ML18029A229
| ML18029A229 | |
| Person / Time | |
|---|---|
| Site: | Browns Ferry  |
| Issue date: | 10/19/1984 |
| From: | Mills L TENNESSEE VALLEY AUTHORITY |
| To: | Harold Denton Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 8411020409 | |
| Download: ML18029A229 (11) | |
Text
REEULATORYOIFORMATION OISTRISUTION SALEM (RIOS)
ACCESSION NBR:8411020409 DOC ~ DATE$ 84/10/19 NOTARIZED$,NO DOCKET ¹ FACIL:50 259 Br owns Ferry Nuclear Power Stat)one Unit 1t Tennessee 05000259 50-260 Browns Ferry Nuclear Power Stations Un)t 2, Tennessee 05000260 50-296 Browns Ferry Nuclear Power Stations Unit 3> Tennessee 05000296 AUTH'AME AUTHOR AFFILIATION MILL'Sg L, H.
Tennessee'alley Authority RECIP ~ NAME RECIPIENT AFFILIATION DENTON,H.R.
Office-. of Nuclear Reactor Regulationi Director.
SUBJECT:
Forwards request for exemption from functional test requirements of Tech Spec 4 HAH for torus restraint snubbers.
DescriptionrJustification L safety evaluation for request encl'pproval requested by 850119, DISTRIBUTION CODE:
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TENNESSEE VALLEYAUTHORITY CHATTANOOGA. TENNESSEE 37401 400 Chestnut Street Tower II October 19, 1984 Mr. Harold R. Denton, Director Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, D.C. 20555
Dear Mr. Denton:
In the Matter of the Tennessee Valley Authority Docket Nos. 50-259 50-260 50-296 Pursuant to the provisions of Browns Ferry technical specification 4.6.H.9, we are hereby submitting a request for exemption from snubber testing for the Browns Ferry Nuclear Plant.
Specifically, we are requesting exemption from the functional test requirements of technical specification 4.6.H for the Torus Restraint Snubbers installed at Br owns Ferry as part of the Mark I Containment Long-Term Program modifications.
Description, justification, and safety evaluation for the exemption request is enclosed.
This exemption is needed in time to avoid the testing on Browns Ferry unit 2 during the current cycle 5 refueling outage.
Therefore, approval is needed by January 15, 1985.
If you need additional information to process and approve this exemption
- request, please inform us by November 15, 1984.
Please get in touch with us through the Browns Ferry Project Manager.
Very tr uly yours, TENNESSEE VALLEY AUTHORITY L. M. Mills, Ma ager Nuclear Licensing Subscribe sworn to for me t is day of 1984.
Notar y Public My Commission Expires Enclosure cc:
See page 2
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Mr. Harold R. Denton October 19, 1984 cc (Enclosure):
U.S. Nuclear Regulatory Commission Region ZI ATTN:
James P. O'Reilly, Regional Administrator 101 Marietta Street, NW, Suite 2900 Atlanta, Georgia 30323 Mr. R. J. Clark Browns Ferry Project Manager U.S. Nuclear Regulatory Commission 7920 Norfolk Avenue
- Bethesda, Maryland 20814
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ENCLOSURE REQUEST FOR EXEMPTION FROM SNUBBER TESTING BROWNS FERRY NUCLEAR PLANT I!
Browns Ferry Technical Specification 4.6.H.9 allows for exemption from snubber testing requirements of Section 4.6.H if granted by The Commission.
Torus Restraint Snubbers (TRS) have been installed at Browns Ferry Nuclear (BFN) Plant as part of NUREG 0661 (Mark I Containment Long-Term.Program)
'and mush be included for testing under Technical Specification 4.6.H.
The TRS are 16 large hydraulic snubbers, fully qualified for the life of the plant, which connect the torus structure to the reactor building structure.
They are installed to accommodate worst case loss of coolant accident loads and are not required for seismic loads.
us f mt'er Technical Specification 4.6.H.9, we request exemption of the TRS from the functional testing requirements and criteria as currently stated in Sections 4.6.H.4 and 4.6.H.5.
Just'ficat'o The TRS are large snubbers which are designed to operate for the life of the plant and are not designed to have removable attachment pins.
Therefore, it is possible that the interference fit of the pins could be adversely-affected by periodic removal and replacement causing attendant reductions in the dynamic spring rate.
Furthermore, the large size of the TRS creates transportation and rigging problems between the installation and testing locations.
BFN does not presently have a machine with the capacity needed to test the TRS.
Overall, there is a great deal of expense involved in TRS testing which is not warranted due to the design and initial testing.
S fet lu t'he exemption of the TRS from functional testing is justified based on qualification testing performed on a prototype before installation of the production TRS in the units.
The tests were defined by TVA's Engineering Design organization to conservatively envelop the accumulative TRS actuations and the range of service conditions anticipated throughout their service life in the units.
The following is a summary of the significant parameters of the qualification test.
84'
BROMNS FERRY UNITS 1, 2, AND 3
SUMMARY
OF QUALIFICATION TESTS ON PROTOTYPE TRS lL~*l.'
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. '213 140 213 133 7,090 + 60 7,370 ~ 140 7,030 ~ 70 7,550 + 120 95 F Ambient 95 F Ambient 20 60 25 250 25 75
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'53 7>270 x 70 7,560 ~ 130 7,020 + 70 8,090 + 350 95 F Ambient 95 F Ambient 30 30 35 35 90 52 300 '3 350 52 105 55 58 53 57 55 7,300 + 280 7,480 + 300 7,490 + 290 7,170 + 270 95F 1
Ambient Ambj,ent 95>
40 40 45 45 400 120 450 135 53 57 53 52 52 55 58 57 7~930 a 340 6,890 + 260 7,880 + 310 7,340 + 280 Ambient 95 F Ambient 95"F 50 500 60 50 150 52 50 103,100 5
Mith 3,224 lb static side load 50 48 5
7,490 + 290 6,980 + 290 Not Calculated Ambient 95 F Ambient At the conclusion of the qualification test, the prototype TRS was func-tionally tested, and no significant change from prequalification measurements of drag force, lockup, and bleed velocity was observed.
The post-qualification bleed rate test was conducted at 130,000-pound load in compression and 90,000-pound load in tension.
The prototype was subse-
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quently disassembled and the seals and internal parts visually examined for damage.
No damage or significant wear of parts was observed during that examination.
Based on this testing, a fatigue usage factor of less than.4 was calculated for 40 years of normal operation followed by a worst-case l,oc~.
The justification for the exemption-is also based on the'consideration that the TRS utilize "life in plant" seal materials.
-.The dynamic seals are machined from. Dupont Tefzel and are. energized by mechanical means and internal pressure.
The static seals are either Tefzel or metallic self/
internal pressure energized C-or 0-rings.
Tests and some operational data collected to date confirm that these seal materials are stable over extended periods and are not subject to unacceptable degradation caused by radiation exposure, extrusion, chemical decomposition, or temperature in this application.
Furthermore, the TRS are in accessible locations, permitting any seal leakage to be monitored.
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