ML20095F076
| ML20095F076 | |
| Person / Time | |
|---|---|
| Site: | Waterford  |
| Issue date: | 04/17/1992 |
| From: | Larkins J Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20095F081 | List: |
| References | |
| NUDOCS 9204280107 | |
| Download: ML20095F076 (9) | |
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[!i1[RGY OPERATIONS. ING DOCKET NQ. 50-382 WATER _f0RD STEAM ELECTRIC STATION. UNIT 1 MMM[fl.T 10 FACILITY OPER_ATING _LICENS1 Amendment No. 72 License No. NPF-3B 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Entergy Operations, Inc. (the licensee) dated May 8, 1991, 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; D.
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 trasonable 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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Acts.*dingly, 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. 72, and the Environmental Protection Plaa contained in Appendix B, are hereby incnrporated 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.
FOR THE NUCLEAR REGULATORY COMMIS$10N 7
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))l} hKww1G ^m John T. Larkins, Director Project Directorate IV-1 Division of Reactor Projects Ill/lV/V Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of 1ssuance:
April 17, 1992
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4 ATTACHMENT TO LICENSE AMEN 0 MENT NO. 72 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 i
contain vertical lines indicating the areas of change.
The corresponding j
overleaf pages are also provided to maintain document completeness.
REMOVE PA011 INSERT PACES 3/4 4-34 3/4 4-34 3/4 4-35 3/4 4-35 B 3/4 4-10 B 3/4 4-10 t
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_ PRESSURIZER HEATUP/C00LDOWN LIMITING CONDITION FOR OPERATION 3.4.8.2 The pressurizer shall be limited to:
A maximum heatup rate of 200'F per hour, i
a.
b.
A maximum cooldown rate of 200'F per hour, and i
A maximum spray nozzl3 usage factor of 0.65.'
c.
i APPLICABILITY:
At all times.
ACTION:
With the p-essurizer temperature limits in excess of any of the a.
above limits, restore the temperature to within the limits within 30 minutes; perform an engineering evaluation to determine the effects of the out-of-limit condition on the structural integrity of the pressurizer; determine.that the pressurizer remains acceptable for continued operation or be in at least HOT STANDBY within the nes.t 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and reduce the pressurizer pressure to less than 500 psig 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 the spray nozzle usage factor > 0.65, comply with requirements of Table 5.7-1.
SURVEILLANCE REQUIREMENTS 4.4.8.2.1 The pressurizer temperatures shall be determined to be within the limits at least once per 30 minutes during system heatup or cooldcan, 4.4.8.2.2 The spray water temperature diff erential shall be determined to be within the limit at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> during auxiliary spray operation.
4.4.8.2.3 Each spray cycle and the corresponding AT (water temperature differential) shall be recorded whenever main spray is initiated with a AT (water temperature differential) of > 130*F and whenever auxiliary spray is initiated with a ST (water temperature differential) of > 140'F.
o W/.TERFORD - UNIT 3 3/4 4-33
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REACTOR C_00LANT SYSTEM OVERPRESSURE PROTECTION SYSTEMS LIMITING CONDITION FOR OPERATION 3.4.8.3 Two Shutdown Cooling (SDC) System suction line relief valves (SI-4D6A and SI 4069) shall be OPERABLE with a lif s :;etttng of less than or equal to 430 psia, APPLICABILITY: H0DE 4 when the temperature of any RCS cold leg is less than or equal to 285'F, MODE 5, and MODE 6 when the head is on the reactor vessel and the RCS is not vented through a 5.6 square inch or larger vent.
ACTION:
With one SDC System suction line relief valve inoperable in H0DE 4, a.
restore the inoperable valve in OPERABLE status within 7 days, or depressurize and vent the RCS through at least a S.6 square inch vent within the next 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.
b.
With one 500 System suction line relief valve inoperable in H0 DES 5, or 6, either (1) restore the itoperable valve to OPERABLE status within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, or (2) complete depressurization and venting of the RCS through at least a 5.6 square inch vent within a total of 32
- hours, With both SDC System suction line relief valves inoperable, complete c.
depressurization and venting of the RCS through at least a 5.6 square inch vent within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.
d.
In the event either the SDC System suction line relief valve (s) or the RCS vent (s) are used to mitigate an RCS pressure transient, a Special Report shall be prepared and submitted to the Commission pursuant to Specification 6.9.2 within 30 days.
The report shall describe the circumstances initiating the transient, the offect of the SDC System suction line relief valve (s) or RCS vent (s) on the transient, and any corrective action necessary to prevent recurrence, e.
The provisions of Specification 3.0.4 are not applicable.
[260FduringinserviceleakandhydrostatictestingwithReactorCoolantSystem temperature changes restricted in accordance with Specification 3.4.8.19 WATERFORD - UNIT 3 3/4 4-34 AMENDMENT NO. 5, 72
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l REACTOR COOLANT SYSTEM SURVEILLANCE REQUIREVENTS 4.4.8.3.1 Each SDC System suction line relief valve shall be demonstrated OPERABLE:
a.
by verifying in the control room at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> th6t each valve in the suction path between the RCS and the J C relief valve is open.
b.
At least every 30 moriths when tested pursuant to Specification 4.0.5.
4.4.8.3.2 With the RCS vented per ACTIONS a, b, or c, the RCS vent (s) and all valves in the vent path shall be verified to be open at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
Except when the vent pathway is provided with a valve which is locked, sealed, or otherwise secured in the open position, then verify these valves open at least once per 31 days.
WATERFORD - UNIT 3 3/4 4-35 AMENDMENT NO. EE, 72
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i REACTOR COOLANT SYSTEM 3/4.4.9 STRUCTURAL INTEGRITY LIMITING CONDITION FOR OPERATION 3.4.9 The structural integrity of ASME Code Class 1, 2, and 3 components shall be maintained in accordance with Specification 4.4.9.
APPLIC ABI L 1,TY:
All MODES.
ACTION:
a.
With the structural integrity of any ASME Code Class I component (s) not conforming to the above requirements, restore the structural integrity of the affected component (s) to within its limit or isolate the affected component (s) prior to increasing the Reactor Coolant System temperature more than 70'F above the minimum temperature required by NDT considerations.
b.
With the structural integrity of any ASME Code Class 2 component (s) not conforming to the above requirements, restore the structural integrity of the affected component (s) to within its limit or isolate the affected component (s) prior to increasing-the Reactor Coolant System temperature above 200'F, except during hydrostatic testing of components tnat are nonisolable from the Reactor Coolant System, then restore the structural integrity prior to increasing the Reactor Coolant System temperature more than 30'F above the minimum temperature required by NDT considerations.
c.
With the structural integrity of any ASME Code Class 3 component (s) not conforming to the above requirements, restore the structural integrity of the affected component to within its limit or isolate the affected component from service, d.
The provisions of Specification 3.0.4 are not applicable.
SURVE!LLANCE REQUIREMENTS 4.4.9 In addition to the requirements of Specification 4.0.5, each reactor coolant pump flywheel shall be inspected per the recommendations of Regulatory Position C.4.b of Regulatory Guide 1.14, Revision 1, August 1975.
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REACTOR COOLANT SYSTEM BASES PRESSURE /TEMPERMURE LIMITS (Continued)
The maximum RT for all Reactor Coolant System pressure-retaining NDT materials, with the exception of the reactor pressure vessel, has been determined to be 90'f.
The lowest Service Temperature limit line shown on Figures 3.4-2 and 3.4-3 is based upon this RT since Article NB-2332 of HDT Section III of the ASME Boiler and Pressure Vessel Code requires the Lowest Service Temperature to be RTNDT + 100*F for piping, pumps, and valves. Below this temperature, the system pressure must be limited to a maximum of 20% of the system's hydrostatic test pressure of 3125 psia (as corrected for elevation and instrument error).
The limitations imposed on the pressurizer heatup and cooldown rates and spray water temperature differential are provided to assure that the pres-surizer is operated within the design criteria assumed for the fatigue analysis performed in accordance with the ASME Code requirements.
The OPERABILITY of the shutdown cooling system relief valve or an RCS vent opening of greater than 5.6 square inches ensures that the RCS will be protected from pressure transients which could exceed the limits of Appendix G to 10 CFR Part 50 when one or more of the RCS cold legs are less than or equal to 285 F.
Each shutdown cooling system relief valve has adequate relieving capability to protect the RCS from overpresserization when the transient is either (1) the start of an idle RCP with the secondary water temperature of the steam generator less _than or equal to 100 f above the RCS cold leg tempera-tures or (2) inadvertent safety injection actuation with injection into a water-solid RCS.
The limiting transient includes simultaneous, inadvertent operation of three HPSI pumps, three charging pumps, and all pressurizer backup heaters in operation.
Since SIAS starts only two HPSI pumps, a 20%
margin is realized.
The restrictions on starting a reactor coolant pump in MODE 4 and with the reactor coolant loops filled in MODE 5, with one or more RCS cold legs less than or equal to 285'F, are provided in Specification 3.4.1.3 and 3.4.1.4 to prevent RCS pressure transients caused by energy additions from the secondary system which could exceed the limits of Appendix G to 10 CFR Part 50.
The RCS will be protected against overpressure transients and will not exceed the limits of Appendix G by restricting starting of the RCPs to when the secondary water temperature of each steam generator is less than 100*f above each of the RCS cold leg temperatures.
Maintaining the steam generator less than 100'F above each of the Reactor Coolant System cold leg temperatures (even with the RCS filled solid) or maintaining a large surge volume in the pressurizer ensures that this transient is less severe than the limiting transient consi-dered above.
The automatic isolation setpoint of the shutdown cooling isolation valves is sufficiently high to preclude inadvertent isolation of the shutdown cooling relief valves during a pressure transient.
WATERFORD - UNIT 3 8 3,e 4-10 Amendment No. 72