ML20217Q461
| ML20217Q461 | |
| Person / Time | |
|---|---|
| Site: | Waterford  |
| Issue date: | 04/08/1998 |
| From: | Chandu Patel NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML20217Q465 | List: |
| References | |
| NUDOCS 9804100443 | |
| Download: ML20217Q461 (17) | |
Text
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UNITED STATES j
j NUCLEAR REGULATORY COMMISSION 2
WASHINGTON, D.C. 20666-0001
,o ENTERGY OPERATIONS. INC.
DOCKET NO. 50-382 WATERFORD STEAM ELECTRIC STATION. UNIT 3 AMENDMENT TO FACluTY OPERATING LIC"%g Amendment No.141 Ucense 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 May 24,1997, as supplemented by letter dated January 21,1998, complies with the standards and requirements of the Atomic Energy Act of1954, 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.
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9804100443 980408 PDR ADOCK 03000382 P
PDR g
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i j
-2.
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:
(2)
Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No. 141, and the Environmental Protection Plan contained in Appendix B, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
3.
This license amendment is effective as of its date of issuarice to be implemented within 60 days.
FOR THE NUCLEAR REGULATORY COMMISSION hhh Chandu P. Patel, Project Manager Project Directorate IV-1 Division of Reactor Projects lil/IV Office of Nuclear Reactor. Regulation
Attachment:
Changes to the Technical Specifications Date of issuance: April 8, 1998 i
4 ATTACHMENT TO LICENSE AMENDMENT NO.141 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 1-1 3/4 1-1 3/4 1-3 3/4 1-3 3/4 1-13 3/4 1-13 3/4 10-1 3/4 10-1 B 3/4 1-1 B 3/4 1-1 B 3/41-1a B 3/4 1-2 8 3/4 1-2
3/4.1 REACTMTY CONTROL SYSTEMS 3/4.1.1 BORATION CONTROL
'N i
LIMITING CONDITION FOR OPERATION l
3.1.1.1 The SHUTDOWN MARGIN shall be greater than or equal to that specified in the COLR.
APPLICABILITY: MODES 1,2*, 3,4, and 5 with any full length CEA fully or partially withdrawn.
ACTION With the SHUTDOWN MARGIN less than that specified in the COLR, immediately initiate I
boration to restore SHUTDOWN MARGIN to within limit.
I i
SURVEILLANCE REQUIREMENTS 4.1.1.1.1 Wdh any full length CEA fully or partially withdrawn, the SHUTDOWN MARGIN shall be determined to be greater than or equal to that specified in the COLR:
- a. Within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> after detection of an inoperable CEA(s) and at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> thereafter while the C5A(s) is inoperable. If the inoperable CEA is immovable or untrippable, the above required SHUTDOWN MARGIN shall be verified acceptable with an increased allowance for the withdrawn worth of the immovable or untrippable CEA(s).
- b. When in MODE 1 or MODE 2 with Koff grester than or equal to 1.0, at least once per 12 houts by verifying that CEA group withdrawal is within the Transient insertion Limits of Specification 3.i.3 6
- c. When in MODE 2 with Keff less than 1.0, within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> 'pior to achieving reactor i
cribcality by verifying that the predicted critical CEA position is within the limits of Specification 3.1.3.6.
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- See Special Test Excephon 3.10.1.
WATERFORD - UNIT 3 3/4 1-1 AMENDMENT NO. 11,00,102,141
1 REACTIVITY CONTtDL SYSTEMS
$URVEILLANCE REQUIREMENTS (Continued) d.
Prior to initial operation above EK RATED THERMAL POWER after each fuel loading, by consideration of the factors of e. below, with the CEA grow s at tha. Transient Insertion Limits of specification 3.1.3.6.
e.
When in MDDE 3, 4 or 5, 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 consideration j
of at least the following factors:
1.
Reactor Coolant System boron concentration, 2.
CEA position, 3.
Reactor Coolant Sys,tes average tesperature, 4.
Fuel burnup based on gross thermal energy generation, 5.
Xenon concentration, and 6.
Samarium concentration.
j 4.1.1.1.2 The overall core reactivity balance shall be compared to predicted values to demonstrate agreement within + 1.0% delta k/k at least once per 31 I
Iffective Full Power Days (EFPD). This comparison shall consider at least those factors stated in Specification 4.1.1.1.le., above. The predicted reactivity values shall be adjusted (normalized) to correspond to the actual core conditions prior to exceeding a fuel burnup of 60 EFPDs after each fuel loading.
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e WATERFORD - UNIT 3 3/4 1-2 AMENDMENT ND. 11 4
REACTIVITY CONTROL SYSTEMS SHUTDOWN MARGIN - ALL FULL LENGTH CEAS FULLY INSERTED LIMITING CONDITION FOR CPERATION 3.1.1.2 The SHUTDOWN MARGIN shall be greater than or equal to that specified in the COLR.
APPLICABILITY: MODES 3,4 and 5 with all full length CEAs fully inserted.
ACTION With the SHUTDOWN MARGIN less than that specified in the COLR, immediately initiate I
boration to restore SHUTDOWN MARGIN to within limit.
I SURVEILLANCE REQUIREMENTS 4.1.1.2 With all full length CEAs fully inserted, the SHUTDOWN MARGIN shall be determined to be greater than or ecyal to that specified in the COLR, 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 consideration of the following factors:
- 1. Reactor Coolant System boron concentration,
- 2. CEA position,
- 3. Reactor Coolant System average temperature,
- 4. Fuel bumup based on gross thermal energy generation,
- 5. Xenon concentration,and
- 6. Samarium concentration.
WATERFORD - UNIT 3 3/4 1-3 AMENDMENT NO. 11,00,102,141
REACTIVITY CONTROL SYSTEMS MODEftATOR TEMPERATURE COEFFICIENT LIMITING CONDITION FOR OPERATION 3.1.1.3 The moderator temperature coefficient (MTC) shall be within the limits specified in the COLR. The maximum upper design limit shall be:
Less positive than 0.5 x 10 delta k/k/*F whenever THERMAL POWER is a.
$70% RATED THERMAL POWER, and b.
Less positive than 0.0 x 10 delta k/k/*F whenever THERMAL POWER is
>70% RATED THERMAL POWER.
APPLICABILITY: MODES I and 2*#
l ACTION:
With the moderator temperature coefficient outside any one of the above limits, 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 />.
I SURVEILLANCE REOUIREMENTS 4.1.1.3.1 The MTC shall be determined to be within its limits by confirmatory measurements. MTC measured values shall be extrapolated and/or compensated to permit direct comparison with the above limits.
4.1.1.3.2 The MTC shall be determined at the following frequencies and THERMAL POWER conditions during each fuel cycle:
a.
Prior to initial operation above 5% of RATED THERMAL POWER, after each fuel loading.
b.
At greater than 15% of RATED THERMAL POWER, prior to reaching 40 EFPD core burnup.
AtanyTHERMALPOWER,'gthin7EFPDofruchingtwo-thirdsof c.
expected core burnup.
l greater than or equal to 1.0.
- With K,,,ial Test Exception 3.10.2.
geSpec This Surveillance test need not be performed for Cycle 7 l
WATERF092 UNIT 3 3/4 1-4 AMENDMENT NO. 5,16,1^2,105 APR 211995
}
REQUIRED STORED BORIC ACID VOLUME AS A FUNCTION OF CONCENTRATION 15000 f
14000 REGION OF ACCEPTABLE OPERATION
{
2 5
i 13000 e
2 s
d>
i 1
RWSP at 2000 ppm j
to I
z RWSP at 2300 ppm (s61)
/
i 11000 l
0 J
Eo (87%)
(
10000 z<
(78%)
4 1
9 y
(*69%)
(
o jE REGION OF UNACCEPTABLE OPER ATION g
(60%)
(
7000 (50%)
co00 2.25 2.50 2.75 3 00 3.25 3 50 13.950)
(4.375)
(4.8251 (5.2501 (5.7001 16 1251 BORIC ACIO CONCENTRATION, WT.% (ppm)
FIGURE 3.1-1 WATERFORD - UNIT 3 3/4 1-13 AMENOMENT NO. l',45141
REACTIVITY CONTROL SYSTEMS BORATED WATER SOURCES - OPERATING LIMITING CONDITION FOR OPERATION 3.1.2.8 Each of the following borated water sources shall be OPERABLE:
a.
At least one of thE following sources:
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 i
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 (83% of indicated Invel), and
{
2.
Aboronconcentrationofbetween2050and2300ppeofboron,andl 3.
A solution temperature between 55"F and 100*F.
APPLICABILITY: MODES 1, 2, 3, and 4.
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 I
equivalent to the requirements of Specification 3.1.1.1 or 3.1.1.2, whichever is applicable; restore the at..: required boric acid makeup tank (s) to OPERABLE 4tatus 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 I hour or be in at least H0T 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:
{
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.
J 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.
WATERFORD - UNIT 3 3/4 1-14 AMENDMENT N0. 4Gd9,129
3/4.10 SPECIAL TEST EXCEPTIONS 3/4.10.1 SHUTDOWN MARGIN LIMITING CONDITION FOR OPERATION 3.10.1 The SHUTDOWN MARGIN requirement of Speedication 3.1.1.1 or 3.1.1.2 may be suspended for measurement of CEA worth and SHUTDOWN MARGIN provided reactivity equivalent to at least the highest estimated CEA worth is available for trip insertion from OPERABLE CEA(s).
APPLICABILITY: MODES 2 AND 3*.
ACTION
- a. With any full-length CEA not fully inserted and with less than the above reactivity equivalent available for trip insertion, immediately initiate boration to restore the SHUTDOWN MARGIN required by Specification 3.1.1.1.
- b. With all full-length CEAs fully inserted and the reactor subcritical by less than the above reactivity equivalent, immediately initiate boration to restore the SHUTDOWN MARGIN required by Specification 3.1.1.2.
SURVEILLANCE REQUIREMENTS 4.10.1.1 The position of each full-length and part-length CEA required either partially or fully withdrawn shall be determined at least once per 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />.
4.10.1.2 Each CEA not fully inserted shall be demonstrated capable of full insertion when tripped from at least the 50% withdrawn position within 7 days prior to reducing the SHUTDOWN MARGIN to less than the limits of Speedication 3.1.1.1.
- Operation in MODE 3 shall be limited to 6 consecutive hours.
WATERFORD-UNIT 3 3/4101 AMENDMENT NO. 44,141
1
~
$PECIAL TEST EXCEPTIONS I
3/4.10. M MODERATOR "EMPERATURE COEFFICfhiT. GROUP HEIGHT. INSERTION. AND POWER DMSTRIBUTION LLMITS 1
LIMITING CONDITION FOR OPERATION 3.10.2 The moderator temperature coefficient, group height, insertion, and i
power distribution limits of Specifications 3.1.1.3, 3.1.3.1, 3.1.3.5, 3.1.3.6, 3.1.3.7, 3.2.2, 3.2.3, 3.2.7, and the Minimum Channels OPERABLE requirement of Functional Unit 15 of Table 3.3-1 may be suspended during the perfomance of PHYSICS TESTS provided:
a.
The THERMAL POWER is restricted to the test power plateau which shall not exceed 85% of RATED THERMAL POWER, and b.
The limits of Specification 3.2.1 are maintained and determined as specified in Specification 4.10.2.2 below.
APPLICABILITY: MODES I and 2.
ACTION:
With any of the limits of Specification 3.2.1 being exceeded while the requirements of Specifications 3.1.1.3, 3.1.3.1, 3.1.3.5, 3.1.3.6, 3.1.3.7, 3.2.2, 3.2.3, 3.2.7, and the Minimum Channels OPERABLE requirement of Functional Unit 15 of Table 3.3-1 are suspended, either:
y a.
Reduce THERMAL POWER sufficiently to satisfy the requirements of Specification 3.2.1, or b.
Be in HOT STANDBY within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
SURVEILLANCE REQUIREMENTS 4.10.2.1 The THERMAL POWER shall be determined at least once per hour during PHYSICS TESTS in which the requirements of Specifications 3.1.1.3, 3.1.3.1, 3.1.3.5, 3.1.3.6, 3.1.3.7, 3.2.2, 3.2.3, 3.2.7, or the Minimum Channels OPERA 6LE requirement of Functional Unit 15 of Table 3.3-1 are suspended and shall be verified to be within the test power plateau.
4.10.2.2 The linear heat rate shall be determined to be within the limits of Specification 3.2.1 by monitoring it continuously with the Incore Detection l
Monitoring System pursuant to the requirements of Specifications 4.2.1.2 I
during PHYSICS TESTS above 55 of RATED THERMAL POWER in which the requirements of Specifications 3.1.1.3, 3.1.3.1, 3.1.3.5, 3.1.3.6, 3.1.3.7 3.2.2, 3.2.3, 3.2.7, or the Minimum Channels OPERABLE requirement of Functional Unit 15 of Table 3.3-1 are suspended.
WATERFORD - UNIT 3 3/4 10-2 Amendment No. H,136
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 SHUTDOWN MARGIN 5 the amount by which the core is subcritical, or would be subentical immediately following a reactor trip, considering a single malfunction resulting in the highest worth CEA failing to insart.
The function of SHUTDOWN MARGIN is to ensure that the reactor remains subcritical following a design basis accdont or anticipated operational occurrence. During operation in MODES 1 and 2, with k, greater than or equal to 1.0, the transient insertion limits of Specification 3.1.3.6 ensure that sufficient SHUTDOWN MARGIN is available.
SHUTDOWN MARGIN requirements vary throughout the core life as a function of fuel depletion and reactor coolant system (RCS) cold leg temperature (T.). The most restrictive '
condition occurs at EOL, with (T.) at no-load operating temperature, and is associated with a postulated steam line break accident and the resulting uncontrolled RCS cooldown. In the analysis of this accident, the specified SHUTDOWN MARGIN is required to control the reactivity transient and ensure that the fuel performance and offsite dose criteria are satisfied. As (initial)
T decreases, the potential RCS cooldown and the resulting reactivity transient are less severe and, therefore, the required SHUTDOWN MARGIN also decreases. Below T of about 200'F, the inadvertent deboration event becomes 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 deboratien and the total loss of SHUTDOWN MARGIN. Accordingly, the SHUTDOWN MARGIN requirements are based upon 1
these limiting conditions.
Additional events considered in establishing requirements on SHUTDOWN MARGIN are single CEA withdrawal and startup of an inactive reactor coolant pump.-
If the SHUTDOWN MARGIN requirements are not met, boration must be initiated immediately. Boration will continue until the SHUTDOWN MARGIN requirements are met.
In the determination of the required combination of borati<m flow rate and boron concentratum, there is no unique requirement that must be satisfied provided the boration source is sufficient to achieve the SHUTDOWN MARGIN. Smce it is imperative to raise the boron concentratson of the RCS as soon as possible, the boron concentration should be a highly concentrated solution, such as that normally found in the boric acid makeup tanks or the refueling water storage pool. The Operator should borate w:th the best source available for the plant cordstions.
Other technical specifications that reference the Spe:ifications on SHUTDOWN 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.
WATERFORD-UNIT 3 B 3/4 1-1 AMENDMENT NO. M,141
3/4.1 REACTIVITY CONTROL SYSTEMS BASES l
3/4.1.1.3 MODERATOR TEMPERATURE COEFFICIENT l
The hmitations on moderator temperature coefficient (MTC) are provided to ensure that the assumptions used in the accident and transient analysis remain valid inrough each fuel cycle. The Surveillance Requirements for measurement of the MTC during each fuel cycle are adequate to confirm the MTC value since this coe4cient changes slowly due principally to the reduction in RCS boron concentration associated with fuel bumup. The confirmation that the measured MTC value is within its limit provides assurances that the coefficient will be maintained within acceptable values throughout each fuel cycle.
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WATERFORD - UNIT 3 B 3/4 1-ia AMENDMENT NO.141
REACTIVITY CONTROL SYSTEMS RASES 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 nomal 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 peak linear feat rate of Specification 3.2.1.
)
- 4.1.2 B0 RATION 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 j
tracing systems, and (6) an emergency power supply from OPERABLE diesel generators.
j With the RCS average temperature above 200*F, a minimum of two separate j
and redundant boron injection systems are provided to ensure singic 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 i
safety from injection system failures during the repair period.
The boration capability of either system is sufficient to provide a SHUT-D0WN MARGIN from expected operating conditions of 2.0% delta k/k after menon decay and cooldown to 200*F. The maximum expected boration capability requirement occurs at E0L from full power equilibrium xenon conditions 1
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 1g,000 gallons of 2050 ppm borated water from the refueling water storage pool or approximately 58,000 gallons of 2050 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 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 menon decay and cooldown from 200*F to 140*F.
This condition requires either 5,465 gallons of 2050 ppe borated water from l
the refueling water storage pool or boric acid solutica from the boric acid makeup tanks in accordance with the requirements of Specification 3.1.2.7.
WATERFORD - UNIT 3 5 3/4 1-2 AMENDMENT NO. 44,129