3F0487-10, Application for Amend to License DPR-72,consisting of Tech Spec Change Request 151,revising Mode in Which Hpis & LPIS Actuated to Demonstrate Operability.Fee Paid

Application for Amend to License DPR-72,consisting of Tech Spec Change Request 151,revising Mode in Which Hpis & LPIS Actuated to Demonstrate Operability.Fee Paid

ML20206R482
Person / Time
Site:	Crystal River
Issue date:	04/15/1987
From:	Wilgus W FLORIDA POWER CORP.
To:	NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM)
Shared Package
ML20206R488	List: 3F0487-10, Application for Amend to License DPR-72,consisting of Tech Spec Change Request 151,revising Mode in Which Hpis & LPIS Actuated to Demonstrate Operability.Fee Paid ML20206R540
References
3F0487-10, 3F487-10, NUDOCS 8704220171
Download: ML20206R482 (5)

Text

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Power C 0RPOR ATION April 15, 1987 3F0487-10 U. S. Nuclear Regulntory Commission Attention: Document Control Desk washington, DC 20553

Subject:

Crystal River Unit 3 Docket No. 50-302 Operating License No. DPR-72 Technical Specification Change Request 151

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Dear Sir:

Florida Power Corporation (FPC) hereby submits the enclosed Technical Speci-fication Change Request No. 151. This change would revise the Mode in which the high and low pressure injection system is actuated to demonstrate operability. The current surveillance 4.5.2.f, requires a Mode 6 test. The proposed surveillance 4.5.2.f allows a test in Mode 3, 4, 5, or 6.

An amendment application fee of one hundred fifty dollars ($150), check no.

18452, as required by 10 CFR 170, has been included with this change request.

Sincerely, W. S. Wi gis Vice pr s'Jent, Nuclear rerations PH/ps xc: D' J. Nelson Grace

'egional Administrator, Region II Mr. T. F. Stetka Senior Resident Inspector 8704220171 870415 k PDR p

ADOCK 05000302 PDR I 00

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Post Office Box 219

• Crystal River, Florida 32629

• Telephone (904) 795-3802 A Florida Progress Company

UNITED STATES OF AMERICA NUCLEAR REGULATORY COMIISSION IN THE MATTER )

) DOCKET No. 50-302 FLORIDA POWER CORPORATION )

CERTIFICATE OF SERVICE W. S. Wilgus deposes and says that the following has been served on the Designated State Representative and the Chief Executive of Citrus County, Florida, by deposit in the United States mail, addressed as follows:

Chairman, Administrator Board of County Commissioners Radiological Health Services of Citrus County Department of Health and Citrus County Courthouse Rehabilitative Services Inverness, FL 32650 1323 Winewood Blvd.

Tallahassee, FL 32301 A copy of Technical Specification Change Request No.151 requesting Amendment to Appendix A of Operating Licensing No. DPR-72.

FLORIDA POWER CORPORATION W. f Wilg Vice Pres' t, Nuclear Operations SWORN TO AND SUBSCRIBED BEFORE ME THIS 15TH DAY OF APRIL 1987.

HTCW), l5cu l No ary Public j Notary Public, State of Florida at Large My Commission Expires: June 21, 1987 (NOTARIAL SEAL)

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STATE OF FLORIDA COUNTY OF CITRUS W. S. Wilgus ' states that he is the Vice President, Nuclear Operations for Florida Power Corporation; that he is authorized on the part of said company to sign and file with the Nuclear Regulatory Commission the information attached hereto; and that all such statements made and matters set forth therein are true and correct to the best of his knowledge, information, and belief.

W W 5. Wilg Vice Pres t, Nuclear Operations Subscribed and sworn to before me, a Notary Public in and for the State and County above named, this 15th day of April 1987.

hp $AJ ary Public i

Notary Public, State of Florida at Large, My Commission Expires: June 21, 1987 l

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FLORIDA POWER CORPORATION CRYSTAL RIVER UNIT 3 DOCKET No. 50-302/ LICENSE NO. DPR-72 CHANGE REQUEST No. 151 HIGH PRESSURE INJECTION ACTUATION TESTS LICENSE DOCUMENT INVOLVED: Technical Specifications PORTIONS: 3.5.2 Emergency Core Cooling Systems DESCRIPTION OF REQUEST:

This submittal requests the requirement to test high and low pressure injections pumps and valves during Mode 6 be changed to allow testing in other Modes.

Specifically, we request that "during Mode 6' be changed in Surveillance Requirement 4.5.2.f, to "During Mode 3, 4, 5, or 6.

REASON FOR REQUEST:

This change will allow us to take credit for tests performed during non-refueling outages. We typically would not go to Mode 6 (Remove the vessel head) for a surveillance or Maintenance outage. During the 1986 Reactor Coolant Pump Shaft Outage we were unable to satisfy the 18 month Surveillance Requirement for HPI and LPI pumps and valves. The testing described by specification 4.5.2.f was successfully completed during the RCP Outage startup.

However, because the test was not performed during Mode 6, it could not be used to satisfy Technical Specification 4.5.2.f. Thus we had to request relief from the 18 month interval requirement.

As fuel cycles continue to lengthen, we expect to continue to have non-refueling outages and so, except this problem to occur again. It appears that until this specification is changed, we will need to continue to pursue relief from the test requirements. This change will provide a long term solution.

Additionally, by providing the flexibility to perform this test during several Modes, FPC can better optimize outage time.

EVALUATION OF REQUEST:

The requirement to perform the HPI and LPI tests during Mode 6 was placed in the specification to satisfy FPC commitments for low temperature overpressurization i

protection. Our original commitments stated we would only test HPI pumps when the reactor vessel head is removed from the vessel (Mode 6). LER 84-23,

, Revision 1, February 10, 1986, changed this commitment to allow testing of HPI l pumps and valves with the vessel head on provided LTOP protection is maintained. Specifically, our commitments for the HPI pumps and valves are:

o VALVE COMMITMENT - Motor operated valves MUV-23, MUV-24, MUV-25, and MUV-26 l will be closed and de-energized with their circuit breakers " red tagged" in

( the " locked reset" position to the Nuclear Shif t Supervisor whenever the reactor coolant temperature is below 265'F. If maintenance, testing, or other plant conditions require operation of these valves, the following requirements will be met-t

1. Double valve isolation on the main and recirculation discharge lines is maintained between injection trains, and

2. . The Hp injection . pump in the affected train is de-energized with its circuit breaker " locked out" and " red tagged" to the Nuclear Shift Supervisor, and

3. The Hp injection pump suction or discharge valve in the affected train is de-energized with its circuit breaker in the " locked reset" position and

" red tagged" to the Nuclear Shift Supervisor.

o PUMP C0f9IITNENT - No testing of the HPI pumps (normal operation of a single make-up pump is exempted) will be performed when the reactor coolant temperature is below 280 degrees F,- unless double valve isolation is maintained between the RCS and all flow paths from the pump (s) being tested.

All of our administrative commitments for LTOPs are incorporated into procedures and controlled by the proceddre review and change process (10CRF50.59). In addition, our commitnent tracking system is now used with each procedure change to assure commitments are not deleted or changed unintentionally. Thus, we have established controls to assure the test may be safely performed during Modes 3, 4, 5, or 6.

SHOLLY EVALUATION OF REQUEST: - _

Florida Power Corporation (FPC) proposes this amendment does not -involve a significant hazards consideration. The actuation test will be performed per other established requirements, such as. technical specification 4.0.4 and FPC commitment providing low temperature over pressurization (LTOP) is consistent with Standard Technical Specifications (NUREG-0103), which specify this test during shutdown (i.e.; modes 3, 4, 5, and 6).

Based on the above, FPC finds the amendment will not:

1. Involve a significant increase in the probability or consequence of an accident previously evaluated because the test will continue to be performed and thus assure equipment operability. This change does not increase the probability or consequence of an LTOP's event because preventative measures will be taken per our commitments described above and in LER 84-23.

, 2. Create the possibility of a new or different kind of accident from any accident previously evaluated because it does not require a physical modification to the plant. Test configuration should be similar to that used currently with some additional restrictions.

3. Involve a significant reduction in the margin of safety because setpoints and response times will not be affected.

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