ML20147E086
| ML20147E086 | |
| Person / Time | |
|---|---|
| Site: | Waterford  |
| Issue date: | 02/13/1997 |
| From: | Chandu Patel NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML20147E092 | List: |
| References | |
| NUDOCS 9702180190 | |
| Download: ML20147E086 (9) | |
Text
f*"hq At UNITED STATES l
p-g
,g NUCLEAR REGULATORY COMMISSION l
't WASHINGTON, D.C. 30e6M1001 s...../
ENTERGY OPERATIONS. INC.
DOCKET NO. 50-382 WATERFORD STEAM ELECTRIC STATION. UNIT 3 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.123 License No. NPF-38 i
1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment by Entergy Operations, Inc. (the licensee) dated July 25, 1996, as supplemented by letter dated January 27, 1997, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Comission's rules and regulations set forth in 10 CFR Chapter I; B.
The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Comission; C.
There is reasonable assurance (1) that the activities authorized by this amendment can be conducted without endangering the health and safeb of the public, and (ii) that such activities will be conducted in compliance with the Comission'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; and E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Comission's regulations and all applicable requirements have been satisfied.
9702180190 970213 DR ADOCK 050 32
- 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 Soecifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No.123, 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 issuance to be implemented within 60 days.
FOR THE NUCLEAR REGULATORY COMMISSION hhh andu 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:
February 13, 1997 t
- --~
ATTACMENT TO LICENSE AMENDMENT NO.123 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 7-12 3/4 7-12 3/4 7-13 3/4 7-13 3/4 7-14 3/4 7-14 8 3/4 7-4 8 3/4 7-4 ra 1
4 l
l
i PLANT SYSTEMS E4.7.3 COMPONENT COOLING WATER AND AUXILIARY COMPONENT COOLING WATER SYSTEMS 1_!r.1] TING CONDITION FOR OPERATION 4
M
{
3.7.3 At least two independent component cooling water and associated auxiliary 4
component cooling water trains shall be OPERABLE.
APPLICABILITY: MODES 1, 2, 3, and 4.
I ACTION:
With only one component cooling water and associated auxiliary component cooling water train OPERA 0LE, restore at least two trains to OPERAELE status I
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 NOT STAND 8Y 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 />.
1 SU.RVEILLANCE REQUIREMENTS i
4 4.7.3 Each component cooling water and associated auxiliary component cooling j
water train shall be demonstrated OPERABLE:
1 At least onc'e per 31 days by verifying that each valve (manual, a.
i power-operated, or automatic) servicing safety-related equipment i
that is not locked, sealed, or otherwise secured in position, is in t
its correct position.
5 b.
At least once per 18 months, during shutdown, by verifying that each automatic valve servicing safety-related equipment actuates to its 4
correct position on SIAS and CSAS test signals.
At least once per 18 months by verifying that each component cooling c.
1 water and associated auxiliary component cooling water pump starts automatically on an SIAS test signal.
4 l
WATERFORD - UNIT 3 3/4 7-11 i
PLANT SYSTEMS 3/4.7.4 ULTIMATE HEAT SINK LIMITING CONDITION FOR OPERATION 3.7.4 Two independent trains of ultimate heat sink (UHS) cooling towers shall l
be OPERABLE with each train consisting of a dry cooling tower (DCT) and a wet mechanical draft cooling tower (WCT) and its associated water basin with:
a.
A minimum water level in each wet tower basin of 97% (-9.86 ft MSL) b.
An average basin water temperature of less than or equal to 89'F.
l c.
Fans as required by Table 3.7-3.
APPLICABILITY: MODES 1, 2, 3, and 4.
ACTION:
a.
With 1 UHS train inoperable, restore the inoperable train 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 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 />.
b.
With both UHS trains inoperable, restore at least one UDS train to OPERABLE status within I heur or be in at least HOT STAl!DBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and 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 />.
1 WATERFORD - UNIT 3 3/4 7-12 Amendment No. H.123
PLANT SYSTIES LIMITING CONDITION FOR OPERATION (Continued)
ACTION:
(Continued) c.
With a Tornado Watch in effect, all 9 DC1 fans under the missile protected portion of the DCT shall be OPERABLE.
If the number of fans OPERABLE is less than required, restore the inoperable fan (s) to OPERABLE status within I hour, or be in at least HOT STANDBY within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in HOT SHUTDOWN within the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
d.
With any UHS fan inoperable, determine the outside ambient temperature at least once every 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> and verify that the minimum fan requirements of Table 3.7-3 are satisfied.
jgg'!EILLANCE REQUIREMENTS 4.T.4.
Each train of UHS shall be determined OPERABLE:
l 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 average water temperature and water level to be within specified limits.
l b.
At least once per 31 days, by verifying that each wet tower and dry tower fan that is not already running, starts and operates for at least 15 minutes.
J l
t i
i WATERFORD - UNIT 3 3/4 7-13 Amendment No. 95,123 i
i
TABLE 3.7-3 ULTIMATE HEAT SINK MINIMUM FAN REQUIREMENTS PER TRAIN DRY COOLING TOWER AMBIENT CONDITION DPJ BULB 2 98'F
< 98'F DRY BULB 2 91*F
< 91*F DRY BULB 2 77'F DRY BULB < 77'F Fan 15 14*
12*
9*
Requirements")
WET COOLING TOWER AMBIENT CONDITION WET BULB 2 75*F
< 75*F WET BULB 2 70*F WET BULB < 70*F Fan 8
7**
4**
9*
Requirements"3 (1) With any of the above reouired UHS fan inoperable comply with ACTION d.
With a tornado watch in effect. all 9 DCT fans under the alssile orotected nortion of the DCT shall be CPERABLE.
With any WCT fants) out-of-service in any cell. covers must be in place on the out-of-service fanfs) or the entire cell (i.e. 4 fans) must be declared out-of-service.
If four fans are out of service in the same cell. the covers do not have to be installed.
WATERFORD - UNIT 3 3/4 7-14 AMENOMENT NO.95.123
.- n
E g7 $YSTEMS i
SA5ES i
3/4.7.1.4 ACTIVITY The limitations en secondary systes specific activity ensure that the resultant offsite radiatten dose will be Itaited to a small fraction of 10 CFR Part 100 limits in the event of a steam Ifne rupture.
i This dose also includes I
the effects of a coincident 1 pe primary to secondary tube leak in th,e steam generator of the affected staan 11ae and a concurrent less-of-effsite elettrical these values are consistent with the assumptfens ased in the safety
- power, i
analyses.
3/4.7.1.5 ISIN STEAM LINE ISOLATION VALVE The OPERASILITY of the sein steam Ifne feelation valves ensures that no more than one steam ponerator will blow down in the event of a steam line rupture. This restr'ction is required te (1) ainfafze the positive reactivit effects of the Reactor Coolant Syrtem cooldown associated with the blowdown, y and (2) limit the pressure rise within containment in the event the steam line rupture occurs within containment.
The OPERABILITY of the sein steam isolation welves within the closure times of the $vrveillance Requirements are consistent with the assumptions used in the safety analyses. '
3/4. 7. 2 57EAM GENiAATOR PRESSURE / TEMPERATURE LIMITATION The limitation on steam generator secondary pressure and temperature ensures that the pressure induced stresses in the steam generators do not exceed the maximum allowable fracture toughness stress limits. The limitation to 115'F and 210 psig is based en a staas generator RTNDT of 40*F and is sufficient to prevent t rittle fracture. Selow thfs temperature of 115'r the i
system pressure must be Ifsited to a maximum of 20K of the secondary hydro-static test pressure of 1375 psia (corrected for instrument error).
Should steam generator temperature drop below 115'F en engineering evaluation of the effects of the overpressurization is required.
However, to reduce the poten-tfa1 for brittle failure the staan generator temperature may be increased to a limit of 200*F while performing the evaluation.
i j
side of the steam generator are bounded by the restrictions en the reactorThe coolant system in specification 3.4.8.1.
3/4.7.3 COMPONENT COOLING WATER AND aurrtgany m ENT E LING WATft $YSTEMS
,um9[ary component cooling water systes ensures that suffi capacity is available for continued operation of safety-M1sted e i
i "t
during normal eno ;ccident conditions. The redundant cooling i
f j
nele failure. is consistent with the l
ss fons es tn he af a
ye WATERFORD - UNIT 3 0 3/4 7'-3 Amendment No. 6 l
l l
PLANT SYSTEMS ggs 3/4.7.4 ULTIMATE HEAT SINK The limitations on the ultimate heat sink level, temperature, and number l
of fans ensure that sufficient cooling capacity is available to either (1) provide normal cooldown of the facility, or (2) to mitigate the effects of accident conditions within acceptable limits.
l The UHS consists of two dry cooling towers (DCTs), two wet cooling towers (WCTs), and water stored in WCT basins.
Esch of two 100 percent capacity loops 4
employs a dry and wet cooling tower.
i Each DCT consists of five separate cells. Cooling air for each cell is j
provided by 3 fans, for a total of 15 per DCT. The cooling coils on three i
cells of each DCT (i.e. 605) are protected from tornado missiles by grating i
located above the coils and capable of withstanding tornado missile impact.
With a Tornado Watch in effect and the number of fans OPERABLE within the j
missile protected area of a DCT less than that required by Table 3.7-3, ACTION e requires the restoration of inoperable fans within I hour or plant shutdown as specified. This ACTION is based on FSAR analysis (subsection 9.2.5.3.3) that assumes the worst case single failure as,1 emergency diesel generator coincident with a loss of offsite power. This failure occurs j
subsequent to a tornado strike and 60% cooling capacity of a DCT is assumed i
available.
i Each WCT has a basin which is capable of storing sufficient water to i
bring the plant to safe shutdown under all accident conditions.
Item a of i
LCO 3/4.7.4 requires a minimum water level in each WCT basin of 97% (-9.86 ft i
MSL). The bases for this elevation is WCT water evaporation and drift loss calculations, which concluded that during a LOCA 168,738 gallons would be l
consumed from one WCT basin. When the WCT basin water level is maintained at -
l 9.86 ft MSL, each basin has a minimum capacity of 174,000 gallons.
Each WCT l
consists of two cells, each cell is serviced by 4 induced draft fans, for a j
total of 8 per MCT. There is a concrete partition between the cells that prevents air recirculation between the fans of each cell.
Covers are required on fans declared out-of-service to prevent air recirculation between fans within a cell.
Table 3.7-3 specifies increased or decreased fan OPERABILITY requirements based on outside air temperature and humidity. The table provides the cooling tower fan OPERABILITY requirements that may vary with outside ambient I
conditions. Fan OPERABILITY requirements are specified for each controlling 4
parameter (i.e., dry bulb temperatures for DCT fans and wet bulb temperatures for WCT fans). The calculated temperature values (EC-M95-009) associated with DCT and WCT fan requirements have been rounded in the conservative direction and lowered one full degree to account for minor inaccuracies.
Failure to meet the OPERABILITY requirements of Table 3.7-3 requires entry into the applicable action. Because temperature and humidity are subject to change during the day, ACTION d requires periodic temperature readings to verify compliance with Table 3.7-3 when any cooling tower fan is inoperable.
The limitations on minimum water level and maximum temperature are based on providing a 30-day cooling water supply to safety-related equipment without exceeding their design basis temperature and is consistent with the recommend-ations of Regulatory Guide 1.27, " Ultimate Heat Sink for Nuclear Plants,"
March 1974.
WATERFORD - UNIT 3 8 3/4 7-4 AMENDMENT NO.95,123 A