ML18088B264
| ML18088B264 | |
| Person / Time | |
|---|---|
| Site: | Saint Lucie  |
| Issue date: | 03/20/1978 |
| From: | Robert E. Uhrig Florida Power & Light Co |
| To: | Stello V Office of Nuclear Reactor Regulation |
| References | |
| L-78-87 | |
| Download: ML18088B264 (17) | |
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REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS>
DISTRIBUTION FOR INCOMING MATERIAL 50-335 REC:
STELLO V NRC ORG:
UHRIG R E FL PWR
- 8. LIGHT DOCDATE: 03/10/78 DATE RCVD: 03/+0/78 DOCTYPE:
LETTER NOTARIZED:
YES COPIES RECEIVED
SUBJECT:
LTR 3 ENCL 40 LICENSE NO DPR-67 APPL FOR AMEND:
TECH SPECS PROPOSED CHANGE CONCERNING REPLACEMENT OF SELFCTED SAFETY-RELATED HYDRAULIC SNUBBERS WITH MECHANICAL SNUBBERS DURING THE UPCOMING REFUELING OUTAGE... W/ATT SAFETY EVALUATION.
PLANT NAME: ST LUCIE 81 REVIEWER INITIAL:
XJM DISTRIBUTOR INITIAL:
+++++++++++++++++ DISTRIBUTION OF THIS MATERIAL IS AS FOLLOWS GENERAL DISTRIBUTION FOR AFTER ISSUANCE OF OPERATING LICENSE.
(DISTRIBUTION CODE A001)
FOR ACTION:
BR C
>W/7 ENCL INTERNAL:
EXTERNAL:
REG FI
/ENCL HANAUER++W/ENCL EISENHUT+~W/ENCL BAER~~lW/ENCL GR IMES+4W/ENCL J.
MCGOUGH~~4 W/ENCL LPDRiS FT PIERCE< FL++W/ENCL TIC+~~W/ENCL NS IC+81 W/ENCL ACRS CAT B++W/16 ENCL NRC PDR44W/ENCL OELD++LTR ONLY CHECK++W/ENCL SHAO++W/ENCL BUTLER44W/ENCL J COLLINS++W/ENCL DISTRIBUTION:
LTR 40 ENCL 39 SIZE:
2P+6P+5P CONTROL NBR:
7807900@
THE END
%%4%%4 %%0l%%%%%%%%4%%%%%%%%%
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FLORIDAPOWER & LIGHTCOMPANY March 10, 1978 L-78-87 Director of Nuclear Reactor Regulation Attention:
Mr. Victor Stello, Director Division of Operating Reactors U.S. Nuclear Regulatory Commission Washington, D. C.
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Dear Mr. Stello:
Re:
St. Lucie Unit 1 Docket No. 50-335 Proposed Amendment to Facilit 0 eratin License DPR-67 In accordance with 10 CFR 50.30, Florida Power and Light Company submits herewith three (3) signed originals and forty (40) copies of a request to amend Appendix A of Facility Operating License DPR-67.
The purpose of this amendment is to support the replacement of selected safety-related hydraulic snubbers with mechanical snubbers during the upcoming refueling outage.
This proposal essentially modifies a request made in a previous proposal.
Our. letter L-76-207 of May 20, 1976 proposed, in part, that changes to Table 3.7-2 be permitted without prior license amendment provided that the conditions of 10 CFR 50.59 be met and the Table be revised by a future amendment.
The May 20, 1976 proposal, which was intended to support hydraulic snubber replacement during the refueling outage, has been the subject of several discussions with the Commission Staff during recent weeks.
The Staff, however, has declined to authorize changes to Table 3.7-2 without prior approval.
Therefore, in order to support the planned replacement of several of the smaller sized hydraulic snubbers with mechanical
- snubbers, we have prepared the present request.
Timely Staff review is requested so that we can implement the proposed changes during the first refueling outage which is scheduled to begin about April 1, 1978.
The proposed Technical Specification changes are described below and shown on the accompanying Technical Specification pages bearing the date of this letter in the lower right hand corner.
'I78079003-goo/ s 3
PEO E... SERVING PEOPLE
Pa es 3/4 7-32 throu h 3/4 7-37 41 entries are deleted from Table 3.7-2 (SAFETY RELATED HYDRAULIC SNUBBERS).
These hydraulic snubbers are scheduled to be replaced with equivalent or better mechanical snubbers during the first refueling outage.
All operating parts in mechanical snubbers are metallic and positive acting.
Replacement of the hydraulic snubbers proposed with mechanical snubbers would represent an improvement over hydraulic snubbers which can experience seal failure and loss of hydraulic fluid.
Use of mechanical snubbers is expected to result in reduced maintenance and to minimize possible
- downtime, thereby resulting in cost savings to our customers.
The proposed amendment has been reviewed by the St. Lucie Facility Review Group and the Florida Power 6 Light Company Nuclear Review Board.
They have concluded that it does not involve an unreviewed safety question.'
safety evaluation is attached.
Very truly yours, Robert E. Uhrig Vice President REU/MAS/sl Attachment cc:
Mr. James P. O'Reilly, Region II Harold F. Reis, Esquire
. 'rADLE 3.7-2.'.
SAFETY RELATED t)YDRAULIC SHUDDERS+
PPL LOCATION NUH13HR MA/K NE4llER SYSTEt< SNUDDCR IHSTAL1.EO OH LOCATION AND ELEVATION ACCESS IDLE OR HIGH RADIATION ESPECIALLY DIFFICULT.
IHACCESSIDLE ZONE TO REt~OVE 017 018 019 020 1Al lA2 1D1 lD2 I
RC, RCP Motor.lhl, Elev.
57'C, RCP Notor 1A2, Elev.
67'C, RCP l<otor 1D1, Elev.
57'C; RCP.t",otor 1D2, Elev. 57'or I
I I
Yes or o
Ho Ho Ho es or Ho Ho Ho.
Ho Ho C)
TABLE 3.7>>2
'AFETY RELATED HYDRAULIC SHUDDERS*
FPY MCATYOM NUMBER 033 034 035 036 037 038 039 040 041
- 042, 043 044 MARK MtB(HER
, SYSTEft SNUBBER INSTALLED OH, LOCATION AHD ELENTIOH r
O2i 55 i'
'5'0'O'O'0'oi no'O'S 6n9-319 tlS, Reactor Bldg, Elev.
HS 5n0-5 HS, Reactor Bldg, =Elev.
tlS 1076-3164 tlS, fd.S. Trestle, Elev.
l<S 6n9-314 t<S, Reactor D'ldg. Elev.
tlS 6n9-31n NS, Reactor Bldg, Elev.
llS. 6n9-310 HS, Reactor Bldg,'l ev.
'Ms 649-304A HS, Reactor Dldg, Elev.
tlS 5n0-9 tlS, Reactor Bldg, Elev.-
HS 5n0-9 HS, Reactor Bldg, Elev.
DF 5ng-7 ol-, Reactor Bldg, Elev.
OF 5n9-7 DF, ReaCtor Bldg, EleV.
DF 5<9-0 DF, Reactor Dldg, Elev.
Yes or Ho Ho t(0 ~
Ho No t)o Ho Yes Yes Yes Ho
~
Ho Yes A or I A
A es. or 0
. No No No No Ho Ho Ho Ho Ho Ho Ho Ho
.I I
ACCESSIBLE OR HIGH RADIATION ESPECIALLY DIFFICU INACCESSI DLE ZONE TO REt'CROYE 047-OF 5n9-17' OF, Reactor Bldg,.Elev.36'es 4
TABLE 3.7-2 SAFETY RELATED HYDRAULIC SNUBBERS*
PPL LOCATION NRSL'R MARK NUMBER
. SYSTEM SNUBBER INSTALLED ACCESSIBLE OR 'IGH RADIATION ESPECIALLY DIFFICULT ON LOCATION AND ELEYATION INACCESSIBLE 'ONE TO REt~iOYE
. (ii or I); "
Yes ar Ha Yas ar Ho
/,
~
'\\
052 053 DP 549-17 SI 960-210 OF, Reactor Bldg, Elev; 36':.
SI, Reactor Bldg, Elev;16'oNo No Nn 058 SI 969-1216'I, Reactor Bldg,.Elev. 10';
061 MS 549-11 SI, Reactor Bldg, Elev.10'lp Na
~
066 Ms 549-11 Sl, Reactor Bldg,'lev.20'o No
c')
Vi g
~
~'e t
TROLE 3.7-2 ShrETY AELRTEO ttYOARULIC SHuOOFAS*
1'PL LOCATION hl.'YilltR
'ARK NUviBP.R SYSTEN SHUOtIEA IHSTALLED 0"'OCATIOt< RHD ELEIthfIOltt hCCESSIOLE OR HIG}t RADIATION hSPECIRLLY DIF;.
rrtRCCt:.SSIOLE l0ÃC 70 AEtS'l6 tA or I)
Yos or Ho
~io".or i,'~o I
Vl 073 07ci 076'77 SI 9)2-6210 SI, Reactor OIdg, Elev.
16'I 973-250 SI, Reactor Olde, Elev.
10'I 973-622ik" SI, Reactor Oldg, E1ev, 1G'l 068-65 SI, ARO, E1ev. 0'.
R h
No No No
,",o-tto f)u CD CO 080 081 082083'I 060-)6i SI 060-910 SI 676<<67 SI 676-67 St 6)6-105 SI, ARO, El ev.
4'I, ARO, Elev.
5'I, ARO, Elev.
5'I, ARO,'/ev.
4'I, Ah0, Elev. 5'
~ A R
ho tlo ho t'>o No tto Ro iso tip
TABLE 3.7-2 SAFETY AELATED HYDAAULIC SHUDDERS*
FPL LOCATION NLRB ER 084 S I 676-105 SYSTEYi SNUBBER INSTALLED
~ ON LOCATION nHO ELEVATION SI, RAD, Elev. 4',
ACCESSIBLE OR HIGH.RADIATION INACCESSIBLE ZONE A or I' Yes or Ho A., 'o ESPECIALLY DIFFICULT TO REhlOVE
~
Yes or Ho Ho 090 SPS-27 092 093 SPS 467 SPS-777 086 SI 676-129 087
~
SI 676-2481 110
.'I 971-6236 114
SI, AAD, Elev.
24'I, AAD, Elev.
30'I, AAD, Elev.
30'I, AAD, Elev. 7' SI, AAD, Elev.
0'I.
AAD, Elev.
4'ressurizer
- Spray, Reactor Bldg, Elev, 60'ressurizer
- Spray, Reactor Bldg, E'-ev 50
.Pressurizer
- Spray, Reactor Bldg, Elev.
OO'
'ress'urizcr Spray-, Reactor Bldg, Elev. 00' A
A Ho No Ho Ho No No No Ho Ho No Ho Ho No Ho Ho
'Ho Ho
~
Ho No
TABLE 3.7-2 SAFETY RELATEO tn'ORAuLIC SNUOOERS+
ppr. Mehvrov NUHDPR SYSTEt t SHUOOEA INSTALLED ACCESSIOLE OR, HIGtt RADIATION OH, LOCATION AHO ELEVATIOH IHACCESSIOLE ZONE g or Ij es Qv o
ESPECIALLY DIFFICULT TO AEt<OVE t'es or Ho 096 0Se 089-CC-1065-9 CC, Reactor Oldg, Elev. 25' CC-1099-48
.'C, Reactor Oldg, Elev.
25'C-1052-6241 CC> Reactor Bldg, Elev. 25'.
Ho
.Ho No tto Ho'o 101 102 i
c 4P 10~i 103 105 106 CC>>17-1 MS-649-313 CC-21-1 m-Sii9-7 CC-23 2
Ctf-3-40 CC, RAO, Elev.
20C, RAO, Elev,.
26'CC, RAO, Elev. 20' CC, RAO, Elev. 26
CC, RAO, Elev.
26'lt, RAD, Elev. 34' 1
- A No No tlo Ho Ho Ho No Ho Ho Ho Ho No
~
107 Clt-3-2.5 Yt CH, RAO, Elev, 23'
.,No f
~ i No
V SAFETY EVALUATION Re:
St. Lucie Unit 1 Docket No. 50-335 Snubbers I.
Introduction This evaluation supports a proposed change to Table 3.7-2 (SAFETY RELATED HYDRAULIC SNUBBERS).
A number of snubbers on F
the list are deleted because they are scheduled to be re-placed by mechanical snubbers during the first refueling outage (Spring 1978).
Only smaller snubbers of the 3 kip (3000 inch-pounds) and 10 kip size will be affected by the changeover (see attached list).
II.
Evaluation The snubbers in question are used for seismic restraint That is, they should accommodate pipe movement caused by slow thermal expansion, but they should "lock-up" to prevent potentially damaging transient movement during a postulated seismic event of sufficient magnitude.
The Pacific Scientific (PSA) mechanical snubbers which we propose to use operate on an "acceleration limiting" basis.
PSA snubbers permit thermal movement since the acceleration associated with thermal movement is very low, but they limit seismic induced acceleration to 0.02g in either direction.
Mechanical snubbers would actually allow less to movement than hydraulic snubbers
-under seismic
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conditions because of hydraulic snubber lockup delays associated with achieving the lockup velocity, activation of the lockup mechanism, and compression of the hydraulic fluid.
Therefore, based on seismic functional requirements, the planned replacement of hydraulic snubbers with mechanical snubbers would be an improvement.
Pacific Scientific performed extensive testing in developing the PSA 3
(3.kip) and PSA 10 mechanical snubbers.
The purpose was to evaluate their operability under the adverse conditions expected in.many applications, such as high humidity, high temperature, and vibration.
The snubbers operated favorably under all test conditions.
PSA 3 and PSA 10 mechanical snubbers are currently in use at Turkey Point Units 3 and 4 and at other reactor sites.
To our knowledge there have been no malfunctions of these A
snubbers in operating plants.
- Also, a PSA 3 snubber from each Turkey Point nuclear unit was removed for inspection and testing after 1 year of service.
Both snubbers were
'from the containment environment.
The inspection and test results showed that the snubbers were performing properly and had not degraded operating conditions.
III.
Conclusions Based on testing and operating experience, the use of PSA mechanical snubbers should improve the operability of the
seismic support system.
In conclusion, (l) the proposed change does not increase the probability or consequences of accidents or malfunctions of equipment important to safety and does not reduce the margin of safety as defined in the basis for any technical specification, therefore, the change does not involve a significant hazards consideration>
(2) there is reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed
- manner, and (3) such activities will be conducted in compliance with the Commission's regulations and the issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public.
Snubber Chan cput (PSL)
The following hydraulic snubbers are scheduled to be replaced by mechanical snubbers during the Spring 1978 refueling outage:
3 kip Size 10 kip Size Tag No.
Mark No.
Tag No.
Mark No.
021 022 025 026 027 029 030 031 032 054 055 056 059 060 062 067 071 094 095 RC 005-34A RC 005-34B RC 005-12B RC 005-12B RC 005-55B RC 005-62A RC 005-89 RC 005-90 RC 005-98 SI 968-565 SI 968-1205 SI 968-1207 SI 969-6193 SI 969-6195 SI 969-6201 SI 970-1251 SI 971-6236 CS 832-118 CS 878-115 023 024 028 045 046 048 049 050 051 057 063 064 065'68 069 070 072 075 078 085 098
'00
'C 005-36 RC 005-12A RC 005-55C BF 549-11 BF 549-11 BF 661-407 BF 661-407 BF 661-416 BF 661-416'I 969-1190 SI 969-6217 SI 969-6217 SI 970-1210 SI 971'-6 SI 971-1229 SI 971-6229 SI 972-1243 SI 973-6219 SI 868-111 SI 676-127 CC 1899-2208 CC 1865-2207
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STATE OF FLORIDA
)
)
COUNTY OF DADE
)
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 19~V cevo1su A4QiCY NOTARY PUBLIC, in nd f r the County of Dade, State of Florida NOTARY PQQgg 8ygyg gg My commission expires:
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