ML20206R670
| ML20206R670 | |
| 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 | |
| ML20206R676 | List: |
| References | |
| 3FO487-12, NUDOCS 8704220213 | |
| Download: ML20206R670 (5) | |
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Power C O R P O R AT IO N April 15, 1987 3F0487-12 U. S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, DC 20555
Subject:
Crystal River Unit 3 Docket No. 50-302 Operating License No. DPR-72 Technical Specification Change Request 153
Dear Sir:
Florida Power Corporation (FPC) hereby submits the enclosed Technical Speci-fication Change Request No. 153.
This change would revise the surveillance test of the Core Flood Tank Isolation Alarm to require a channel calibration instead of an actuation type test.
A corresponding change to the Yechnical Specification bases is also enclosed.
An amendment application fee of one hundred fifty dollars ($150), check no.
18454, as required by 10 CFR 170, has been included with this change request.
Sincerely, W. S. Wi Vice Pr
- dent, Nuclear perations PH/ps xc:
Dr. J. Nelson Grace Regional Administrator, Region II Mr. T. F. Stetka Senior Resident Inspector f*\\
8704220213 870415 1
PDR ADOCK 05000302 P
PDR kt.C. C.
'CJA Post Office Box 219 + Crystal River, Florida 32629 + Telephone (904) 795-3802 A Florida Progress Company
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UNITED STATES OF AIERICA NUCLEAR REGULATORY C005tISSION IN THE MATTER
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DOCKET No.
50-302 FLORIDA POWER CORPORATION
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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.153 requesting Amendment to Appendix A of Operating Licensing No.
FLORIDA POWER CORPORATION I
W. Si Wilgu Vice Presi t, Nuclear Operations SWORN TO AND SUBSCRIBED BEFORE ME THIS 15TH DAY OF APRIL 1987.
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IS U ry Public
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Notary Public, State of Florida at Large My Commission Expires: June 21, 1987 (NOTARIAL SEAL)
STATE OF FLORIDA COUNTY OF CITRilS 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. S.' Wilgus Vice Presi e
, 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.
l Qen
'srv d > f i haryPublic Notary Public, State of Florida at Large, My Commission Expires: June 21, 1987
FLORIDA POWER CORPORATION CRYSTAL RIVER UNIT 3 DOCKET NO. 50-302/ LICENSE NO. DPR-72 CHANGE REQUEST No. 153 CORE FLOOD TANK ISOLATION ALARMS LICENSE DOCUMENT INVOLVED:
Technical Specifications PORTIONS:
3.5.1 Core Flood Tank DESCRIPTION OF REQUEST:
This proposal requests a revision to Surveillance 4.5.1.d to require a CHANNEL CALIBRATION of the Core Flooding Tank (CFT) Isolation Valve Alarm in lieu of an actuation test.
Additionally, a change to the bases is provided describing the actuation of this alarm.
REASON FOR REQUEST:
The current specification explicitly requires the CFT Isolation Alarm be actuated after the Reactor Coolant System (RCS) pressure exceeds 750 psig.
Ad-ditionally, if the alarm is considered inoperable, Specification 4.0.4 requires performing the actuation test prior to entering the applicable mode (prior to exceeding 750 psig in Mode 3).
Typically, the alarm is tested during shutdown within the specified surveillance interval.
However, if the alarm fails the test and shutdown continues per the action statement, the surveillance is difficult to satisfy because 4.0.4 pro-hibits raising RCS pressure to the necessary test pressure in Mode 3.
Although a test in Mode 4 at 750 psig is possible, such a test is not recommended because it brings us close to the Reactor Coolant System pressure / Temperature limits.
This situation also occurs if the 18 Month Surveillance interval is exceeded during a shutdown.
If the shutdown is planned and of a known duration, the test might be performed during the cooldown.
However, this is not always the case.
EVALUATION OF REQUEST:
This proposed change will not decrease plant safety because an equivalent test of the CFT Isolation Alarm will assure alarm operability.
The proposed CHANNEL CALIBRATION is consistent with the type of test performed for other Engineered Safeguards Actuation Instrumentation channels and for the Reactor Protection Instrument channels.
Additionally, because the surveillance will no longer re-quire entry into a degraded mode or increase the likelihood of a low temperature over pressurization event, plant safety will be enhanced.
SHOLLY EVALUATION OF REQUEST Florida Power Corporation (FPC) proposes this amendment will not involve a significant hazards consideration because an equivalent surveillance of the Alarm Channel will be performed.
For other types of Instrument Channels, such as the Reactor protection System and the Engineered Safety Features Actuation System, a channel calibration is performed to assure operability.
Based on the above Fpc findings this amendment will not:
1.
Involve a significant increase in the probability or consequence of an accident previously evaluated because the alarm channel will be tested to assure operability.
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DCGET No. 50-302/ LICENSE NO. DPR-72 CHANGE REQUEST NO. 153
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CORE FLOOD TANK ISOLATION ALARMS Page 2 2.
Create the possibility of a new or different kind of accident from any accident previously evaluated because the change does not modify the plant or require a significantly different plant equipment configuration.
3.
Involve a significant reduction in the margin of safety because the change will not revise the channel setpoint.
Crystal River - Unit 3 (Licensing-88)