3F0585-19, Application for Amend to License DPR-72,consisting of Tech Spec Change Request 6 Re Undervoltage Protection Equipment. Certificate of Svc Encl
| ML20128L560 | |
| Person / Time | |
|---|---|
| Site: | Crystal River  |
| Issue date: | 05/28/1985 |
| From: | Westafer G FLORIDA POWER CORP. |
| To: | Denton D Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML20128L564 | List: |
| References | |
| 3F0585-19, 3F585-19, NUDOCS 8505310386 | |
| Download: ML20128L560 (5) | |
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Power C OR PO R ATION May 28,1985 3F0585-19 Mr. H. R. Dendon, Director Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, DC 20555
Subject:
Crystal River Unit 3 Docket No. 50-302 Operating License No. DPR-72 Technical Specification Change Request No. 6, Rev.1
Dear Sir:
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Fiorida Power Corporation hereby submits the enclosed three (3) originals and forty N
('#0) copies of Technical Specification Change Request No. 6, Rev. I requesting /
amendment to Appendix A of Operating License No. DPR-72. As part of this request, proposed replacement pages for Appendix A are enclosed.
This amendment request proposes technical specificaticns for the undervoltage protection equipment at Crystal River Unit 3.
Sincerely,-
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G. R. Westafer Manager, Nuclear Operations Licensing and Fuel Management PGH/feb Enclosures cc:
Dr. J. Nelson Grace Regional Administrator, Region II Office of Inspection and Enforcement U.S. Nuclear Regulatory Commission s
101 Marietta Street N.W., Suite 2900 Atlanta, GA 30323 g
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850531038685g8py2 DR ADOCK O GENERAL OFFICE 3201 Thirty-fourth Street South e P.O. Box 14042, St. Petersburg, Florida 33733
- 813-866-5151
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-STATE OF FLORIDA COUNTY OF PINELLAS G. R. Westafer states that he is the Manager, Nuclear Operations Licensing and Fuel Management 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.
d ___.
G. R. WestaTer
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Manager, Nuclear Op6 rations Licensing and Fuel Management Subscribed and sworn to before me, a Notary Public in and for the State and County above named, this 28th day of May,1985.
Notar? PQlic Notary Public, State of Florida at Large, My Commission Expires: November 12,1986
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UNITED STATES OF AMERICA NUCLEAR REGULATORY COMMISSION IN THE MATTER OF
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DOCKET No. 50-302 FLORIDA POWER CORPORATION
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CERTIFICATE OF SERVICE G. R. Westafer 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. 6 requesting amendment to Appendix A of Operating Licensing No. DPR-72.
FLORIDA POWER CORPORATION Y
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w G. R. Wesfaf6r
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Manager, Nuclear Operations Licensing and Fuel Management SWORN TO AND SUBSCRIBED BEFORE ME THIS 28th DAY OF MAY 1985.
o Notai7Public f
Notary Public, State of Florida at Large My Commission Expires: November 12,1986 (NOTARIAL SEAL)
FLORIDA POWER CORPORATION CRYSTAL RIVER UNIT 3 DOCKET No. 50-302/ LICENSE NO. DPR-72 REQUEST NO. 6, REVISION 1 UNDERVOLTAGE PROTECTION LICENSE DOCUMENT INVOLVED: Technical Specifications PORTION:
3.3.2.1 tingineered Safety Feature Actuation System Instrumentation DESCRIPTION OF REQUEST:
This change will add Technical Specifications for the second level of undervoltage protection equipment installed at Crystal River Unit 3.
REASON FOR REQUEST:
By letter dated June 6,1977, the Nuclear Regulatory Commission required Florida Power Corporation to compare the design of the Crystal River Unit 3 electrical distribution system with NRC positions contained in that letter. Florida Power Corporation was also required to submit detailed design requirements and proposed Technical Specifications for any modifications necessary to meet those positions. Enclosed are the proposed Technical Specifications.
EVALUATION OF REQUEST:
The proposed design features of the existing loss-of-voltage relays (one per phase on each bus) are arranged in a two-out-of-three logic scheme. These relays are the inverse time delay type, with the minimum time to trip (7.8 seconds) occurring at 0 volts. In addition, time delay relays are installed (one per phase in each bus) and arranged in a three-out-of-three logic scheme as an undervoltage trip. These relays are set to trip at 94.5% of the motor nominal voltage (4000 V), with a total response time of 23 seconds.
If the undervoltage condition persists for 7 seconds, the diesel generator is started.
If the condition continues for an additional 13 seconds, load shedding occurs and the diesel generator output breakers close within the subsequent 3 seconds. The logic schemes and i
time delays for the proposed system will protect the plant from spurious bus trips while affording sufficient protection to avoid equipment damage during loss of voltage and sustained degraded grid conditions.
The setpoint delay times specified in the proposed Technical Specification include an allowance for manufacturer's recommended tolerance for the relays.
For example, the inverse time delay relay should be correct within 7% (.55 Volts) and the degraded voltage relays should be correct within 10% (.7 Volts).
We have not proposed Technical Specification testing requirements to demonstrate independence of the on-site and offsite power sources, as requested in the Supplemental Safety Evaluation, August 24, 1983. The undervoltage protection _ system was not designed and installed to simulate interruption and reconnection of the on-site power sources concurrent with a undervoltage or loss of voltage event. Therefore to verify independence, a diesel generator trip, an additional load shed, auto-start and powering emergency loads l
would be necessary. As explained in our response to generic letter 84-15, Florida Power has attempted to decrease the number of diesel generator run tests and tag-outs in order to reduce mechanical wear. The requested test would require additional diesel generator run i
tests and stop-start cycles on the emergency loads. Therefore, Florida Power Corporation l
has not included the proposed test in this submittal.
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FLORIDA POWER CORPORATION CRYSTAL RIVER UNIT 3 DOCKET NO. 50-302/ LICENSE NO. DPR-72 REQUEST NO. 6, REVISION 1 SIGNIFICANT HAZARDS CONSIDERATION DETERMINATION DESCRIPTION OF AMENDMENT REQUEST:
The proposed amendment would change the Technical Specifications for engineered safety features instrumentation to include operability and surveillance requirements for the undervoltage protection instrumentation.
BASIS FOR PROPOSED NO SIGNIFICANT HAZARDS CONSIDERATION DETERMINATION:
The Commission has provided guidance concerning the application of standards of no significant hazards consideration by giving certain examples (43 FR 14870, April 6,1983).
One of the examples of actions considered likely to involve no significant hazards consideration is example "(ii), a change that constitutes an additional limitation restriction or control not presently included in the Technical Specifications: For example, a more stringent surveillance requirement." Since this Amendment clearly constitutes an additional limitation to be included in the Technical Specifications, we have determined that the proposed changes do not involve a significant hazards consideration.
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