ML20198F462
| ML20198F462 | |
| Person / Time | |
|---|---|
| Site: | Waterford  |
| Issue date: | 12/21/1998 |
| From: | Chandu Patel NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML20198F466 | List: |
| References | |
| NUDOCS 9812280128 | |
| Download: ML20198F462 (8) | |
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UNITED STATES j
NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 206d50001
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ENTERGY OPERATIONS. INC.
I DOCKET NO. 50-382 WATERFORD STEAM ELECTRIC STATION. UNIT 3 l
l AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.147 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 August 12,1998, 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 nmendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.
9812280128 981221 PDR ADOCK 05000382 P
pon
. 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.147, 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
&A?
Chandu P. Patel, Project Manager j
Project Directorate IV-1 Division of Reactor Projects Ill/IV Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of issuance:
December 21, 1998
l
&TTACHMENT TO LICENSE AMENDMENT NO.147 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 1-13 3/4 1-13 3/4 1-14 3/4 1-14 3/4 5-1 3/4 5-1 3/4 5-9 3/4 5-9 B 3/4 5-2 B 3/4 5-2 i
... - - -. - ~. - -
REQUIRED STORED BORIC ACID VOLUME AS A FUNCTION OF CONCENTRATION 15000 14000 REGION OF ACCEPTABLE i
OPERGON p
l '=
8 b
1 RWSP at 2000 ppm tn 6(
(
RWSP a 2300 ppm
- ui (87%)
10000
\\
^
1
\\
g (78%)
m kI 9
Q (69%)
(
9 REGION OF ACCEPTABLE OPERATION (60%)
7000 A
(50%)
e000 J
2.25 2.50 2.75 3.00 3.25 3.50 (3,950)
(4,375)
(4,825)
(5,250)
(5,700)
(6,12i" BORIC ACID CONCENTRATION, WT.% (ppm)
FIGURE 3.1 1
- This curve bounds RWSP concentration ranging from 2300 ppm to 2900 ppm WATERFORD - UNIT 3 3/4113 AMENDMENT NO.10, 'i, t 't 147
REACTh TY CONTRObSYSTE'MS O
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 the tanks in accordance with Figure 3.1-1, and
- b. The refueling water storage pool with:
i 1.
A minimum contained borated water volume of 475,500 gallons (83% of indicated level), and j
2.
A boron concentration of between 2050 and 2900 ppm of boron, and I
i 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) ir. operable, 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 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 poolinoperable, 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:
- 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.
- 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 NO. 10,10,120,147
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 with:
a.
The isolation valve open, b.
A contained borated water volume of between 926 (40%) and 1807 (83.8%) cubic
- feet, c.
Between 2050 and 2900 ppm of boron, and d.
A nitrogen cover-pressure of between 600 and 670 psig, l
APPLICABILITY: MODES 1,2,3*, and 4*.
ACTION:
a.
With one safety injection tank inoperable, except as a result of a closed isolation valve, restore the inoperable tank 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 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 />.
l b.
With one safety injection tank inoperable due to the isolation valve being closed, l
either immediately open the isolation valve or be in at least HOT STANDBY within l
1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> and be in HOT SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
i' SURVEILLANCE REQUIREMENTS l-4.5.1 Each safety injection tank shall be demonstrated OPERABLE:
a.
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:
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 2900 ppm boron, and a contained borated water volume of between 888 (39%) and 1807 (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.
L i
f WATERFORD - UNIT 3 3/4 5-1 AMENDMENT NO. 4e+;+99,147 L.
to.
EMERGENCY CORE COOLING SYSTEMS 3/4.5.4 REFUELING WATER STORAGE POOL 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 2900 ppm of boron, and c.
A solution temperature of between 55'F and 100'F.
APPLICABILITY. MODES 1,2,3, and 4.
ACTION
- With the refuelins 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 />.
l SURVEILLANCE REQUIREMENTS 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 sir temperature is less than 55'F or greater than 100'F.
/ATERFORD - UNIT 3 3/4 5-9 AMENDMENT NO. 49;+29,147
1 4
EMERGENCY CORE COOLING SYSTEMS BASES s
i ECCS SUBSYSTEMS (Continued) l With the RCS temperature below 350'F, one OPERABLE ECCS subsystem is acceptable I
without single failure consideration on the basis of the stable reactivity condition of the reactor
{
and the limited core cooling requirements.
The trisodium phosphate dodecahydrate (TSP) stored in dissolving baskets located in the containment basement is provided to minimize the possibility of corrosion cracking of certain metal components during operation of the ECCS following a LOCA. The TSP provides this protection by dissolving in the sump water and causing its final pH to be raised to greater than or equal to 7.0. The requirement to dissolve a representative sample of TSP in a sample of water borated to be representative of post LOCA sump conditions provides assurance that the stored l
TSP will dissolve in borated water at the postulated post-LOCA temperatures. A boron J
concentration of 3011 ppm boron is postulated to be representative of the highest post-LOCA j
sump boron concentration. Post LOCA sump pH will remain between 7.0 and 8.1 for the l
maximum (3011 ppm) and minimum (1504 ppm) boron concentrations calculated using the maximum and minimum post-LOCA sump volumes and conservatively assumed maximum and minimum source boron concentrations.
With the exception of systems in operation, the ECCS pumps are normally in a standby, nonoperating mode. As such, flow path piping has the potential to develop voids and pockets of 4
entrained gases. Maintaining the piping from the ECCS pumps to the RCS full of water ensures that the system will perform propeny, injecting its full capacity into the RCS upon demand. This 4
i will prevent water hammer, pump cavitation, and pumping noncondensible gas (e.g., air, j
nitrogen, or hydrogen)into the reactor vessel following an SIAS or during SDC. The 31 day j
frequency takes into consideration the gradual nature of gas accumulation in the ECCS piping j
and the adequacy of the procedural controls goveming system operation.
l The Surveillance Requirements provided to ensure OPERABILITY of each component ensure that at a minimum, the assumptions used in the safety analyses are met and that subsystem OPERABILITY is maintained. Surveillance Requirements for throttle valve position stops and flow balance testing provide assurance that proper ECCS flows will be maintained in the event of a LOCA. Maintenance of proper flow resistance and pressure drop in the piping 1
system to each injection point is necessary to: (1) prevent total pump flow from exceeding runout conditions When the system is in its minimum resistance configuration, (2) provide the l
proper flow split between injection points in accordance with the assumptions used in the ECCS-LOCA analyses, and (3) provide an acceptable level of total ECCS flow to all injection points 4
equal to or above that assumed in the ECCS-LOCA analyses.
The requirement to verify the minimum pump discharge pressure on recirculation flow ensures that the pump performance curve has not degraded below that used to show that the pump exceeds the design flow condition assumed in the safety analysis and is consistent with the requirements of ASME Section XI.
WATERFORD - UNIT 3 B 3/4 5-2 AMENDMENT NO. 127,100,147
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