ML19339C540
| ML19339C540 | |
| Person / Time | |
|---|---|
| Site: | Fort Calhoun  |
| Issue date: | 11/14/1980 |
| From: | OMAHA PUBLIC POWER DISTRICT |
| To: | |
| Shared Package | |
| ML19339C534 | List: |
| References | |
| NUDOCS 8011180569 | |
| Download: ML19339C540 (9) | |
Text
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- 2. 0 LIMITING CCNDITIONS 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.
g Opecifications Limiting conditions for operation are as follows:
1 (1) Reactor Critical All four (h) 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 10-15 of rated power and the flow requirements of Table 1.1 No. 2 are met.
(2) Hot Shutdown or 3000F < Teold 1 515 F
, (a) The reactor coolant loops listed belov shall be oper-4 able:
(.1) Reactor coolant loop 1 and at 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 operations 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.
Amendment No. % , kT 2-1 ATTACICC'T A
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- 2.0 LIMITING CONDITIONS FOR OPERATION l 2.1 Reactor Coolant System (Continued) 2.1.1 Operable Components (Continued)
(c )- If fever.than the above required rer.ctor coolant pumps are operable, the required
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pumps shall be restored to operable status l 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 4 placed in cold shutdown within the next 12 i hours.
0 (3) cold Shutdown or'2100F<Teold 1 300 F (a) . At least two (2) of the decay heat re= oval loops listed below shall be operable:
i (i) Reactor coolant loop 1 and its associated a 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.
7 (iii) One containment spray or LpSI pump, one shut-down cooling heat exchanger, and associated ,
shutdown cooling piping.
(iv)
One containment spray or LFSI pu=p, m. addition to that in (iii) above, one shutdown-cooling
! heat exchanger, in addition to that in (iii) above, and associated shutdown cooling piping.
j (b) At least one (1) of the decay heat removal loops listed above shall be in operation.
Exceptions All reactor coolant pumps and decay heat removal loops i 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 reacter coolant system boron concentration, and (2) core outlet temperature is maintained at least 100F below saturation temperature.
(4) Refueling 7hutdown Condition (a) At lea it one (1) shutdown cooling loop shall be in
! operation.
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- (b) If shutdown cooling is not in operation, all contain-cent penetrations providing direct access' from the l containment atmosphere to the outside atmosphere shall be closed within 8. hours. l Amendment No. 39- 2-2 L
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i 2.0 LIMITING CONDITIONS FOR OPERATION 2.1 Reactor Coolant System (Continued) l 2.1.1 Operable Components (Continued)
I (c) 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 ex-changers and at least two LFSI or containment spray pumps shall be operable.
l Exceptions i
j All decay heat removal loops may be made ir. operable 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 operatiotv3 are permitted that would cause dilution of the reactor coolant system boron concentration, and (2) no refueling operations are taking place.
(5) At least one reactor coolant pu=p or one low pressure safety injection pump in the shutdown cooling mode shall be in operation whenever a change is being made in the
- boron concentration of the reactor coolant when fuel is in the reactor.
I (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- e ature oof the reactor coolant is above 3000F. Each steam generator shall be demonstrated operable by per-formance of the in-service inspection program specified in Section 3.3(2) prior to exceeding a reactor coolant temperature of 3000F.
(7) Maximum reactor coolant system hydrostatic test pres-sure shall be 3125 psia. A maximum of 10 cycles of 3125 psia hydrostatic tests are allowed.
(8) Reactor coolant system leak and hydrostatic tests shall be conducted within the limitations of Figures 2-1A and 2-13.
(9) Maximum secondary hydrostatic test pressure shall not exceed 1250 psia. A minimen temperature of 820F is required. Only 10 cycles are permitted.
l (10) Maximum steam generator steam side leak test pressure shall'not exceed 1000 psia. A minimwm temperature of 820 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:
. Amendment No. 39 2-2a
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.
Basis The plant is designed to operate with both reactor coolant i loops and associated reactor coo] ant pumps in operation and maintain DNBR above 1.30 during all nornal operations and anticipated transients.
In the hot shutdown mode, a single reactor coolant loop pro-vides sufficient heat removal capability for removing decay heat; however, single failure considerations require that two loops be operable.
In the cold shutdown mode, a single reactor coolant loop or shutdown cooling loop provides sufficient heat removal cap-ability for re=oving decay heat, but single failure consider-ations require that at least two loops be_ operable. Thus, ,
if the reactor coolant loops are not operable, this specifi-cation requires tv- lovn cooling pumps to be operable.
The requirement tn . 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 vessel belov 2100F as required during the refueling mode, and (2) sufficient coolant circulation is maintained through the reactor core to mini-mice the effects of a boron dilution incident 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 cf a failure of the operating shutdown cooling loop, adequate time is provided to initiate emergency procedures to cool the core.
1 knen 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 lower boron concentration which could result in a reacti-vity insertion. ' Sufficient mixing of the reactor coolant 2-2b e
2.0 LIMITING CONDITIONS FOR OPERATION 2.1 Reactor Coolant System (Continued) 2.1.1 Operable Components (Continued) is assured if one low pressure safety injection pump or one reactor coolant pu=p is in operation. The low pressure safety injection pump will circulate the reactor coolant system volume in less than 35 minutes when operated at rated capacity. The pressurizer volume is relatively inactive; therefore, it will tend to have a boron concentration higher than the rest of the reactor coolant system during a dilution operation. Adminis-trative procedures vill provide for use of pressurizer sprays to maintain a nominal spread betv'een the boron concentration in the pressurizer addition of boren.(and
- 1) the reactor coolant system during the Both steam generators are required to be filled above the low steam generator vater 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 re= oval system for the reactor.
The design cyclic transients for the reactor system are given in FSAR Section 4.2.2. In addition, the steam generators are designed for additional conditions listed in FSAR Section L.3.h.
Flooded and pressurized conditions on the steam side assure minimum tube sheet temperature differential during leak test- ,
ing. The minimum temperature for pressurizing the steam gener-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 seconf 3ry side /RCS cold leg AT to 500F ensures that a single low set point PORY vould prevent an overpressurization due to actuation of a reactor coolant pump.
Re ferences (1) FSAR Section h.3,~
2-2c
2.0 LIMITING CONDITIONS FOR OPERATION 2.8 Refueling Overations 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 be properly closed. In addition, all automatic contain-ment isolation valves shall be operable or at least one valve in each line shall be closed. l (2) The five containment atmosphere and plant ventilation duct radiation 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 be monitored continaously.
(4) Whenever core geometry is being changed, neutron flux shall be continuously monitored by at least two source range neutron monitors, with each monitor providing continuous visual indication in the control room. When ctre 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 operation. However, the pump and heat ex-changer may be removed from operation for 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 coolant hot les loops or during manipulation of a source.
(6) During reactor vessel head removal and while refueling operations are being performed in the reactor, the refuel-ing boron concentrstion snall be maintained in the reactor coolant system and shall be checked by sampling on each shift.
Amendment No. 25 2-37
6.0 INTERIM SPECIAL TECHNICAL SPECIFICATIONS 6.1 Limits on Reacter Coolant Puso Operation DELETED Ament;ent No. /, p, 32 6-1
DISCUSSION It is the District's conclusion that the provisions incorporated in this amendment provide adequate assurance of reliable decay heat removal capability.
The preceding amendment deviates from the Model Technical Speci-fications in four respects.
(1) The instrumentatien installed at Fort Calhoun Station makes it impractical to comply with the portion of Special Test Exception 3.10.3 vhich establishes the reactor trip setpoints at < 15% of rated power. Hevever, this require-ment is unnecessary since adequate protection is provided by the. variable high power trip channels as discussed in Technical Specification 1.3(1).
(2) Provisions have been added to the cold shutdown and re-fueling shutdown condition specifications which will allow inoperability of the shutdown cooling system for up to 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />. The configuration of the shutdown cooling system is cuch that a system outage is required for the maintenance of certain components. Past experience has indicated that shutdown cooling can be removed for 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> without unacceptable temperature rise in the primary system.
(3) A refueling cavity water level of 15 feet is adequate to, provide a heat sink for decay heat. The basis for 23 feet is to provide snielding for fuel movement. Therefore, since 15 feet provides for adequate heat removal and allows more operating flexibility, it is proposed that the 15 feet level be utilized.
(4) Surveillance requirements have_not been included. Verifi-cation of four pump operation is unnecessary since the reactor protective system automatically trips the reactor at less than 95% of four pump flov. The operations staff has been. trained to continuously monitor plant parameters to ensure compliance with limiting conditions for operation (LCO's). Sufficient instrumentation is available in the control room to allow such monitoring of all parameters pro-posed in this amendment. It is the District's opinion that verif7ing compliance with LCO's at discrete intervals (such as every h hours), rather than continuously, may actually.
, decrease the level of safety.
Section 2.8 of the Technical Specifications has been amended' to allow an outage .of the shutdown cooling system during certain refueling operations, consisten_t with 3.9.8.1 of the Model Technical Specifica-tions.
Interim Technical Specification 6.1 has been eliminated since it is superseded by the other requiremento of- this proposed licence chance.
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o JUSTIFICATION FOR FEE CLASSIFICATION The proposed amendment is deemed to be Class III within the meaning of 10CFR170.22 because its acceptability has been identified by Commission positions. The Comission identified the need and format for the pro 7osed amendment by letter dated June 11, 1980.
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