ML20148D978
| ML20148D978 | |
| Person / Time | |
|---|---|
| Site: | Waterford  |
| Issue date: | 05/29/1997 |
| From: | Chandu Patel NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML20148D983 | List: |
| References | |
| NUDOCS 9706020213 | |
| Download: ML20148D978 (15) | |
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p arcog UNITED STATES 0
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NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20666-0001
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ENTERGY OPERATIONS. INC.
DOCKET NO. 50-382 WATERFORD STEAM ELECTRIC STATION. UNIT 3 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 129 License No. NPF-38 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Entergy Operations, Inc. (the licensee) dated February 5,1997, as supplemented by letter dated March 26, 1997, 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 (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 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.
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9706020213 970529 PDR ADOCK 05000302 P
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2.
Accordingly, the license is amended by changes to the Technical l
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:
(2) Technical Specifications and Environmental Protection Plan l
The Technical Specifications contained in Appendix A, as revised I
through Amendment No.129, and the Environmental Protection Plan contained in Appendix B, are hereby incorporated in the license, i
The licensee shall operate the facility in accordance with the l
Technical Specifications and the Environmental Protection Plan.
3.
This license amendment is effective as of its date of issuance to be I
implemented within 60 days.
FOR THE NUCLEAR REGULATORY COMMISSION h+1M [ O Chandu P. Patel, Project Manager Project Directorate IV-1 Division of Reactor Projects III/IV Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance:
May 29, 1997 i
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ATTACHMENT TO LICENSE AMENDMENT N0. 129 TO FACILITY OPERATING LICENSE NO. NPF-38 DOCKET NO. 50-382 Replace 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 areas of change. The corresponding overleaf pages are also provided to maintain document completeness.
REMOVE PAGES INSERT PAGES 3/4 1-12 3/4 1-12 3/4 1-14 3/4 1-14 3/4 5-1 3/4 5-1 3/4 5-9 3/4 5-9 3/4 9-1 3/4 9-1 B3/4 1-2 B3/4 1-2 l
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REACTIVXTY 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 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 require-I ments of Specification 3.1.1.1 or 3.1.1.2, whichever is applicable, restore the above required boric beid 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 />.
SURVEILLANCE 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.
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WATERFORD - UNIT 3 3/4 1-11 AMENDMENT NO. 11
.&4N 8 198P
i REACTIVITY CONTROL SYSTEMS 4
BORATED WATER SOURCES - SHUTDOWN 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%
indicatedlevel),and 2.
A minimum boron concentration of 2050 ppm.
l APPLICABILITY: MODES 5 and 6.
1 ACTION:
With no borated water sources OPERABLE, suspend all operations involving CORE ALTERATIONS or positive reactivity changes.
SURVEILLANCE REQUIREMENTS 4.1.2.7 The above required borated water source 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 air 1
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.
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1 WATERFORD - UNIT 3 3/4 1-12 AMENDMENT NO. 44,129
l REQUIRED STORED BORIC ACID VOLUME
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AS A FUNCTION OF CONCENTRATION j
3 15000 t
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1 i
u000 i
assioN OF ACCEPTABLE
{
F OPERATION 1
1 1
e j
13000 1
RWSP at 1730 ppm i
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5 uo00 j
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RwsP.i so00,,.
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g (g)
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4, Y
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8000 (69%)
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REstoN OF UNACCEPTABLE g
OPERATION i
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A 20o0 Y
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so00 2.35 2.50 3.75 3.00 3.35 3.50 9.950)-
M.3751 4tA35)
S.3501 S.1001 05.1251 BORIC ACIO CONCENTRATION, WT.E (ppe) i i
FIGURE 3.1-1 i
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WATERFORD - UNil 3 3/4 1-13 AMENDNENT NO. MA5 i
NOV s s88 I
REACTIVITY CONTROL SYSTEMS
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}@ggfD WATER SOURCES - OPERATING
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LIMITING CONDITION FOR OPERATION 3.1.2.8 Each of the following borated water sources shall be OPERABLE:
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 l
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:
E 1.
A minimum contained borated water volume of 475,500 gallons (83% of indicated level), and 2.
Aboronconcentrationofbetween2050and2300ppmofboron,andl 3.
A solution temperature between 55'F and 100*F.
APPLICABILITY: MODES 1, 2,-3, and 4.
i ACTION:
a.
With the above required boric acid makeup tank (s) inoperable, restore 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 te 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 statur within l' hour 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 l
t hours.
SURVEILLANCE RE0VIREMENTS 4.1.2.8 Each borated water source shall be demonstrated OPERABLE:
a.
At least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> by verifying the RWSP temperature when 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.
t c.
At least once per 7 days by:
1.
Verifying the boron concentration in the water, and 2.
Verifying the contained borated water volume of the water source.
I WATERFORD - UNIT 3 3/4 1-14
' AMENDMENT NO. W rie,129 i
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3/4.5 EMERGENCY CORE COOLING SYSTEMS (ECCS) 3/4.5.1 SAFETY INJECTION TANKS LIMITING CONDITION FOR OPERATION 3.5.1 Each Reactor Coolant System safety injection tank shall be OPERABLE
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with:
The isolation valve open, a.
b.
A contained borated water volume of between 926 (40%) and 1807 (83.8%) cubic feet, Between 2050 and 2300 ppm of boro.n, and c.
l d.
A nitrogen cover-pressure of between 600 and 670 psig.
APPLICABILITY: MODES 1, 2, 3*, and 4*.
ACTION:
With one safety injection tank inoperable, except as a result of a a.
closed isolation valve, restore the inoperable tank to OPERABLE status within I hour 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 HOT SHUTDOWN within the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />, b.
With one safety injection tank inoperable due to the isolation valve being closed, either immediately open the isolation valve or be in at least HOT STANDBY within I hour and be in HOT SHUTDOWN within th next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
SURVEILLANCE RE0VIREMENTS 4.5.1 Each safety injection tank shall be demonstrated OPERABLE:
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:
a.
1.
Verifying the contained borated water volume and nitrogen cover-pressure in the tanks, and 2.
Verifying that each safety injection tank isolation valve is =
open.
- With pressurizer pressure greater than or equal to 1750 psia.
When pressurizer pressure is less than 1750 psia, at least three safety injection tanks must be OPERABLE, each with a minimum pressure of 235 psig and a maximum pressure of 670 psig, and a contained borated water volume of between 1332 (61%) and 1807 (83.8%) cubic feet. With all four safety injection tanks OPERABLE, each tank shall have a minimum pressure of 235 psig and a maximum pressure of 670 psig, a boron concentration of between 2050 and 2300 ppm boron, and a contained borated water volume of between 888 (39%) and 1807l (83.8%) cubic feet.
In MODE 4 with pressurizer pressure less than 392 psia (700 psia for remote shutdown from LCP-43), the safety injection tanks may be isolated.
WATERFORD - UNIT 3 3/4 5-1 AMENDMENT NO M4,129
j EMERGENCY CORE COOLING SYSTEMS 3/4.5.4 REFUELING WATER STORAGE POOL
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LIMITING CONDITION FOR OPERATION 3.5.4 The refueling water storage pool shall be OPERABLE with.
a.
A minimum contained borated water volume of 475,500 gallons (83%
indicated level),
b.
Between 2050 and 2300 ppm of boron, and l
c.
A solution temperature of between 55*F and 100*F.
APPLICABILITY: MODES 1, 2, 3, and 4.
ACTION:
i 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 REOUIREMENTS 4.5.4 The RWSP shall be demonstrated OPERABLE:
a.
At least once per 7 days by:
1.
Verifying the contained borated water volume in the pool, 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 RWSP temperature when the RAB air temperature is less than 55*F or greater than 100*F.
i WATERFORD UNIT 3 3/4 5-9 AMENDMENT NO. M, 129 l
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3/4.9 REFUELING OPERATIONS 3/4.9.1 BORON CONCENTRATION LIMITING CONDITION FOR OPERATION 3.9.1 With the reactor vessel head closure bolts less than fully tensioned or with the head removed, the boron concentration of all filled portions of the Reactor Coolant System and the refueling canal shall be maintained uniform and sufficient to ensure that the more restrictive of the reactivity conditions specified in the COLR is met.
APPLICABILITY: MODE 6*.
ACTION:
With the requirements of the above specification not satisfied, immediately suspend all operations involving CORE ALTERATIONS or positive reactivity changes and initiate action to restore boron concentration to within COLR limitis.
SURVEILLANCE RE0VIREMENTS 4.9.1.1 The more restrictive of the above two reactivity conditions shall be determined prior to:
a.
Removing or unbolting the reactor vessel head, and b.
Withdrawal of any full-length CEA in excess of 3 feet from its fully inserted position within the reactor pressure vessel.
4.9.1.2 The boron concentration of the Reactor Coolant System and the refueling canal shall be determined by chemical analysis at least once per 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />.
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- The reactor shall be maintained in MODE 6 whenever fuel is in the reactor vessel with the reactor vessel head closure bolts less than fully tensioned or with the head removed.
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WATERFORD - UNIT 3 3/4 9-1 AMENDMENT NO. 402,129 j
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l REFUELING OPERATIONS
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3/4.9.2 INSTRUMENTATION 1
LIMITING CONDITION FOR OPERATION I
l 3.9.2 As a minimum, two source range neutron flux monitors shall be OPERABLE l
and operating, each with continuous visual indication in the control room and
)
one with audible indication in the containment and control room.
APPLICABILITY: MODE 6.
l ACTION:
a.
With one of the above required monitors inoperable or not operating, immediately suspend all operations involving CORE ALTERATIONS or positive reactivity changes.
b.
With both of the above required monitors inoperable or not operating, determine the boron concentration of the Reactor Coolant System at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
i SURVEILLANCE REQUIREMENTS 4.9.2 Each source range neutron flux monitor shall be demonstrated OPERABLE j
by performance of:
a.
A CHANNEL CHECK at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />, b.
A CHANNEL FUNCTIONAL TEST within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> prior to the initial start of CORE ALTERATIONS, and c.
A CHANNEL FUNCTIONAL TEST at least once per 7 days, 9
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WATERFORD - UNIT 3 3/4 9-2 l
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3/4.1 REACTIVITY CONTROL SYSTEMS
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BASES 3/4.1.1 BORATION CONTROL 3/4.1.1.1 and 3/4.1.1. 2 SHUTDOWN MARGIN SHUTDOWN MARGIN is the amount by which the core is subcritical, or would be suberitical insediately following a reactor trip, considering a single malfunction resulting in the highest worth CEA failing to insert.
The function of SHUTDOWN MARGIN is to ensure that the reactor remains l
suberitical following a design basis accident or anticipated operational During operation in MODES 1 and 2, with k,ff greater than or occurrence.
equal to 1.0, the transient insertion limits of Specification 3.1.3.6 ensure that sufficient SHUTDOWN MARGIN is available.
l SHUTDOWN MARGIN requirements vary throughout the core life as a function of fuel depletion and reactor coolant system (RCS) cold leg temperature (Tcold)*
The most restrictive condition occurs at EOL, with (Teold) at no-load operating temperature, and is associated with a postulated steam line break accident and l
the resulting uncontrolled RCS cooldown.
In the analysis of this accident, the specified SHUTDOWN MARGIN is required to control the reactivity transient and i
ensure that the fuel performance and offsite dose criteria are satisfied. As (initial) T decreases, the potential RCS cooldown and the resulting reactiv-eold ity transient are less severe and, therefore, the required SHUTDOWN MARGIN also decreases.
Below T of about 200'F, the inadvertent deboration event becomes cold i
limiting with respect to the SHUTDOWN MARGIN requirements. Below 200'F. the specified SHUTDOWN MARGIN ensures that sufficient time for operator actions exists between the initial indication of the deboration and the total loss of SHUTDOWN MARGIN. Accordingly, the SHUTDOWN MARGIN requirements are based upon these limiting conditions.
l Additional events considered in establishing requirements on SHUTDOWN MAR-GIN are single CEA withdrawal and startup of an inactive reactor coolant pump.
Other technical specifications that reference the Specifications on SHUT-DOWN MARGIN are: 3/4.1.2, BORATION SYSTEMS, 3/4.1.3, MOVABLE CONTROL ASSEMBLIES, 3/4.9.1, REFUELING OPERATIONS - BORON CONCENTRATION, and 3/4.10.1, SHUTDOWN MARGIN.
3/4.1.1.3 MODERATOR TEMkERATURE COEFFICIENT The limitations on moderator temperature co'efficien't (MTC) are provided to ensure that the assumptions used in the accident and transient analysis l
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.
I WATERFORD - UNIT 3 8 3/4 1-1 AMENDMENT NO. 11 JAN9 1987
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 limitation 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 temperature, and (5) the ECCS analysis remains valid aboveitsminimumRTlIe'atrateofSpecification3.2.1.
for the peak linear 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 tracing 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 requirement 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 2050 ppm borated water from the refueling water storage pool or approximately 58,000 gallons of 2050 ppm 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 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 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 2050 ppm borated water from l
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. 40,129 7
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