ML17216A725: Difference between revisions
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| document type = OPERATING LICENSES-APPLIATION TO AMEND-RENEW EXISTING, TEXT-LICENSE APPLICATIONS & PERMITS | | document type = OPERATING LICENSES-APPLIATION TO AMEND-RENEW EXISTING, TEXT-LICENSE APPLICATIONS & PERMITS | ||
| page count = 10 | | page count = 10 | ||
| project = | |||
| stage = Request | |||
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Revision as of 09:12, 10 November 2019
| ML17216A725 | |
| Person / Time | |
|---|---|
| Site: | Saint Lucie  |
| Issue date: | 10/10/1986 |
| From: | Woody C FLORIDA POWER & LIGHT CO. |
| To: | Thadani A Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML17216A726 | List: |
| References | |
| L-86-412, NUDOCS 8610170112 | |
| Download: ML17216A725 (10) | |
Text
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Al 0 REGULATORY }FOR} }ATION DISTR I BUT I QN SY (R IDS) ( I~ ACCESSION NBR: 8610170112 DOC. DATE: 86/10/10 NOTARIZED: NO DOCKET ¹ FACIL: 50-335 St. Lucie Plant> Unit 1> Florida Power Zc Light Co. 05000335 AUTH. MANE AUTHOR AFFILIATION WOODY> C. 0 Florida Power Zc Light Co. REC IP. NA}'}E RECIPIENT AFFlLIATION THADANI>A. C. PWR Prospect Directorate 8
SUBJECT:
Application for amend to License DPR-67> revising Tech Spec Pages 3/4 6-10> 3/0 6-11 0 83/0 6-1 re containment air loc ks. Fee DIBTRIDVTIDN CODE TITLE: OR paid.
*00ID CDPIEB RECEIVED: LTR Submittal: General Distribution j ENCL I BITE:
NOTES: RECIPIENT COPIES RECIPIENT COPIES ID CODE/NA}'}E LTTR ENCL ID CODE/NA}'}E LTTR ENCL PWR-8 EB 1 1 PWR-8 PEICSB 2 2 PWR-8 FQB 1 PWR-8 PDB LA 0 PWR-8 PDB PD 01 5 5 TOURI GNY> E 1 PWR-8 PEICSB PWR-8 RSB 1 INTERNAL: AD}}/LF}'}8 0 ELD/HDS2 1 0 SCB 1 NRR/ORAS 0 04 1 RGN2 1 EXTERNAL: EGPIG BRUSKE> S 1 LPDR 03 NRC PDR 02 1 NSIC 05 TOTAL NU}'}HER OF COPIES REGUIRED'TTR 23 ENCL 19
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t t Pl pic Ib i/pnsm+ FLORIDA POWER & LIGHT COMPANY iOCTOBER 1.0 i98g L-86-4I2 Office of Nuclear Reactor Regulation Attention: Mr. Ashok C. Thadani, Director PWR Project Directorate 738 Division of PWR Licensing - B U. S. Nuclear Regulatory Commission Washington, D. C. 20555
Dear Mr. Thadani:
Re: St. Lucie Unit No. I Docket No. 50-335 Proposed License Amendment Containment Air Locks In accordance with IO CFR 50.90, Florida Power and Light Company submits herewith three signed originals and forty copies of a request to amend Appendix A to Facility Operating License DPR-67. The proposed change to the St. Lucie Unit I Technical Specifications make the Unit I Technical Specifications the same as the St. Lucie Unit 2 Technical Specifications. The proposed changes are shown in the accompanying Technical Specification Pages 3/4 6-IO, 3/4 6-I I, and B3/4 6-I. A discussion of the changes is included in the attached safety evaluation and no significant hazards considerations determination. The proposed amendment has been reviewed by the St. Lucie Plant Facility Review Group and the Florida Power and Light Company Nuclear Review Board. In accordance with IO CFR 50.9I(b)(l), a copy of the proposed amendment is being forwarded to the state designee for the State of Florida. ln accordance with IO CFR I70.2I, FPL Check No. 2347 is attached as remittance for the license amendment application fee. V r truly yours, O. Woo y roup Vice President uc lear Energy COW/R JS/gp Attachments cc: Mr. Allan Schubert, Dept. of Health & Rehabilitation Services Dr. J. Nelson Grace, Region II Harold F. Reis, Esquire, Newman & Holtzinger j abzpzTpzzp;.";86zpzp'
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of Florida Power & Light Company, the Licensee herein; That he has executed the foregoing document; that the statements made in this document are true and correct to the best of his knowledge, information, and belief, and that he is authorized to execute the document on behalf of said Licensee.
. W. Dic Subscribed and sworn to before me this
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"'fPalm Beach, State of Florida for the County ROTlRY PUBLIC STATE OF FLORIOA RY CORRISSIOR EXP SEPT 18,1989 My Commission expires: 88RoEo TRRu oERERAL IRS. oRo.
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Safe Evaluation/No Si nificant Hazards Considerations Determination The proposed changes make the St. Lucie Unit I Technical Specifications the same (except for the plant specific information) as the St. Lucie Unit 2 Technical Specifications. These changes are administrative in nature as described below: The changes on page 3/4 6-IO consist of deleting the existing ACTION: and adding the St. Lucie Unit 2 ACTION:. Editorial changes are also made to 3.6.I.3 b. to make it the same as Unit 2. The changes on page 3/4 6- I I consist of deleting the existing SURVEILLANCE REQUIREMENTS and adding the St. Lucie Unit 2 SURVEILL'ANCE REQUIREMENTS. Unit I plant specific information was included as appropriate. The changes on page 83/4 6-l make the Unit I BASES exactly like the Unit 2 BASES. The proposed changes are consistent with the approved St. Lucie Unit 2 Technical Specifications, and are in accordance with IO CFR 50 Appendix J III.D.2.(b)(iii) and the latest C-E Standard Technical Specifications. The proposed amendment is similar to Example (i) of Amendments that are considered not likely to involve significant hazards considerations, identified in the staff procedure for determination of no significant hazards in that the proposed amendment is a purely administrative change to the technical specifications to achieve consistency between St. Lucie Units I & 2. lt has been determined that the proposed amendment involves no significant hazards considerations because there are no changes to the Containment Air Locks and that the proposed changes to the Technical Specifications provide for the surveillance testing of the air lock seals to assure that the overall air lock leakage will not become excessive due to seal damage during the intervals between air lock leakage tests. Therefore, I. There is no change in the probability or consequences of an accident previously evaluated.
- 2. The possibility of a new or different kind of accident from any accident previously evaluated is not created.
- 3. There is no reduction in a margin of safety.
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i ~ ~ a ~ With one containment air lock door inoperable":
- 1. Maintain at least the OPERABLE air lock door closed and either restore the inoperable air lock door to OPERABLE status within 24 hours or lock the OPERABt E air lock door closed.
- 2. Oper ation may then continue until performance of the next required overall air lock leakage test provided that the OPERABLE air lock door is verified to be locked closed at least once per 31 days.
- 3. Otherwise, be in at least HOT STANDBY within the next 6 hours and in COLD SHUTDOWN within the following 30 hours.
- 4. The provisions of Specification 3.0.4 are not applicable.
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- b. With the containment air lock inoperable, except as the result of an inoperable air lock door, maintain at least one air lock door closed; restore the inoperable air lock to OPERABLE status within 24 hours or be in at least HOT STANDBY within the next 6 hours and in COLD SHUTDOWN within the following 30 hours.
If the inner air lock door is inoperable, passage through the OPERABLE outer air lock door is permitted to effect repairs to the inoperable'nner air lock door. No more than one airlock door shall be open at any time. a ~ Within 72 hours following each closing, except when the air lock is being used for multiple entries, then at least once per 72 hours, by verifying the seal leakage is < 0. 01 L as determined by precision flow measurement when the volume between the door seals is pres-surized to greater than or equal to:
- 1. For the personnel air lock, greater than or equal to P ,
$ 9,g~~psig for at least 15 minutes if not tested with tfte automatic tester.
- 2. For the emergency for at least 15 air lock, greater minutes.
than or equal to~i0.0 psig
3/4.6 COHTAIH 1EHT SYSTEMS BASES 3/4.6.1 COHTAIHi'1EHT VESSEL 3/4.6.1.1 COiVTAIHl~iEHT VESSEL INTEGRITY COHTAIhf1EHT VESSEL IHTEGRITY ensures that the release of radio-s active materials from the containment atmosphere will be restricted to those leakage paths and associated leak rates assumed ip the accident analyses. This restriction, in conjunction with the leakage rate limi-tation, will limit the site boundary radiation doses to within the limits of 10 CFR 100 during accident conditions. 3/4.6.1. 2 COHTAIHl1EHT LEAKAGE The limitations on containment leakage rates ensure that the total containment leakage volume will not exceed the value assumed in the accident analyses at the peak accident pressure, Pa (39.6 psig). As an added conservatism, the measured overall integrated leakage rat is furtner limi ed to < 0.7" La or < 0.75 Lt (as applicable) during p r-formance of the periodic tests to account for possible degradation o the containment leakage barriers between leakage tests. The surveillance testing, or measuring leakage rates are consistent with the requirements of Appendix "J" of 10 CFR 50. 3/4.6.1.3 CONTAIN/'~EHT AIR LOCKS The limitations on closure and leak rate for the containment air lgcks pre required to meet the restrictions on COHTAINi~iEHT INTEGRITY and ~
)eB" rate.
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/Ac &rerM ai~ lock leaking<<a//1 no/- dec~e, dkcessiv< doe 4 Sea< du~age d~ii'ny >AD indene(s 8Haem ar'~ loci /eakayc~. k~*.
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