View source for L-78-233, 07/11/1978 Letter Request to Amend Appendix a of Facility Operating Licenses

{{Adams
| number = ML18227D803
| issue date = 07/11/1978
| title = 07/11/1978 Letter Request to Amend Appendix a of Facility Operating Licenses
| 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-78-233
| document type = Legal-Affidavit, Letter type:L, License-Application for Facility Operating License (Amend/Renewal) DKT 50
| page count = 7
}}

=Text=
{{#Wiki_filter:REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)
DISTRIBUTION FOR INCOMING MATERIAL                                                               50-25  ~ ~~  g REC:      STELLO V                                       ORG:     UHRIG R E                                     DOCDATE:   07/ll/78 NRC                                                     FL    PWR 4 LIGHT                                   DATE RCVD:   07/17/78 DOCTYPE:          LETTER             NQTAR     IZED: YES                                                          COPIES RECEIVED

==SUBJECT:==
LTR 3     ENCL 40 AMEND.        TQ LIC. NOS. DPR-31 h DPR-41 CONSISTING OF PROPOSED CHANGES TQ APPENDI:X A TECI-I. SPECS. CONCERNING USE 5 SURVEILLANCE OF MOTOR OPERATED VALVES... NOTARIZED 07/11/78.
,
PLANT NANE: TURI EY PT C. 4-
  ~~~~~~~~~.~~~~'-~;-~~~~            DISTRIBUTION OF TI-IIS MATERIAL IS AS FOI REVIEWER  INITIAL: XEF DISTRIBUTOR COWS INITIAL: ~
                                                                                                                  ~~~~~~~~~~~~~~~~~~
GENERAL DISTRIBUTION FOR AFTER ISSUANCE OF OPERATING LICENSE.
(DISTRIBUTION              CODE A001>
FQR ACTION:                    BR,   CHIEF ORB51 BC++W/7 ENCL INTERNAL:                    ~REG      FILB++W/ENCL                                           NRC PDR4+W/ENCL I~% E+4W/2 ENCL                                                QELD44LTR ONLY IHANAUER++W/ENCL                                               CORE PERFORMANCE BR++W/ENCL AD FOR SYS S. PROJ++4I/ENCL                                    ENGINEERING BR<+4/ENCL REACTOR SAFETY BR++W/ENCL                                      PLANT SYSTEMS BR++W/ENCL EEB~~W/ENCL                                                    EFFLUENT TREAT SYS++W/ENCL J. MCGOUGH++W/ENCL EXTERNAL:                      LPDR S MIAMIr FL++W/ENCL TERA++W/ENCL NSI C++W/ENCL ACRS        CAT B44W/16 ENCL
  $ $ $ $ $ $ $ $ f$ $ $ $ $ $ $ $ $ $ $ $ $ $ $ $ $ $ $ $ $ @$ $ $ $ $ $ $ $ $ $ $ $ $ $ $ $ $ $ $ $
  $ CHECK NBR: 63s 590 AMOUNr:              $ n, 000. OO                                                           $
  $ CHECK AND COPY OF TRANSMITTAL LTR ADVANCED                                                      $
  $ TQ 4l. MILLER (LFMB) (07/18/78) UPON RECIEPT
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  $ $ $ $ $ $ $ $ $ $ $ $ %$ $ $ $ $ $ $ $ $ $ $ %$ $ 4$ $ $ $ $ $ $ $ $ $ $ $ $ $ $ $$ %$ $ $ $ $
DI - TRIBUTIQN:                 LTR RO             ENCL 39                                              CONTROL NBR:    781990298 8 I ZE: 2P+2P+1P

FLORIDA POWER 5 LIGHT COMPANY July  ll, 1978 L-78-233 Director of Nuclear Reactor Regulation Attention: Mr. Victor Stello, Director Division of Operating Reactors U. S. Nuclear Regulatory Commission Washington, D. C. 20555

==Dear Mr. Stello:==

Re:   Turkey Point Units 3 and 4 Docket Nos. 50-250 and 50-251 Proposed Amendment      to Facility 0  eratin    Licenses   DPR-31   and DPR-41 At the request of the Commission, and in accordance with 10 CFR 50.30, Florida Power 8 Light Company submits herewith three (3) signed originals and forty (40) copies of a request to amend Appendix A of Facility Operating Licenses    DPR-31  and DPR-41.
The proposed    amendment   is described below       and shown on the accompanying Technical Specification       page bearing the date of this letter in the lower right   hand  corner.
Pa  e  3.4-2 Technical Specification 3.4.1.a.7 is revised to include motor operated valves 863-A and 863-B. These valves are installed in parallel and provide a crosstie from the discharge of the RHR pumps to the SI system.          The valves are closed during normal operation and       remain   closed   upon initial ECCS actuation.
To preclude spurious       actuation    during the ECCS injection phase, the valves will have power        removed   from their motor operators by locking open the circuit         breakers    in the appropriate motor control centers. Power will         be  restored   to the valve operators to accomplish the switchover from         the   ECCS  injection mode to the recirculation    mode.
Pa e  3.4-3 Technical Specification 3.4.1.b.7 is added to permit periodic survei llance of the valves specified in 3.4.1.a.7.
The proposed    amendment has been reviewed by the Turkey Point Plant Nuclear Safety Committee and the Florida Power 8 Light Company Nuclear Review Board.
They have concluded that       it  does not involve an unreviewed safety question.
                                                            >82 9yo.~~~
                                                                     ~r  ~
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Director of Nuclear Reactor Regulation                   July 11, 1978 Page Two                                                 L-78-233 In accordance with the criteria stated in 10 CFR 170.22, FPL has determined that this is a CLASS III amendment. A check in the amount of $ 4,000 to cover the requisite amendment fee is enclosed.
Very t      yours, Robert E. Uhrig Vice President REU/MAS/cpc Enclosures cc:  Mr. James P. O'Reilly, Region  II Robert Lowenstein, Esquire
* W,

C
: 5. TIPO residual  hea   emoval pumps  shall be operable.
: 6. TWO  residual heat exchangers shall   be opexabla.
I
: 7. All valves, interlocks   and  piping associated with the above components   and required for post accident operation, shall be   operable, exce'pt valves that
          ,.are positioned and locked. Valves 862-A&B; 863-A&B; 864-A&B; 865-A,B&C; 866-A&B sha11 have power removed from their motor operators by locking open the circuit breakers at the Motor Control Centers. The air supply to valve 758 shall be shut off to the valve operator.
: b. During power operation, the requirements of       3.4.la may be    modified to allow one of the following com-ponents to be inoperable (including associated valves and piping) at any one time except for the cases staLed in 3.4.1 b.2. If the system is not restored to meat the requirements of 3.4.la within the time period specified; the xeactor,shall be placed in the hot        .
shutdown condition. If the requirements of 3.4.la are not satisfied within an additional 48 hours the reactor shall 'be placed in the cold shutdown condition.
l.,   ONE   accumulator may ba out of service  for  a period of up to 4 hours.
: 2. ONE   of FOUR safety injection pumps may be out
         - of service for 30 days. A second safety in-jection pump may be out of service, provided the pump is restored to opexable status within 24 hours. TWO of the FOUR safety injection pumps shall be 'tested to demonstraLe operability before initiating maintenance of tha inoperable pumps.
: 3. ONE   channel of heat tracing on the flow path may be out of service for 24 hours.
3.4-2
: 5. ONE  residual heat exchanger may be out of
               - service   for a pe d of 24 hours.
6     Any  valve in the system may be inoperablc pro-I vided repairs are completed within 24 hours.
I Prior to initiating maintenance, all valves that provide the duplicate function shall be tested to demonstrate operability
: 7. To  facilitate surveillance of valve operability, the valves specified in 3.4.l.a.7 may be unlocked and may have supplied air or electric power restored for a period not to exceed 24 hours.
.2    RKRGENCY CONTAXh~LKNT COOLXNG SYSTEHS h
a   &e reactor shall not bc made critical~ except for low power physics tests, u. less the f'ollowing conditions arc met:
: 3. THREE emergency    containment cooling  unit are operable.
: 2. Tt;0 containment spray pumps    arc F
op  rable-All valves   and  piPing associated with the'bove com-ponent , and required for post accident operation, wrc operablc.
     'b'uring       po~er operation, thc requirements     of
           &.4.2a may be modified to allow one of the Xollowing components to be inoperable (in-eluding associated valves'and piping) at any one time. Xf the system is not restored'to meet the requirements of 3.4-2a within the time period pecificd, thc reactor shall b' placed in the hot shutdown condition. Xf the requirements of 3 4.2a arc not satisfied l
Tpithin an add i tio::a 48 hour.. the reactor shall bc placed in'he cold shutdown condit9.os.
Q.4-3

STATE OF FLORIDA     )
                     )        ss COUNTY OF DADE       )
Robert E. Uhrig, being    first      duly sworn, deposes                 and says That he is a Vice President of Florida Power                         G Light Company the Licensee herein; That he has executed the foregoing document; that the state ments made in this said 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.
r n~
Robert'.            Uhdig Subscribed and sworn to before          me    this
~/day        of NOTA    PUBLIC, xn an    for the       Co   nty of Dade, State of Florida tlCT RY pUSUC STAT- Cp FLQMCA at   LASCAR Ny commission   expires:   sctlcQ)  Tt&J ltAYllA"c sc"cll'4 4}}