L-77-239, Revised Letter Request to Amend Appendix a of Facility Operating Licenses
| ML18227D833 | |
| Person / Time | |
|---|---|
| Site: | Turkey Point  |
| Issue date: | 07/27/1977 |
| From: | Robert E. Uhrig Florida Power & Light Co |
| To: | Stello V Office of Nuclear Reactor Regulation |
| References | |
| L-77-239 | |
| Download: ML18227D833 (6) | |
Text
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V.So NUCL,EAR REGULATORV COMMISSION NRC FQRM 195 (2 7d)
NRC DISTRIBUTION FoR PART 50 DOCKET MATERIAL COCKET NUMBER FII E NUMBEA TO:
BT.ETTE R
~OAIQINAL CICOPv DESCRIPTION HNOTORIZEO HuNCLASSIFIEO Mr. Victor Stello PROP INPUT FORM ENCI OSURE FROM:
Florida Power
& Light Company Miami, Florida Robert ED Uhri OATE OF OOCUMENT 7/27/77 OATE RECEIVEO 8/1/77 NUMBEAOF COPIES AECEIVEO III'IIIIlBIEg License No DPR-31
& 41 Appl for Amend:
tech specs proposed change concerning exemption from requirements with respect to the method for leak testing personnel and emergency airlocks after each opening..
notorized 7/29/77
~ ~ ~
PLANT RQK! Turkey Point Units 3 & 4 RJL 8/2/77 (2-P)
(2-P)
FOR ACTION/INFORMATION ENVIRHNHENTAL AGER.
CEN Ii ASS'%STALL!
ASSIGNED AD!
V MOORE LTR BRANCH CHIEF PROJECT MANAGER:
LICENSING ASSISTANT.
Be HARLESS INTERNALDISTRIBUTION
~TFMS SAFETY IMMAN ENGINEERING PLANT SYSTEMS TEDESCO BENAROYA IPPOLITO OPERATING REACTORS SITE SAFETY &
ENVIRON ANALYS1S DENTON & MIJLLER PPTZRO TECH ERNST BALLARD B
D GAMYILL 2
SI'H ANALYSIS VOLLKR TEAN EXTERNALDISTRIBUTION Je COLLINS CONTROL NUMBER IC G IV J
HANCHETT 6 CYS ACRS SENT CATZGO NRC FOAM 19d I2 TSI NSIC 77~1q0271
P. O. SOX 013100, 'MIAMI, FL 33101
- toff, Director of Nuclear Reactor Regulation Attention:
Mr. Victor Stello, Director Division of Operating Reactors U. S. Nuclear Regulatory Commission Washington DC 20555 FLORIOA PGWER & LIGHTCOMPANY July 27, 1977 L-77-239
Dear Mr. Stello:
Re:
Turkey Point Units 3
4 Docket Nos.
50-250 and 50-251 Proposed Amendment to Facility 0 eratin Licenses DPR-31 and DPR-41 Our'letter of May 2, 1977, (L-77-134) requested that Appendix A of Operating Licenses
.DPR-31 and DPR-41 be amended..
This letter supersedes our previous request.
On February 28,
- 1977, we received a letter from Mr. George Lear of your staff asking that we revise our request of September 12,
Specifically, we are requesting, pursuant to 10 CFR 50.12, exemption from the requirements of Section III.
B with respect to the method for leak testing personnel and emergency airlocks after each opening.
Section 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, 1975, letter, we plan to use a vacuum test device to 3.eak test the, airlock 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 a Light Company Nuclear Review Board (CNRB) with the following 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 with 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 performed after each opening.
PEOPLE... SERVING PEOPLE
L-77-239 July 27, 1977 Mr. Victor Stello page 2
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 exemption request, we propose to modify our Technical Specifications on airlock leak testing.
The present proposal supplements our previous proposal of September 20, 1974.
Xn accordance with 10 CFR 50.30, 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 'n 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 Speci-fication amendment and have concluded that it does not involve a significant hazards consideration and should not require pre-noticing.
Very truly yours, Robert E. Uhrig Vice President REU:NR:tm Attachment cc:
Norman C. Moseley, Region II Robert Lowenstein, Esquire
4.4.2 LOCAL PENETRATION TESTS Test Procedure and Fre uenc Local leak detection tests of the following compo-nents 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 0
- Within 3 days of every first of a series of openings when containment integrity is re-quired, verify that door seals have not been damaged or seated improperly by vacuum testing the volume between the door seals in accordance with approved plant procedures.
b.
At least once per 6 months, conduct an overall airlock leakage test to verify that the overall 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) each refueling Acce tance Criteria Repairs and tests shall be made whenever the sum of the local leak rate tests, including the isolation valves discussed in 4.4.4, exceeds sixty percent of the total containment allowable leak rate.
4.4.3 REPORT OF TEST RESULTS Each integrated leak rate test will be the subject of a summary technical report, including
- Exemption to Appendix "J" of 10 CFR 50..
In accordance with NRC Staff position.
4.4-2 7/27/77
STATE OF FLORIDA
)
)
COUNTY OF DADE
)
sso Robert E. Uhrig, being first duly sworn, deposes and says:
That he is a Vice President of Florida Power
& Light Company, the Licensee hexein; 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.
I Robert E. Uhrig Subscribed and sworn to before me this day of 19~7 NOTARY PUBLIC, in and for t County o
- Dade, State of Florida egret itkv, 'r.wv. '.~ c."','.,<<,:,.<<,j My commission expires: