L-76-119, Letter Request to Amend Appendix a of Facility Operating Licenses. Proposes Technical Specification Changes Relating to Surveillance of Safety-Related Hydraulic Snubbers
| ML18227D861 | |
| Person / Time | |
|---|---|
| Site: | Turkey Point  |
| Issue date: | 03/22/1976 |
| From: | Robert E. Uhrig Florida Power & Light Co |
| To: | Stello V Office of Nuclear Reactor Regulation |
| References | |
| L-76-119 | |
| Download: ML18227D861 (7) | |
Text
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NRC DISTRIBLITIQNFDA, RT gP Po U.S. NUCLFAA AEGULATOAYCOMMISSION CKET MATERIAL DOCKET NUMBER 50-2507~
FILE NUMBER Mr. V. Stello IZA.ETTE R XRDRIGINAL 0 COPY 0 NOTOR IZE D WUNC LASS IF I E D FROM:
FPL Miami, Fla.
33101 R.ED Uhrig PROP DATE OF DOCUMENT 3-22-76 DATE RECEIVED 3-29-76 NUMBEA OF OOPIES RECEIVED 3 Orig & 37 CC I DEscRIPTIDN Ltr requesting or am t to PP j
of OL/DPR-31 & DPR-41 related to hydraulic snubbers
& traas the following:
ENcI.osURE Revised
& addi pages to Proposed Chan e P'6 re to hydraulic snubbers...
(40 cys encl rec'd)
! PLA?Q NAYE Turkey Pt. Units 3 & 4 SAFETY ASSXGNED AD BRANCH CHXEF:
FOR ACTION/INFORMATION ASSIGNED AD.
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FLORIDA POWER 8c LIGHT COMPANY March 22, 1976 L-76-119 Director of Nuclear Reactor Regulation Attention:
Mr. Victor Stello, Jr., Director Division of Operating Reactors U. S. Nuclear Regulatory Commission Washington, D.
C.
20555
Dear Mr. Stello:
Re:
Turkey Point Units 3 and Docket Nos.
50-250 and Proposed Amendment to Facility Ooeratin Licenses DPR-31 and DPR-41 In accordance with 10 CFR 50.30, Florida Power a Light Company submits herewith three (3) 'signed originals and forty (40) conformed copies of a request to amend Appendix A of Facility Operating Licenses DPR-31 and DPR-41.
This submittal proposes Technical Specification changes relating to thh surveillance of safety-related hydraulic snubbers at Turkey Point Units 3 and 4.
The proposal supplements and modifies our proposal of November 6,
1974 and is based on model Technical Specifications transmitted to Flor'ida Power 6 Light Company by your staff on December 24, 1975.
The proposed Technical Specification changes are as described below and as shown in the accompanying Technical Specification pages bearing the date of this letter in the lower right hand corner.
Pacae ii The Table of Contents is revised to include Sections 3.12 and 4.14.
Pacae iii The Table of Contents is revised to include Sections B3.12 and B4.14.
P ace e ice The List of Tables is.revised to include Table 3.12-1.
c 3107 HELPING BUILD FLORIDA
Director of Nuclear Reactor Regulation Page Two March'2, 1976 Page 3.12-1 A new specification. 3.12 is added to define the limiting con-ditions for operation applied to the operability of safety-related hydraulic snubbers.
Table 3.12-1, Sheets 1 throu h 4
A new Table 3.12-1 is added to identify all safety-related hydraulic snubbers on Units 3 and 4.
The table has four categories which identify snubbers that are (a) in high radiation areas, (b) especially difficult to remove, (c) inaccessible during normal operation, and (d) accessible during normal operation.
There are currently no hydraulic snubbers which fall in three of the four categories,
- however, these categories are included for ease of'future amendment should hydraulic snubbers ever be installed in such areas.
Although they are not inaccessible during power operation, it.
is proposed that hydraulic snubbers located inside containment be inspected independently from those outside containment in order to prevent unnecessary radiation exposure to those per-sonnel who perform snubber inspections.
Historically, most inoperable snubbers have been found outside containment, there-fore, flexibilityin this Technical Specification is considered advisable to preclude unnecessary.
containment entry during power operation.
Pa es 4.14-1'nd 4.14-2 A new specification 4.14 is added to designate the surveillance requirements applicable to safety-related hydraulic snubbers.
Pages B3.12-1 and B3.12-2 A new section B3.12 is added to provided bases for new specification 3.12.
Pa e B4.14-1 A new section B4.14 is added to provide bases for new specifica-tion 4.14.
The proposed amendment has been reviewed and the conclusion reached that it does not involve a significant hazards considera-tion, therefore, prenoticing pursuant to 10 CPR 2.105 should not be required.
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Director of Nuclear Reactor Regulation Page Three March 22, 1976 We request that, upon approval of this proposed amendment, the snubber inspection reporting requirements of the Directorate of Licensing letter of November 8,
1973 from R.
C.
DeYoung to Robert E. Uhrig be eliminated.
Very truly yours, Robert E. Uhrig Vice President REU/MAS/cpc
'ttachment cc:
Mr. Norman C. Moseley Jack R.
Newman, Esquire
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