View source for L-76-119, 03/22/1976 Letter Request to Amend Appendix a of Facility Operating Licenses. Proposes Technical Specification Changes Relating to Surveillance of Safety-Related Hydraulic Snubbers

{{Adams
| number = ML18227D861
| issue date = 03/22/1976
| title = 03/22/1976 Letter Request to Amend Appendix a of Facility Operating Licenses. Proposes Technical Specification Changes Relating to Surveillance of Safety-Related Hydraulic Snubbers
| author name = Uhrig R
| author affiliation = Florida Power &amp; Light Co
| addressee name = Stello V
| addressee affiliation = NRC/NRR
| docket = 05000250, 05000251
| license number = DPR-031, DPR-041
| contact person = 
| case reference number = L-76-119
| document type = Letter type:L, License-Application for Facility Operating License (Amend/Renewal) DKT 50
| page count = 7
| project = 
| stage = Other
}}

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NRC FOAM 195                                           U.S. NUCLFAA AEGULATOAYCOMMISSION DOCKET NUMBER I  I2.N)                                                                                           50-2507~
FILE NUMBER NRC DISTRIBLITIQN FDA,          RT gP Po CKET MATERIAL FROM:  FPL                                  DATE OF DOCUMENT Mr. V. Stello                                                                             3-22-76 Miami, Fla.        33101 R.ED Uhrig                            DATE RECEIVED 3-29-76 IZA.ETTE R               0 NOTOR IZE D             PROP                                        NUMBEA OF OOPIES RECEIVED XRDRIGINAL         WUNC LASS IF I E D 0 COPY                                                                                       3  Orig  & 37 CC I DEscRIPTIDN    Ltr requesting    or    am t to           PP      ENcI.osURE     Revised & addi pages to Proposed Chan e j       of  OL/DPR-31 & DPR-41    related to hydraulic                     P'6 re to hydraulic snubbers...
snubbers & traas the     following:
(40 cys encl  rec'd)
! PLA?Q NAYE          Turkey Pt. Units       3 & 4 SAFETY                                FOR ACTION/INFORMATION                 ENVIRO      D  , 3>>30-76 ASSXGNED AD                                                        ASSIGNED AD .
BRANCH CHXEF:                                                      BRANCH CHXEF :
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* BENAROYA                      ALLARD SPANGLER GOSSICK & STAFF               ENGIIiEER N                      IPPOLITO SITE TECH A F.                         KNIGHT                           OPERATING REACTORS           GAiMMXLL N                          SIHIKXL                          STELLO                       STEPP PAWLICKI OPERATING TECH PROJECT MANAGEMENT            REACTOR SAFETY                   EXSEiiHUT                    SITE ANALYSIS BOYD                          ROSS                             SHAO                        VOLLtIER P, COLLINS                    NOVAK                            BAER HOUSTON                       ROSZTOCZY                        SCHICENCER                  J    COLLINS PETERSON                      CHECK                            GRIMES                      KREGER MELTZ HELTEiMES                     AT &    I                        SITE. SAFETY & ENV   R SKOVHOLT                      SALTZMAN                         ANALYSIS RUTBERG                          DENTON & HULLER EXTERNAL DISTRIBUTION                                            CONTROL NUI'slBER LPDR. Miamx.      a.          NATL      YB                     BROOKHAVEN NATL LAB TIC                           REGS V-IE                       ULRIKSON (OIt&#xc3;L)
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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 specification. 3.12 is added to define the ditions for operation applied to the operability limiting A new                                                         con-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, flexibility in 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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