L-78-233, 07/11/1978 Letter Request to Amend Appendix a of Facility Operating Licenses: Difference between revisions

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==SUBJECT:==
==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.
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.
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PLANT NANE: TURI EY PT C. 4-
PLANT NANE: TURI EY PT C. 4-
   ~~~~~~~~~.~~~~'-~;-~~~~            DISTRIBUTION OF TI-IIS MATERIAL IS AS FOI REVIEWER  INITIAL: XEF DISTRIBUTOR COWS INITIAL: ~
   ~~~~~~~~~.~~~~'-~;-~~~~            DISTRIBUTION OF TI-IIS MATERIAL IS AS FOI REVIEWER  INITIAL: XEF DISTRIBUTOR COWS INITIAL: ~
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   $ CHECK NBR: 63s 590 AMOUNr:              $ n, 000. OO                                                          $
   $ CHECK NBR: 63s 590 AMOUNr:              $ n, 000. OO                                                          $
   $ CHECK AND COPY OF TRANSMITTAL LTR ADVANCED                                                      $
   $ CHECK AND COPY OF TRANSMITTAL LTR ADVANCED                                                      $
   $ TQ 4l. MILLER (LFMB) (07/18/78) UPON RECIEPT
   $ TQ 4l. MILLER (LFMB) (07/18/78) UPON RECIEPT f
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   $ $ $ $ $ $ $ $ $ $ $ $ %$ $ $ $ $ $ $ $ $ $ $ %$ $ 4$ $ $ $ $ $ $ $ $ $ $ $ $ $ $ $$ %$ $ $ $ $
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DI - TRIBUTIQN:                LTR RO            ENCL 39                                              CONTROL NBR:    781990298 8 I ZE: 2P+2P+1P
DI - TRIBUTIQN:                LTR RO            ENCL 39                                              CONTROL NBR:    781990298 8 I ZE: 2P+2P+1P
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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.
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
Very t      yours, Robert E. Uhrig Vice President REU/MAS/cpc Enclosures cc:  Mr. James P. O'Reilly, Region  II Robert Lowenstein, Esquire
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Latest revision as of 19:16, 2 February 2020

07/11/1978 Letter Request to Amend Appendix a of Facility Operating Licenses
ML18227D803
Person / Time
Site: Turkey Point  NextEra Energy icon.png
Issue date: 07/11/1978
From: Robert E. Uhrig
Florida Power & Light Co
To: Stello V
Office of Nuclear Reactor Regulation
References
L-78-233
Download: ML18227D803 (7)


Text

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 f

$ $ $ $ $ $ $ $ $ $ $ $ %$ $ $ $ $ $ $ $ $ $ $ %$ $ 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.~~~

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Pi

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

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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 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> 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 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.

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 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. 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 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

3.4-2

5. ONE residual heat exchanger may be out of

- service for a pe d of 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

6 Any valve in the system may be inoperablc pro-I vided repairs are completed within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

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 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

.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 hour5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />.. 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