ML18227B255
| ML18227B255 | |
| Person / Time | |
|---|---|
| Site: | Turkey Point  |
| Issue date: | 05/02/1977 |
| From: | Robert E. Uhrig Florida Power & Light Co |
| To: | Stello V Office of Nuclear Reactor Regulation |
| References | |
| Download: ML18227B255 (10) | |
Text
NRG FORM 1'-'4
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NRC DISTRIBUTION FoR T 50 DOCKET MATERIAL Fll E NUMBER TO:
Mr-Victor Stello FROM:
Florida Power tk Light Company Miami, Florida Robert ED uhrig
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DATE OF DOCUMENT 5/2/ IZ DATE RECEIVED 5/5/77 gfLETTER goRIGINAI Ocopv DESCRIPTION g NOTORIZED gUNCI.ASSIFIED PROP INPUT FORM ENCI OSURE NUMBER OF COPIES RECEIVED 3
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tIDOÃOX'nrOVE
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~ y Amdt~ to OL/change'o Appendix. A tech specs
~ ~ inotorized 5/2/77. ~ ~with proposal.
to modify tech specs on al,rJ.ock leak testingo
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PLANT 'NAME
'ACKNOWLEI?GE (2-P)
SAFETY ASSIGNED AD:
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0 ECT MANA E L C ASST FOR ACTION11 v-5 NFORMATION r
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PROJECT MANAGER:
LIC ASST G.FILE NRC PDR j&E OELD GOSSICK & STAFF MIPC CASE HARLESS PROJECT MANAGEMENT BOYD P
COLLINS HOUSTON PETERSON MELTZ HELTFMF.S SKOVIIOLT LPDR TIC:
NSIC:
ASLB:
ACRS CYS HOHRRC/
NRC FORM I96 I2 781 INTERNALD
- SYSTEMS'AFETY
'EINEIIAN SCHROEDER ENGINEERING MACARRY BOQNr<K SDNEIL PAWLICK REACTOR SAFE ROSS NOVAK ROSZTOCZY CHECK AT&I SALTZIIAN RUTBFRC EXTERNAL DISTRIBUTION NAT~ IAB REG VOGIE LA PDR CONSULTANTS TASH.
ISTRl BUT)ON PLANT: SYSTEMS' TEDF.SCO 0 A IPPOLITO OPERATING REACTORS STELLO OPERATING TECH EISENHUT BR,O.OgtAYSXBQ,T ULRIKS~OH OR SITE SAFE
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ENVY(
0 ERNST BALLARD SPANGLER SITE TECH GA&IILL STEPP HULMAN SITE hNALYSIS VOLLMER
'BUNCII J ~ COLLINS KREGF.R CONTROL NUMBER
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T7/748 ~++
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P. O. BOX 013100, MIAMI, FL 33101 yitlg
~err ~i FLORIDAPOWER & LIGHTCOMPANY 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:
.a; p
'ctriIff; Re:
Turkey Point Units 3 and 4
Docket Nos.
50-250 and 50-251 Proposed Amendment to Facility 0 erato;.n Licenses DPR-31 and DPR-41 May 2,1977 L-77-134 On February 28, 1977, we received a letter from Mr. George Lear of your staff asking that we revise our request of September 12, 1975 (L-75-437) for exemption from certain requirements of Appendix J to 10CFR50.
Specifically, we are requesting, pursuant to 10CFR50.l2, exemption from the requirements of Section III. B with respect to the method for leak testing personnel and emergency airlocks after each opening.
Sec-tion III. B requires that such tests.
be performed by local pneumatic pressurization at a pressure not less than the postulated peak accident pressure (Pa) inside containment.
However, for reasons described in our September 12 letter, we plan to use a vacuum test device to leak test the air-lock door seals after each opening -in lieu of a positive pressure test of the entire airlock.
This exemption request has been reviewed by the Turkey Point Plant Nuclear Safety Committee (PNSC) and the Florida Power
.6 Light Company Nuclear Review. Board (CNRB) with,the follow-ing conclusions:
1)
The request,for'"exemption,,
as stated
- above, is necessary..
2)
The request appears to conform with guideline 3 in Enclosure 2 to Mr. Lear's letter.
3)
We intend 'to comply wi.th the requirements of Appendix J regarding the frequency -of airlock
'testing.
A Type B test of the entire airlock will be performed at least every 6 months and a
vacuum test of the door seals will be per-formed, after each opening.
z~r~@ ~@9p PEOPLE... SERVING PEOPLE
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4)
One objective of airlock leak testing, as stated in Enclosure 2 to Mr. Lear's letter, is that the "after each opening" test will provide. a means of assuring that the door seals have not been damaged or seated im-properly during airlock use.
The vacuum test will facilitate our accomplishment of this objective.
5)
The vacuum test is an industry approved alternative to a pressure test.
6)
Performance of a door seal vacuum test will not. adversely affect the health and safety or the common defense and security of the public.
As a result of this'xemption request, we propose to modify our Technical Specifications on airlock leak testing.
The present proposal supplements our previous proposal of September 20, 1974.
In accordance with 10CFR50.30, three (3) originals and forty (40) copies of our request to amend Appendix A of Operating Licenses DPR-31 and DPR-41 are attached.
The proposed changes are described below and shown on the accompanying Technical Specification page bearing the date of this letter in the lower right hand corner.
Pa e 4.4-2 Specification 4.4.2.2 is revised to conform with our plans for leak testing airlocks.
The PNSC and CNRB have also reviewed the proposed Technical Specification amendment and have concluded that it does not involve a significant hazards consideration and should not require prenoticing.
Very uly yours, Robert E. Uhrig Vice President REU/MAS/cmp Attachment cc:
Norman C. Moseley, Region II Robert Lowenstein, Esquire
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4.4.2 LOCAL PENETRATION TESTS Test Procedure and Fre'uenc Local leak detection ests of the following components shall be performed at a pressure not less than 50 psig using. pressure
- decay, soap bubble, halogen detection or equivalent methods at the frequency listed, unless =otherwise noted:
1.
Containment purge valves (pressure applied in connecting duct) each refueling.,
2.
Personnel and Emergency Airlocks a.
- Within 3 days of every first of a series of openings when containment integrity is required, ver'fy that. door seals have not been damaged or.seated improperly by vacuum testing the volume between the door seals in accordance with approved.
plant procedu"es.
b.
At least once per 6 months, conduct an overall airlock leakage test to verify that the overa11 airlock leakage rate is within its limit.
3.
Equipment access opening (pressure applied between gaskets) annually and after use.
4.
Fuel transfer tube flange (pressure applied between gaskets) each refueling.
5.
Electrical penetrations (pressure applied to canister) prior to integrated leak tests.
Acce tance Criteria 4.4.3 Repairs and tests sha 1 be made whenever the sum.
of the local leak rate tests, including the isolation valves discussed in 4.4.,4, exceeds sixty per cent of the total containment allowable leak rate.
REPORT OF TEST RESULTS Each integrated leak "ate test will be the subject of a summary technica'eport, including,
- Exemption to Appendix "J" o= 10CFR50.
In accordance with NRC Staf= position.
4.4-2 5/2/77
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STATE OF FLORIDA
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COUNTY OF DADE
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ss Robert E. Uhrig, being first duly sworn, deposes and says:
That he is a Vice President of Florida Power
& 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.
Robert E. Uhrig Subscribed and sworn to before me this day of
, F9~7 NOTARY P BLIC, in and for the County of Dade, State of Florida NOTARY FIIRIIC STATE OF FlORIDA AT I AF NY COMMISS!ON EXPIRES 3AH.
26, 1979 ENDED THRU GENERAL INSURANCE VNOERWR)FELS Ny commission expires:
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