: | 01/08/1987 |
| From: | Joshua Wilson Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20212G482 | List: |
| References | |
| NUDOCS 8701200521 | |
| Download: ML20212G478 (15) | |
Text
.
p Klo 8
ng'o, UNITED STATES
[
p, NUCLEAR REGULATORY COMMISSION g
j WASHINGTON, D. C. 20555 e
LOUISIANA POWER AND LIGHT COMPANY l
DOCKET NO. 50-382 WATERFORD STEAM ELECTRIC STATION, UNIT 3 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 10 License No. NPF-30 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment, dated August 20, 1986, as supplemented by two letters dated October 6, 1986, by Louisiana Power and Light Company (licensee), complies with standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Comission's 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 regulations of the Commission; C.
There is reasonable assurance (1) 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 comon defense and security or to the health and safety of the public; 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.
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. NPF-38 is hereby amended to read as follows:
8701200521 870108 PDR ADOCK 05000382 P
2 j
(2) Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No. 10, and the Environmental Protection Plan contained in Appendix B, are hereby incorporated in this license.
LP&L shall operate tite facility in accordance with the Technic 61 Specifications and the Environmental Protection Plan.
3.
The license amendment is effective as of the date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION J
s H. Wilson, Project Manager PWR Project Directorate No. 7 Division of PWR Licensing-B
Attachment:
Changes to the Technical Specifications Date of Issuance: January 8,1987 I
January 8, 1987 ATTACHMENT TO LICENSE AMENDMENT NO. 10 TO FACILITY OPERATING LICENSE NO. NPF-38 DOCKET NO. 50-382 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 area of change. Also to be replaced are the following overleaf pages to the amended pages.
Amendment Pages Overleaf Pages XIX XX 3/4 1-6 3/4 1-5 3/4 1-7 3/4 1-8 3/4 1-12 3/4 1-11 3/4 1-13 3/4 1-14 B 3/4 1-2 8 3/4 1-1 1
I
INDEX LIST OF FIGURES FIGURE PAGE 3.1-1 REQUIRED STORED BORIC ACID VOLUME AS A FUNCTION OF CONCENTRATION..........................
3/4 1-13 3.1-2 CEA INSERTION LIMITS VS THERMAL POWER..............
3/4 1-27 3.2-1 ALLOWABLE PEAK LINEAR HEAT RATE VS BURNUP..........
3/4 2-2 3.2-2 DNBR MARGIN OPERATING LIMIT BASED ON COLSS.........
3/4 2-8 3.2-3 DNBR MARGIN OPERATING LIMIT BASED ON CORE PROTECTION CALCULATORS (COLSS OUT OF SERVICE)......
3/4 2-9 3.4-1 DOSE EQUIVALENT I-131 PRIMARY COOLANT SPECIFIC ACTIVITY LIMIT VERSUS PERCENT OF RATED THERMAL POWER WITH THE PRIMARY COOLANT SPECIFIC ACTIVITY >1.0 pCi/ GRAM DOSE EQUIVALENT I-131.......
3/4 4-27 3.4-2 REACTOR COOLANT SYSTEM PRESSURE / TEMPERATURE LIMITATIONS FOR 0-8 EFFECTIVE FULL POWER YEARS (HEATUP)...........................................
3/4 4-30 3.4-3 REACTOR COOLANT SYSTEM PRESSURE / TEMPERATURE LIMITATIONS FOR 0-8 EFFECTIVE FULL POWER YEARS (C00LDOWN).........................................
3/4 4-31 3.6-1 CONTAINMENT PRESSURE VS TEMPERATURE...............
3/4 6-12 f
4.7-1 SAMPLING PLAN FOR SNUBBER FUNCTIONAL TEST..........
3/4 7-26 5.1-1 EXCLUSION AREA.....................................
5-2 5.1-2 LOW POPULATION Z0NE................................
5-3 5.1-3 SITE BOUNDARY FOR RADIOACTIVE GASEOUS AND LIQUID EFFLUENTS...................................
5-4 6.2-1 0FFSITE ORGANIZATION FOR MANAGEMENT AND TECHNICAL SUPP0RT.................................
6-3 6.2-2 PLANT OPERATIONS ORGANIZATION......................
6-4 i
l 5
i
-WATERFORD - UNIT 3 XIX AMENDMENT NO. 10 1
.._.. _ - - - -..,. _ _ - _ _ -... _ - - - - - - - _ _. _ _ _. _ - -., - - _ - - ~ _ _ _ -.
_ -...., _ ~ _
INDEX LIST OF TABLES TABLE
_PAGE 1.1 FREQUENCY N0TATIONl.....................................
1-9 1.2 OPERATIONAL M00ES.......................................
1-10 2.2-1 REACTOR PROTECTIVE INSTRUMENTATION TRIP SETPOINT LIMITS..................................................
2-3 2.2-2 CORE PROTECTION CALCULATOR ADDRESSABLE CONSTANTS........
2-S MONITORING FREQUENCIES FOR BORON DILUTION DETECTION 3.1-1 K, f f > 0. 9 8............................................. 3/4 1-17 3.1-2 0.98 > K,ff > 0.97......................................
3/4 1-17a 3.1-3 0. 9 7 1 K, f f > U. 9 6......................................
3/4 1-17b 3.1-4 0.96 1 K,ff > 0.95........m
..........m...........m 3/4 1-17c 3.1-5 K,ff 5 0.95.............................................
3/4 1-17d 3.3-1 REACTOR PROTECTIVE INSTRUMENTATION......................
3/4 3-3 3.3-2 REACTOR PROTECTIVE INSTRUMENTATION RESPONSE TIMES.......
3/4 3-8 4.3-1 REACTOR PROTECTIVE INSTRUMENTATION SURVEILLANCE REQUIREMENTS............................................
3/4 3-10 3.3-3 ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION.........................................
3/4 3-14 3.3-4 ENGINEEREDSAFETYFEATURES$CTUATIONSYSTEM INSTRUMENTATION TRIP VALUES.............................
3/4 3-19 3.3-5 ENGINEERED SAFETY FEATURES RESPONSE TIMES...............
3/4 3-22 4.3-2 ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION SURVEILLANCE REQUIREMENTS...............
3/4 3-25 3.3-6 RADIATION MONITORING INSTRUMENTATION....................
3/4 3-29 4.3-3 RADIATION MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS...............................
3/4 3-32 3.3-7 SEISMIC MONITORING INSTRUMENTATION......................
3/4 3-36 4.3-4 SEISMIC MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS...............................
3/4 3-37 3.3-8 METEOROLOGICAL MONITORING INSTRUMENTATION...............
3/4 3-39 WATERFORD - UNIT 3 XX AMENDMENT NO. 9
REACTIVITY CONTROL SYSTEMS
\\
MINIMUM TEMPERATURE FOR CRITICALITY LIMITING CONDITION FOR OPERATION 3.1.1.4 The Reactor Coolant System lowest operating loop temperature (Tcold) shall be greater than or equal to 520*F.
APPLICABILITY:
MODES 1 and 2#.
ACTION:
With a Reactor Coolant System operating loop temperature (Ttowithinitslimitwithin15 minu less than 520*F, restore T I
STANDBYwithintESNext15 minutes.
SURVEILLANCE REQUIREMENTS 4.1.1.4 The Reactor Coolant System cold leg temperature (Tcold) shall be determined to be greater than or equal to 520*F:
(
a.
Within 15 minutes prior to achieving reactor criticality, and b.
At least once per 30 minutes when the reactor is critical and the Reactor Coolant System T is less than 530*F.
cold
- With K,g greater than or equal to 1.0.
WATERFORD - UNIT 3 3/4 1-5
REACTIVITY CONTROL SYSTEMS 3/4.1.2 B0 RATION SYSTEMS FLOW PATHS - SHUTDOWN LIMITING CONDITION FOR OPERATION 3.1.2.1 As a minimum, one of the following boron injection flow paths shall be l
OPERABLE and capable of being powered from an OPERABLE emergency power source:
a.
A flow path from the boric acid makeup tank via either a boric acid makeup pump or a gravity feed connection and any charging pump to the Reactor Coolant System if the boric acid makeup tank in Specifica-tion 3.1.2.7a. is OPERABLE, or b.
The flow path from the refueling water storage pool via either a charging pump or a high pressure safety injection pump to the Reactor Coolant System if the refueling water storage pool in Specification 3.1.2.7b. is OPERABLE.
APPLICABILITY: MODES 5 and 6.
ACTION:
With none of the above flow paths OPERABLE or capable of being powered from an OPERABLE emergency power source, suspend all operations involving CORE ALTERATIONS or positive reactivity changes.
SURVEILLANCE REQUIREMENTS 4.1.2.1 At least one of the above required flow paths shall be demonstrated OPERABLE:
At least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> when the Reactor Auxiliary Building air a.
temperature is less than 55*F by verifying the Boric Acid Makeup Tank solution is greater than 55*F (when the flow path from the boric acid makeup tank is used).
i b.
At least once per 31 days by verifying that each valve (manual, power-operated, or automatic) in the flow path that is not locked, sealed, or otherwise secured in position, is in its correct position.
i WATERFORD - UNIT 3 3/4 1-6 AMENDMENT N0.10
REACTIVITY CONTROL SYSTEMS FLOW PATHS - OPERATING LIMITING CONDITION FOR OPERATION 3.1.2.2 At least two boron injection flow paths to the RCS via the charging pumps shall be OPERABLE. The following flow paths may be used:
a.
With the contents of either boric acid makeup tank in accordance with Figure 3.1-1, the following flow paths shall be OPERABLE:
1.
One flow path from an acceptable boric acid makeup tank via its boric acid makeup pump; and 2.
One flow path from an acceptable boric acid makeup tank via its gravity feed valve; or b.
With the combined contents of both boric acid makeup tanks in accor-dance with Figure 3.1-1, both of the following flow paths shall be OPERABLE:
1.
One flow path consisting of both boric acid makeup pumps, and 2.
One flow path consisting of both gravity feed valves.
APPLICABILITY: MODES 1, 2, 3, and 4.
ACTION:
With only one of the above required boron injection flow paths to the Reactor Coolant System OPERABLE, restore at least two boron injection flow paths to the Reactor Coolant System to OPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or be in at least HOT STANDBY and borated to a SHUTDOWN MARGIN equivalent to the requirements of l
Specification 3.1.1.1 or 3.1.1.2, whichever is applicable, within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />; restore at least two flow paths to OPERABLE status within the next 7 days or be in COLD SHUTDOWN within the next 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
SURVEILLANCE REQUIREMENTS 4.1.2.2 At least two of the above required flow paths shall be demonstrated OPERABLE:
a.
At least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> when the Reactor Auxiliary Building temperature is below 55'F by verifying that the temperature of the boric acid makeup tank (s) is above 55*F.
b.
At least once per 31 days by verifying that each valve (manual, power-operated, or automatic) in the flow path that is not locked, sealed, or otherwise secured in position, is in its correct position, c.
At least once per 18 months during shutdown by verifying that each automatic valve in the flow path actuates to its correct position on an SIAS test signal.
d.
At least once per 18 months by verifying that the flow path required by Specification 3.1.2.2a.1 and 3.1.2.2a.2 delivers at least 40 gpm I
to the Reactor Coolant System.
WATERFORD - UNIT 3 3/4 1-7 AMENDMENT NO.10
p REACTIVITY CONTROL SYSTEMS
~
(
CHARGING PUMPS - SHUTDOWN LIMITING CONDITION FOR OPERATION 3.1.2.3 At least one charging pump or 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 power source.
APPLICABILITY: MODES 5 and 6.
ACTION:
With no charging pump or high pressure safety injection pump OPERABLE or capable of being powered from an OPERABLE emergency power source, suspend all operations involving CORE ALTERATIONS or positive reactivity changes.
SURVEILLANCE REQUIREMENTS 4.1.2.3 No additional Surveillance Requirements other than those required by Specification 4.0.5.
l l
l l
l l
WATERFORD - UNIT 3 3/4 1-8
i i
REACTIVITY CONTROL SYSTEMS BORIC ACID MAKEUP PUMPS - OPERATING LIMITING CONDITION FOR OPERATION 3.1.2.6 At least the boric acid makeup pump (s) in the boron injection flow path (s) required OPERABLE pursuant to Specification 3.1.2.2a. shall be OPERABLE and capable of being powered from an OPERABLE emergency bus if the flow path through the boric acid pump (s) in Specification 3.1.2.2a. is OPERABLE.
APPLICABILITY:
MODES 1, 2, 3, and 4.
ACTION:
With one boric acid makeup pump required for the boron injection flow path (s) pursuant to Specification 3.1.2.2a. inoperable, restore the boric acid makeup pump to OPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or be in at least liOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and borated to a SHUTDOWN MARGIN equivalent to at least 2%
delta k/k at 200*F; restore the above required boric acid makeup pump (s) to OPERABLE status within the next 7 days or be in COLD SHUTDOWN within the next 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
SURVEILLA[ ICE REQUIREMENTS 4.1.2.6 Each required boric acid makeup pump shall be demonstrated OPERABLE at least once every 18 months by verifying that each boric acid makeup pump starts in response to an SIAS test signal.
4 e
WATERFORD - UNIT 3 3/4 1-11
REACTIVITY CONTROL SYSTEMS BORATED WATER SOURCES --SNUTDOWN LIMITING CONDITION FOR OPERATION 3.1.2.7 As a minimum, one of the following borated water sources shall be OPERABLE:
a.
One boric acid makeup tank with a boron concentration between 2.25-and 3.50 weight percent and a minimum borated water volume of 4150 gallons (36% indicated level).
b.
The refueling water storage pool (RWSP) with:
1.
A minimum contained borated water volume of 65,465 gallons (12%
indicated level), and 2.
A minimum boron concentration of 1720 ppm.
APPLICABILITY:
MODES 5 and 6.
ACTION:
With no borated water sources OPERABLE, suspend all operations involving CORE ALTERATIONS or positive reactivity changes.
SURVEILLANCE REQUIREMENTS i
4.1.2.7 The above required borated water source shall be demonstrated OPERABLE:
At least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> when the Reactor Auxiliary Building air a.
temperature is less than 55'F by verifying the boric acid makeup tank solution is greater than 55*F (when it is the source of borated water).
b.
At least once per 7 days by:
1.
Verifying the boron concentration of the water, and 2.
Verifying the contained borated water volume of the tank.
WATERFORD - UNIT 3 3/4 1-12 AMENDMENT NO. 10
REQUIRED STORED BORIC ACID VOLUME AS A FUNCTION OF CONCENTRATION 15000 14000 REGION OF ACCEPTABLE OPERATION E
13000 8'
RWSP at 1n0 ppm d
c y
12 M RWSP at 2000 ppm p
2 RWSP at 2300 ppm
(
)
f o
(85%)
10000 2
4 (77%)
p 9
(68%)
(
8000 o
REGION OF UNACCEPTABLE Eo OPERATION (60%)
(
7000 (51%'l 6000 2.25 2.50 2.75 3.00 3.25 3.50 (3.950)
(4.375)
(4.825)
(5.250)
(5.700)
(6.1261 L
BORIC ACIO CONCENTRATION, WT.% (ppm)
FIGURE 3.1-1 WATERFORD - UNIT 3 3/4 1-13 AMENDMENT NO. 10
REACTIVITY CONTROL SYSTEMS BORATED WATER SOURCES - OPERATING LIMITING CONDITION FOR OPERATION 3.1.2.8 Each of the following borated water sources shall be 0?ERABLE:
At least one of the following sources:
a.
1)
One boric acid makeup tank, with the tank contents in accordance with Figure 3.1-1, or 2)
Two boric acid makeup tanks, with the combined contents of the tanks in accordance with Figure 3.1-1, and b.
The refueling water storage pool with:
1.
A minimum contained borated water volume of 475,500 gallons (82% of indicated level), and 2.
A boron concentration of between 1720 and 2300 ppm of boron, and 3.
A solution temperature between 55*F and 100 F.
APPLICABILITY: MODES 1, 2, 3, and 4.
ACTION:
With the above required boric acid makeup tank (s) inoperable, restore a.
the tank (s) to OPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and borated to a SHUTDOWN MARGIN equivalent to the requirements of Specification 3.1.1.1 or 3.1.1.2, whichever is applicable; restore the above required boric acid makeup tank (s) to OPERABLE status within the next 7 days or be in COLD SHUTDOWN within the next 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
b.
With the refueling water storage pool inoperable, restore the pool 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 the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
SURVEILLANCE REQUIREMENTS 4.1.2.8 Each borated water source shall be demonstrated OPERABLE:
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 RWSP temperature when a.
the Reactor Auxiliary Building air temperature is less than 55*F or greater than 100*F.
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 BAMT temperature is above 55*F when the Reactor Auxiliary Building air temperature is less than 55*F.
c.
At least once per 7 days by:
1.
Verifying the boron concentration in the water, and 2.
Verifying the cor.tained borated water volume of the water source.
WATERFORD - UNIT 3 3/4 1-14 AMENDMENT N0. 10
~. _.
3/4.1 REACTIVITY CONTROL SYSTEMS BASES
~
3/4.1.1 BORATION CONTROL 3/4.1.1.1 and 3/4.1.1.2 SHUTDOWN MARGIN l
A sufficient SHUTDOWN MARGIN ensures that (1) the reactor can be made i
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.
SHUTDOWN MARGIN requirements vary throughout core life as a function of fuel depletion, RCS boron concentration, and RCS T,yg.
The most restrictive i
condition occurs at EOL, with T,yg at no load operating temperature, and is associated with a postulated steam line break accident and resulting uncon-trolled RCS cooldown.
In the analysis of this accident, a minimum SHUTDOWN MARGIN of 5.15% delta k/k is required to control the reactivity transient.
Accordingly, the SHUTDOWN MARGIN requirement is based upon this limiting
(
condition and is consistent with FSAR safety analysis assumptions. With T,yg less than or equal to 200*F, the reactivity transients resulting from any postulated accident are minimal and a 2% delta k/k SHUTDOWN MARGIN provides adequate protection.
j 3/4.1.1.3 MODERATOR TEMPERATURE COEFFICIENT The limitations on moderator temperature coefficient (MTC) are provided to ensure that the assumptions used in the accident and transient analysis remain valid through each fuel cycle.
The Surveillance Requirements for measurement of the MTC 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 assurances that the coef-ficient will be maintained within acceptable values throughout each fuel cycle.
l WATERFORD - UNIT 3 B 3/4 1-1
REACTIVITY CONTROL SYSTEMS BASES 3/4.1.1.4 MINIMUM TEMPERATURE FOR CRITICALITY This specification ensures that the reactor will not be made critical with the Reactor Coolant System cold leg temperature less than 520*F.
This limita-tion is required to ensure (1) the moderator temperature coefficient is within its analyzed temperature range, (2) the protective instrumentation is within its normal operating range, (3) the pressurizer is capable of being in an OPERABLE status with a steam bubble, (4) the reactor pressure vessel is above its minimum RT temperature, and (5) the ECCS analysis remains valid for the NDT peak linear heat rate of Specification 3.2.1.
3/4.1.2 BORATION SYSTEMS The boron injection system ensures that negative reactivity control is available during each mode of facility operation.
The components required to
{
perform this function include (1) borated water sources, (2) charging pumps, (3) separate flow paths, (4) boric acid makeup pumps, (5) associated heat trac-ing systems, and (6) an emergency power supply from OPERABLE diesel generators.
With the RCS average temperature above 200*F, a minimum of two separate and redundant boron injection systems are provided to ensure single functional capability in the event an assumed failure renders one of the systems inoper-able. Allowable out-of-service periods ensure that minor component repair or corrective action may be completed without undue risk to overall facility safety from injection system failures during the repair period.
The boration capability of either system is sufficient to provide a SHUT-DOWN MARGIN from expected operating conditions of 2.0% delta k/k after xenon decay and cooldown to 200*F. The maximum expected boration capability require-ment occurs at EOL from full power equilibrium xenon conditions assuming the most reactive CEA stuck out of the core and requires boric acid solution from the boric acid makeup tanks in the allowable concentrations and volumes of Specification 3.1.2.8 plus approximately 19,000 gallons of 1720 ppe borated water from the refueling water storage pool or approximately 58,000 gallons of 1720 ppe borated water from the refueling water storage pool alone. The higher limit of 447,100 gallons is specified to be consistent with Specification 3.5.4 in order to meet the ECCS requirements.
With the RCS temperature below 200*F one injection system is ccceptable without single failure consideration on the basis of the stable reactivity con-dition of the reactor and the additional restrictions prohibiting CORE ALTERA-TIONS and positive reactivity changes in the event the single injection system becomes inoperable.
The boron capability required below 200*F is based upon providing a 2%
delta k/k SHUTDOWN MARGIN after xenon decay and cooldown from 200*F to 140'F.
This condition requires either 5,465 gallons of 1720 ppm borated water from the refueling water storage pool or boric acid solution from the boric acid makeup tanks in accordance with the requirements of Specification 3.1.2.7.
WATERFORD - UNIT 3 B 3/4 1-2 AMENDMENT NO.10
1 REACTIVITY CONTROL SYSTEMS BASES 3/4.1.1.4 MINIM 8)M TEMPERATURE FOR CRITICALITY This specification encures that the reactor will not be made critical with t
the Reactor Coolant System cold leg temperature less than 520*F. This limita-tion is required to ensure (1) the moderator temperature coefficient is within its analyzed temperature range, (2) the protective instrumentation is within its normal operating range, (3) the pressurizer is capable of being in an OPERABLE status with a steam bubble, (4) the reactor pressure vessel is above its minimum RT temperature, and (5) the ECCS analysis remains valid for the NOT peak linear heat rate of Specification 3.2.1.
3/4.1.2 BORATION SYSTEMS The boron injection system ensures that negative reactivity control is available during each mode of facility operation. The components required to perform this function include (1) borated water sources, (2) charging pumps, (3) separate flow paths, (4) boric acid makeup pumps, (5) associated heat trac-ing systems, and (6) an emergency power supply from OPERABLE diesel generators.
With the RCS average temperature above 200*F, a minimum of two separate end redundant boron injection systems are provided to ensure single functional capability in the event an assumed failure renders one of the systems inoper-able. Allowable out-of-service periods ensure that minor component repair or corrective action may be completed without undue risk to overall facility safety from injection system failures during the repair period.
The boration capability of either system is sufficient to provide a SHUT-DOWN MARGIN from expected operating conditions of 2.0% delta k/k after xenon 2
i decay and cooldown to 200*F.
The maximum expected boration capability require-ment occurs at EOL from full power equilibrium xenon conditions assuming the most reactive CEA stuck out of the core and requires boric acid solution from the boric acid makeup tanks in the allowable concentrations and volumes of Specification 3.1.2.8 plus approximately 19,000 gallons of 1720 ppe borated l
water from the refueling water storage pool or approximately 58,000 gallons of 1720 ppe borated water from the refueling water storage pool alone. The higher i
limit of 447,100 gallons is specified to be consistent with Specification 3.5.4 l
in order to meet the ECCS requirements.
With the RCS temperature below 200*F one injection system is acceptable without single failure consideration on the basis of the stable reactivity con-dition of the reactor and the additional restrictions prohibiting CORE ALTERA-TIONS and positive reactivity changes in the event the single injection system becomes inoperable.
The boron capability required below 200'F is based upon providing a 2%
delta k/k SHUTDOWN MARGIN after xenon decay and cooldown from 200*F to 140'F.
This condition requires either 5,465 gallons of 1720 ppm borated water from the refueling water storage pool or buric acid solution from the boric acid makeup j
tanks in accordance with the requirements of Specification 3.1.2.7.
WATERFORD - UNIT 3 8 3/4 1-2 AMENDMENT NO.10 i
i