ML19341C653
| ML19341C653 | |
| Person / Time | |
|---|---|
| Site: | Fort Calhoun  |
| Issue date: | 02/10/1981 |
| From: | Clark R Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML16341B537 | List: |
| References | |
| NUDOCS 8103030878 | |
| Download: ML19341C653 (10) | |
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. UNITED STATES
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g WASHINGTON, D. C. 20555 j
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OMAHA PUBLIC POWER DISTRICT DOCKET NO. 50-2_85 FORT CALHOUN STATION, UNIT NO. 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 56 License No. DPR-40 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment by the Omaha Public Power District (the licensee) dated November 17, 1980, 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; E.
The f acility will operate in conformity with the appli-cation, the provisions of the Act, and the rules and regulations of the Comission; 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 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.
.81030300 6
2.
Accordingly, Facility Operating License No. DPR-40 is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 3.B. of Facility Operating License No. DPR-40 is hereby amended to read as follows:
B.
Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 56, are hereby incorporated in the license.
The licensee shall operate the facility.in accordance with the Technical Specifications.
3.' This license amendaent is effective as of the date of its issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
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tw av Robert A. Clark, Chief Operating Reactors Branch #3 Division of Licensing i
Attachment:
Changes to the Technical Specifications f
Date of Issuance:
February 10, 1981
ATTACMENT TO LICENSE AMENDMENT NO. 56 FACILITY OPERATING LICENSE NO. DPR-40 DOCKET N0. 50-285 Replace the following pages of the Appendix "A" Technical Specifications with the enclosed pages. The revised pages are identified by Amendment number and contain vertical lines indicating the area of change.
Pages 2-1 2-2 2-2a 2-2b (added) 2-2c (added 2-37 6-1 4
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2.0 LIMITING CONDITIONS FOR OPERATION 2.1 Reactor Coolant System 2.1.1 Operable Components Applicability Applies to the operable status of the reactor coolant system components.
Objective To specify certain conditions of the reactor coolant system components.
Specifications Limiting conditions for operation are as follows:
(1) Reactor Critical All four (k) reactor coolant pumps shall be in operation.
Exceptions The limitations of this specification may be suspended during the performance of physics tests provided the power level is 5 10-1% of rated pcVer and the flow requirements of Table 1.1 No. 2 are met.
(2) kotShutdownor3000F1Teold 1 515 F C
(a) The reactor coolant loops listed below shall be oper-able:
(i)
Reactor coolant locp 1 and st least one associated reactor coolant pump.
(ii)
Reactor coolant loop 2 and at least one associated reactor coolant pump.
(b) At least one of the above reactor coolant loops shall be in operation.
Exceptions All reactor coolant pumps may be de-energized for up to one hour provided (1) no operatiene are permitted that would cause dilution of the reactor coolant system boron concentration, and (2) core outlet temperature is maintained at least 10 F below saturation temperature.
Amen'dment No. %,1//, 56 2-1
2.0 LIMITING CONDITIONS FOR OPERATION 2.1 Reactor Coolant System (Continued) 2.1.1 Operable Compon nts (Continued)
(c) If fewer than th,e above required reactor coolant pumps are operable, the required pumps shall be restored 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 the reactor shall be placed in cold shutdown within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
(3) Cold Shutdown or 2100F1Teold 1 300 F (a) At least two (2) of the decay heat removal loops listed below shall be operable:
(i)
Reactor coolant loop 1 and its associated steam generator and at least one associated reactor coolant pump.
(ii)
Reactor coolant loop 2 and its associated steam generator and at least one associated reactor coolant pump.
(iii) One containment spray or LFSI pump, one shut-down cooling heat exchanger, and associated shutdown cooling piping.
(iv)
One containment spray or l?SI pump, in addition to that in (iii) above, one shutdown cooling heat exchanger, in additicn to that in (iii) above, and associated shuticwn ecoling piping.
(b) At least one (1) of the decay heat removal loops listed above shall be in operation.
(c) With no coolant loop in operation, suspend all operations involving a reduction in boron concentration of the Reactor Coolant System and initiate corrective action to return the required coolant loop to operation in 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.
(4)
Refueling Shutdown Condition (a) At least one'(1) shutdown cooling loop shall be in operation.
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l Amendment No. 3p, 56 2-2 i
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2.0 LIMITING CONDITIONS FOR OPERATION 2.1 Reactor Coolant System (Continued)
I 2.1.1 Operable Components (Continued)
(b) When the water level above the top of the irradiated fuel assemblies seated within the reactor vessel is less than 15 feet, both shutdown cooling heat exchangers and at least two LPS1 or containment spray pumps shall be operable.
Exceptions All decay heat removal loops may be made inoperable for up to 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> provided (1) no operations are permitted that would cause dilution of the reactor coolant system boron concentration,
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(2) no refueling operations are taking place, and (3) all contain-ment penetrations providing direct access from the containment utmosphere to the outside atmosphere are closed within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.
1 (5) At least one reactor coolant pump or one low pressure safety injection pump in the shutdown cooling mode shall i
be in operation whenever a change is being =ade in the boron concentration of the reactor coolant when fuel is in the reactor.
(6) Both steam generators shall be filled above the low steam generator water level trip set point and avail-able to remove decay heat whenever the average temper-i ature of the reactor coolant is above 3C3cF.
Each steam generator shall be demonstrated operable by per-formance of the in-service inspecticn program specified e
in Section 3.3(2) prior to exceeding a reactor coolant temperature of 3000F.
(7) Maxi =um reactor coolant system hydresta-ic test pres-i sure shall be 3125 psia.
A maximum of 10 cycles of 3125 psia hydrostatic tests are alleved.
(S) Reactor coolant system leak and hydrostatic tests shall be conducted within the limitations of Figures 2-1A and 2-1B.
(9) Maximum secondary hydrostatic test pressure shall not exceed 1250 psia.
A mininum temperature of 82 F is
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required.
Only 10 cycles are permitted.
(10) Maximum steam generator steam side leak test pressu '
shall not exceed 1000 psia. A minimum temperature of 82 F is required.
(11) A non-operating reactor coolant pump, shall not be started unless at least one'of the following condi-tions are met:
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Amendment No. 39', 56 2-2a 1
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n 2.0 LIMITING CONDITIONS FOR OPERATION 2.1 Reactor Coolant System (Continued) 2.1.1 Operable Components (Continued)
(a) A pressurizer steam space of 60% by volume or greater exists, or (b) The steam generator secondary side temperature is less than 500F above that of the reactor coolant system cold leg.
i Basis The plant is designed to operate with both reactor coolant 4
i loops and associated reactor coolant pumps in operation and maintain DNBR above 1.30 during all normal operations and anticipated transients.
In the hot shutdown mode, a single reactor coolant loop pro-
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vides sufficient heat removal capability for removing decay heat; however, single failure considerations require that two loops be operable.
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In the cold shutdown mode, a single reactor coolant loop or shutdown cooling loop provides sufficient heat removal cap-i ability for removing decay heat, but single failure consider-l ations require that at least two loops be operable.
- Thus, if the reactor coolant loops are not operable, this specifi-cation requires two shutdown cooling pumps to be operable.
The requirement that at least one shutdown cooling loop be in operation during refueling ensures that:
(1) sufficient cooling capacity is available to remove decay heat and main-tain the water in the reactor pressure ve sel below 2100F as required during the refueling mode, and (2) sufficient coolant circulation is maintained through the reacter core to mini-mice the effects of a boron dilution inciden and prevent boron stratification.
The requirement to have two shutdown cooling pumps operable when there is less than 15 feet of water above the core en-sures that a single failure of the operating shutdown cool-ing loop will not result in a complete loss of decay heat removal capability.
With the reactor vessel head removed and 15 feet of water above the core, a large heat sink is available for core cooling; thus, in the event of a failure of the operating shutdown cooling loop, adequate time is provided to initiate emergency procedures to cool the core.
I When reactor coolant boron concentration,is being changed, the process must be uniform throughout the reactor coolant system volume to prevent stratification of reactor coolant at lover boron concentration which could result in a reacti-vity insertion.
Sufficient =ix!ag of the reactor coolant Amendment No. 56 2-2b
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2.0 LIMITING CONDITIONS FOR OPERATION 2.1 Reactor Coolant System (Continued) 2.1.1 Operable Cenponents (Continued) is assured if one low pressure safety injection pump or one reactor coolant pump is ir.'opere. tion.
The low pressure safety injection pump vill circulate the reactor coolant system volume in less than 35 minutes when operated at rated capaci*/.
The
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pressuriser volume is relatively inactive; therefore, it will tend to have a boron concentration higher than the rest of the i
l reactor coolant system during a dilution operation. Adminis-a trative procedures will provide for use of pressurizer sprays i
to maintain a nominal spread between the boron concentration in the pressurizer and the reactor coolant system during the addition of boron.(1) l Both steam generators are required to be filled above the low steam generator water level trip set point whenever the temper-ature of the reactor coolant is greater than the design temper-ature of the shutdown cooling system to assure a redundant heat removal system for the reactor.
The design cyclic transients for the reactor system are given in FSAE Section h.2.2.
In addition, the steam generators are designed for additional conditions listed in FSAR Section 4.3.h.
Flooded and pressurized conditions on the steam side assure mir.imum tube sheet temperature differential during leak test-1 I
ing.
The minimum temperature for pressurizing the steam gene:-
i ator steam side is 700F.
Formation of a 605 steam space ensures that the resulting pres-sure increase would not result in an overpressurization, should a reactor coolant pump be started when the steam generator secondary side temperature is greater than that of the RCS cold leg.
For the case in which no pressurizer steam space exists, limit-ation of the steam generator secondary side /RCS cold leg AT to 500F ensures that a single lov set point PORV vould prevent an overpressurization due to actuation of a reactor coolant pump.
The exception to Specific'ation 2.1.1(4) requiring all containment penetrations providing direct access from the containment to the outside atmosphere be closed within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> requires that the equipment hatch be closed and held in place by a minimum of four bolts.
4 References (1)
FSAR Section 4.3.7 Amendment No. 56 2-2c 4
2.0 LIMITING C0iDITIONS FOR OPERATION 2.8 Refueline Operations Applicability Applies to operating limitations during refueling operations.
Objective To minimize the possibility of an accident occurring during refueling operations that could affect public health and safety.
Specifications The following conditions shall be satisfied during any refuel-ing operations:
(1) The equipment hatch and one door in the air lock shall properly closed.
In addition, all automatic contain-
. mat isolation valves shall be operable or at least one valve in each line shall be closed.
(2) The five centainment atmosphere and plant ventilation duct radiatien monitors that initiate closure of the containment pressure relief, air sample, and purge e
system valves shall be tested and verified to be oper-able immediately prior to refueling operations.
The five monitors shall employ one-out-of-five logic from separate contact outputs for VIAS.
(3) Radiation levels in the containment and spent fuel storage areas shall te monitored continuously.
(b) Whenever core geometry is being changed, neutron flux shall be centinuously monitored by at least two source range neutror. monitors, with each monitor providir.g continuous visual indication in the centrol room.
When core geometry is not being changed., at least one source range neutron monitor shall be in service.
(5) At least one shutdown cooling pump and heat exchanger shall be in'cperation.
However, the pump and heat ex-changer may be removed from operation fer up to one hour per 8 hour9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> period during the performance of core alter-ations in the vicinity of the reactor ecclant hot les loops or curing manipulation of a source.
(6) During reacter vessel head removal apd while refueling operations are being performed in the reactor, the refuel-ing boron concentration shall be maintained in the reactor coolant system and shall be checked by sampling on each shift.
Amendment No. 2f, 56 2-37
6.0 IIITERIM SPECIAL TECHNICAL SPECIFICATIOi;S 6.1 Limits on Reactor Coolant Pump Operatien 4
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l Arendmentflo.g,yo,11,56 6-1 i