ML20211G352

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Proposed Tech Spec 3/4.7.3 Modifying Surveillance Requirements Re Operability of RCIC Sys.Related Info Encl
ML20211G352
Person / Time
Site: Perry FirstEnergy icon.png
Issue date: 02/20/1987
From:
CLEVELAND ELECTRIC ILLUMINATING CO.
To:
Shared Package
ML20211G333 List:
References
NUDOCS 8702250355
Download: ML20211G352 (6)
v • d • e


Text

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PLANT SYSTEMS

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3/4.7.3 REACTOR CORE ISOLATION COOLING SYSTEM LIMITING CONDITION FOR OPERATION 3.7.3 The an OPERABLE

.x APPLICABILITY: OPERATIONAL CONDITIONS 1, 2 and 3* with reactor steam dome pressure greater than 150 psig.

ACTION:

With the RCIC system inoperable, operation may continue provided the HPCS system is OPERABLE; restore the RCIC system to OPERABLE status within 14 days or be in at least 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 /> and reduce reactor steam dome pressure to less than or equal to 150 psig within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

SURVEILLANCE REQUIREMENTS 4.7.3 The RCIC system shall be demonstrated OPERABLE:

a.

At least once per 31 days by:

1.

Verifying by venting at the high point vents that the system piping from the pump discharge valve to the system isolation valve is filled with water.

2.

Verifying that each valve, manual, power operated or automatic in the flow path that is not locked, sealed or otherwise secured in position, is in its correct position.

3.

Verifying that the pump flow controller is in the correct position.

b.

When tested pursuant to Specification 4.0.5 by verifying that the RCIC pump develops a flow of greater than or equal to 700 gpm in the test flow path with a system head corresponding to reactor vessel operating pressure when steam is being supplied to the turbine at 1020 + 25 - 100 psig (steam dome pressure).*

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  • The provisions of Specification 4.0.4 are not applicable provided the surveillance is performed within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> after reactor steam pressure is I

adequate to perform the test.

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BACKGROUND INFORMATION On February 16, 1987 during the performance of Periodic Test Instruction (PTI)

E51-P001 " Reactor Core Isolation Cooling System (RCIC) Tuneup to the Reactor Pressure Vessel" (RPV) reactor level instrumentation anomalies were identified.

At the beginning of the test reactor thermal power was approximately 8% of

-rated with one bypass _ valve approximately 90% open. Reactor coolant temperature was approximately 540 degrees and RPV pressure 940 psig. RCIC was manually initiated at 1055, injecting flow into the RPV at 700 gpm.

At 1100, plant operators identified various reactor water level instruments common to the A referenced leg indicating upscale (>230 inches). The instrumention on the A reference leg was declared inoperable and actions initiated to comply with Technical Specifications. RCIC testing continued and similar instrument anomolies were identified on the D reference leg at 1150. The RCIC testing was then secured at 1156. All RPV level instrumentation returned to normal approximately 30 seconds following the RCIC injection being secured.

After review of the sequence of events, it was determined that additional RCIC vessel injection testing should be conducted. This was to determine the RCIC injection flow rate at which the RPV level instrumentation anomolies occurred.

A Special Test Instruction (SXI) - 011 "RCIC Vessel Injection Test" was developed, reviewed and approved by the Plant Operations Review Committee (PORC).

SXI-Oll was performed on February 18 with reactor thermal power approximately 5% of rated with one bypass valve approximately 60% open. Reactor coolant temperature was approximately 520 degrees and RPV pressure 920 psig. The test was initiated at 2031 with RCIC injection flow at approximately 260 gpm.

RPV level instruments on the D reference leg immediately began to increase and within 30 seconds were offscale high. At approximately 2034 the A reference leg instrumentation indications also began to increase. RCIC injection flow was then reduced to approximately 140 gpm.

The A reference leg instrument indications returned to normal approximately 20 seconds following the flow reduction. This test was repeated 2 additional times with various flow plateaus between 150 and 280 gpm.

It was concluded based upon the duta that RCIC injection flow at or below 210 gpm af fected no other instruments except those connected to the D reference legs.

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RCIC INOPERADLE UP TO 75% PCWER g

The Reactor Core Isolation Cooling (RCIC) and High Pressure Core Spray (HPCS) systems are both designed to ensure that the reactor pressure l

vessel (RPV) water level remains above Level 1 for a loss of feedwater transient.

With RCIC inoperable the HPCS is backed up by the Auto-i matic Dnpressurize. tion System (ADS) plus the low pressure Emergency Core Cooling (ECC) systems.

The most limiting transient for RCIC inopereble is the loss of feredwater transient.

An analysis of a loss of f eedwater#

transient hen been performed for Perry at 75%

power assumi ng RCIC inoperable pl us a single failure of the HPCS systwm.

The ' conser va ti ve 10CFR50 Appendix K decay heet model end the Technical Specification MAPLHGR value of 0.87 for 75% power were used in the 7

analysis.

These assumptions are identical to the FSAR ECCG performance analysis with the e::ception of the initial power leve].

Initiation of thd ADS occurs et approximately 14 minutes into the event on low water level (Level 1) plus a two minute delay.

The low pressure ECC systems then initiate and rapidly restore the water level to the normal range.

1he calculated PCT for this case is 792 F which is only slightly above the normal operating temperature of the cladding.

Thus, adequate protection is provided for the fuel and no fuel damage is expected to occur with RCIC inoperable.

Figures i

b' through 3 show the pressure, water level and cladding temperature i

respenses for this cese.

The ECCS performance analyses in Section 6.3 of the Perry FSAR take no cr edi t f or the RCIC systum and are thus unaffected by having it deelared i noperable.

!?aned on these calculaticos it i s concluded that.

operation et up to 75% power With RCIC inoperabl e i s justi f i ed.

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