ML20199H064
| ML20199H064 | |
| Person / Time | |
|---|---|
| Site: | Crystal River  |
| Issue date: | 01/27/1998 |
| From: | Hebdon F NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML20199H068 | List: |
| References | |
| NUDOCS 9802040402 | |
| Download: ML20199H064 (5) | |
Text
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UNITED STATES
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NUCLEAR REGULATORY COMMISSION
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WASHINGTON, D.C. 20066-0001 FLORIDA POWER CORPORATION CITY OF ALACHUA CITY OF BUSHNELL CITY OF GAINESVILLE CITY OF KISSIMMEE CITY OF LEESBURG CITY OF NEW SMYRNA BEACH AND UTILITIES COMMISSION. CITY OF NEW SMYRNA CITY OF OCALA ORLANDO UTILITIES COMMISSION AND CITY OF ORLANDO SEMINOLE ELECTRIC COOPERA'lVE. If;C.
CITY OF TALLAHASSEE QQQKET NO. 50-302 CRYSTAL RIVER UNIT 3 NUCLEAR GENERATING PLANT l
AMENDMENT TO FACILITY OPERATING LICENSE i
l Amendment No.164 License No. DPR-72 1.
The Nuclear Regulatory Comminion (the Commission) has found that:
A.
The application for amendment by Florida Power Corporation, et al. (the licensees) dated October 31,1997, as supplemented December 1, and 13,1997, and January 19,1998, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations set forth in 10 CFR Chapter I; B.
The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C.
There is reasonable assurance (I) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; D.
The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.
4802040402 900127 PDR ADOCK 05000302 p
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2.
Accordingly, the license is hereby amended as indicated in the attachment to this license amendment, to read as follows:
Paragraph 2.C.(5)
"Within six months of the date u; issuance of this license Florida Power Corporation shall complete modifications to the level indication of the borated water
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and installation of dual setpoint pilot-operated relief valve on the pressurizer."
Paragraph 2.C.(11)
A system of thermocouples added to the decay heat (DH) drop and Auxiliary Pressurizer Spray (APS) lines, ccpable of detecting flow initiation, shall be operable for Modes 4 through 1. Channel checks of the thermocouples shall be performed on a monthly basis to demonstrate operability, if either the DH or APS system thermocouples becomo inoperable, operability shall be restored within 30
- days or the NRC shall be informed, in a Special Report within the following fourteen (14) days, of the inoperability and the plans to restore operability.
The license is hereby also amended to authorize revision of the Final Safety Analysis Report (FSAR) as set forth in the application for amendment by Florida Power Corporatica dated December 1, and 13,1997, and January 19,1998, for monitoring sump boron concentration including concentration delay times and application of 25%
safety factor as discussed in the attached safety evaluation. The licensee shall submit the revised FSAR authorized by this amendment describing procedure EM-225B with the next update of the FSAR in accordance with 10 CFR 50.71(e).
3.
This license amendment is effective as of its date of issuance and shall be implemented within 30 days.
FOR THE NUCLEAR REGULATORY COMMISSION Frederick J. Hebdon! Director Project Directorate 113 Division of Reactor Projects - 1/11 Office of Nuclear Reactor Regulation
Attachment:
Pages 4a,5 and Sa of License DPR-72*
Date ofissuance: January 27, 1998
- Pages 4a, 5, and Sa are attached for convenience, for the composite license to reflect this change.
- 4a -
I i) SR 3.8.4.5 shall be successfully demonstrated prior to entering MODE 4 on the first plant start-up following Refuel Outage g.
j) SR 3.8.7.1 shall be successfully demonstrated no later than 7 days following the implementation date of the ITS.
k) SR 3.8.8.1 shall be successfully demonstrated no later than 7 days following the implementation date of the ITS.
2.C.(3)
Florida Power Corporation shall not operate the reactor in operational Modes 1 and 2 with less than three reactor coolant pumps in operation until safety analyses for less than three pump operation have been submitted by the licensees and approval has been granted by the Commission by amendment to this license.
2.C.(4) del.ETED per Amendment No. 20 dated 7-3-79.
2.C.(5)
Within six months of the date of issuance of this license. Florida Power Corporation shall complete modifications to the level I
indication of the borated we er storage tank anu installation of dual setpoint pilot operate;.^elief valve on the pressurizer.
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Amendment No. b 40 -149, if4 3
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lant ystem e ggpressu sati 2.c.(7) Prior to startup following the first regularly scheduled refueling outage, Florida io.ser Corporation shall scuffy to the satisfaction of tr,e Cornisison, the reactor coolant with regard to pressure sensing lines to the f
.tial pressure transt.iitters.
2.c.(a) dithin three sonths of issuance of this license, Florida Power Corporation shall auhtiit to the Cont.insion a proposed surveillance pecgram for coattorisy the contalanent for the
- "p.trpose of deter. tining any future delamination of the i
f).Q..(%) Fire protection
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Florida power Corporation shall implement'and maintain in eff provisions of the approved fire protection program as descr ect all 8
Final Safety Analysis Report for the facility and as appr Safety Evaluation Reports dated July e t-M -93 oved in the January 4, 1983. July 18, 1985 27, 1979, January 22, 1981, following provisions:
and March 16, 1988, subject to the 1
The licensee may make changes to the approved fire pro program without prior approval of the Cossaission only if thos changes would not adversely affect the ability to achieve an maintain safe shutdown in the event of a fire.
A dd*d U.(10) The d'esign of the reacter coolant pump supports need not M
include consideration of the effects of postulated ruptures Ann:L of the prinary reactor coolant loop piping and ray be revised M,
in accordance with Florida Power Corporation's amendmert g/ g _
- reouest of April 24, 1986, 2.C.(11)
Auxiliary Pressurizer Spray (APS)A system of thermoco initiation, shall be operable for Modes 4 through 1. lines, capabl demonstrate operability.of the thermocouples shall be perfo Channel checks If either the OH cr APS system thermocouples become inoperable, operability shall be restored within 30 days or the NRC shall be informed, in a Special Report within the following fourteen (14) days, of the inoperability and the plans to restore operability.
Ammaart m.164 r
pg n.
es.
2.0 Physical Protectio')
The licensee shall fully implement and maintain in effect all provisions of the Commission-approved physical security, guard training and quellfication, and safeguards contingency plans including amendments made pursuant to provisions of the Misev11aneous Amendments and-Search Requirements revisions to 3
-10 CFR 73.55 (51 FR 27817 and 27822) and to the authority of 3
10 CFR 50.90 and 10 CFR 50.54(p).
The plans, which contain
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Safeguards Information protected under 10 CFR 73.21, are entitled:
" Crys al River Nuclear Power Plant, Unit 3. Modified Amended Security i
k Plan," with revisions submitted through April 14, 1988; " Crystal River Nuclear Power Plant, Unit 3 Security Training and Quali-3 fication Plan," with revisions submitted through July.29,1987; and " Crystal River Nuclear Power Plant, Unit 3, Safeguards Contingency Plan," with revisions submitted through July 23, 1987.
Changes made in accordance with 10 CFR 73.55 shall be implemented in accordance with the schedule set forth therein.
l a.O.[E)" Crystal River Nuclear Plant Unit 3 Security Training and t
Qualification Plan", Revision 3, dated Decelser 30,1981, sub-mitted by letter dated March 19,1982, and consisting of all Added previous revisions. This plan shall be followed in accordance with 10 CFR 73.55(b)(4), 60 days after approval by the Comission, per All security personnel, as required in the above plans, shall be g4 qualified within two years of this approval.
The licensee may make
@JL changes to this plan without prior Comission approval if the changes do not decrease the safeguards effectiveness of the plan.
g,y3 The'licenset shall maintain records of and submit reports concerning such changes in the same manner as required for changes-made to the Security Plan and Safeguards Contingency Plan pursuant to 10.CFR 50.54(p).
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