ML20148S603
| ML20148S603 | |
| Person / Time | |
|---|---|
| Site: | Fort Saint Vrain  |
| Issue date: | 04/07/1988 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20148S568 | List: |
| References | |
| NUDOCS 8804190106 | |
| Download: ML20148S603 (2) | |
Text
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UNITED STATES g
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W ASHINGTON, D. C. 20555 i
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SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO.S3TO FACILITY OPERATING LICENSE NO. OPR-34 PUBLIC SERVICE COMPANY OF COLORADO FORT ST. VRAIN NUCLEAR GENERATING STATION DOCKET NO. 50-267
1.0 INTRODUCTION
By letter dated December 23, 1986, Public Service Company of Colorado proposed changes in the technical specifications (TS) of the Fort St.
Vrain Nuclear Generating Station. The changes involve the deletion of the snuhber tables and a clarification of the requirements for performance of an engineering evaluation o'n inoperable snubbers. The licensee's application was made in response to NRC Generic Letter 84-13, "Technical Specifications for Snubbers", dated May 3,1984. These chances are intended to eliminate the need for frequent TS amendments to incorporate changes in the snubber listings. The staM requested additional infoma-tion from the licensee by letter dated October 19, 1987. The licensee provided this additional information by letter dated December 17, 1987.
2.0 EVALUATION The NRC staff indicated in the referenced Generic letter that it had reassessed the inclusion of snubber listings within the TS and concluded that such listings were not necessary provided the snubber TS are r. edified to specify which snubbers are required to be operable. The licensee's requested changes to the TS would delete the tabulat listings of snubbers and add the criteria requirino all snubbers to be operable except those snubbers on non safety-related systems whose failures would have no adverse effects on any safety-related systems.
We have reviewed the current TS together with the proposed changes and compared these changes with the model TS provided in the Generic Letter.
From our review, we find that the proposed changes are administrative in nature and do not authorize any physical changes to the plant's safety-related structures, systems or components. Any physical changes in snubber quantities, types or location would have to be reviewed under the provis'ibns of 10 CFR 50.59 to detemine if an Unreviewed Safety Ouestion exists. Therefore, the proposed changes would not in any way reduce availability of those snubbers which are provided to ensure that the structural integrity of the reactor coolant system and all other safety-related systems is maintained during and following a seismic or other transient events.
Based on the above discussion and the fact that the proposed changes are consistent with guidance provided in the Generic Letter, we have detemined that the proposed changes are acceptable.
8804190106 090407 DR ADOCK 05000267 PDH
3.0 ENVIRONMENTAL CONSIDERATION
The amendment involves a change in the installation or use of a facility component located within the restricted area as defined in 10 CFR Part 20.
The staff has determined that the arendment involves no significant increase in the amounts, and no significant change in the types, of any effluents that may be released offsite, and that there is no significant increase in individual or cumulative occupational radiation exposures.
The Commission has previously issued a proposed finding that the amendment involves no sionificant hazards consideration and there has been no public comment on such finding. Accordingly, the amendment meets the eligibility criteria for categorical exclusion set forth in 10 CFP Section 51.22(c)(9).
Pursuant to 10 CFR 51.22(b), no environnental impact statement or environ-mental assessnent need be prepared in connection with the issuance of the amendment.
4.0 CONCLUSION
The staff has concluded, based on the considerations discussed above, that:
(1) there is reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed manner, and (2) such activities will be conducted in compliance with the Commission's regulations, and the issuance of the amendment will not be inimical to the common defense and security or to the health and safety of the public.
Date: April 7, 1988 Principal Contributors:
M. Hartzman, EMEB/ DEST
- 4 e
April 7,1988 Docket No. 50-267 Mr. R. O. Williams, Jr.
Vice President, Nuclear Operations Public Service Company of Colorado Post Office Box 840 Denver, Colorado 80201-0840
Dear Mr. Williams:
SUBJECT:
FORT ST. VRAIN NUCLEAR GENERATING STATION, AMENDMENT N0, 59 TO FACILITY OPERATING LICENSE NO. DPR-34 (TAC NO. 64439)
The Comission has issued the enclosed Amendment No. 59 to Facility Crerating License No. DPR-34 for the Fort St. Vrain Nuclear Generating Station. This amendment consists of changes to the Technical Specifications (TS) in response to your application dated December 23,1986 (P-86671) as supplemented by your letter dated December 17,1987(P-87412).
The amendment deletas the tabular listing of safety-related snubbe s from the Fort St. Vrain Technical Specifications.
A copy of the Safety Evaluation is enclosed. The Notice of Issuance will be included in the Cemission's next Bi-weekly Federal Registel notice.
Sincerely,
/s/
Kenneth L. Heitner Project Manager Project Directorate - IV Division of Reactor Projects - III, IV, Y and Special Projects Office of Nuclear Reactor Regulation
Enclosures:
1.
Amendrent No. 59 to DPR-34 2.
Safety Evaluation cc w/ enclosures:
See next page DISTRIBUTION:
Docket File ~
JPartinw l
NRC PDR TBarnhart(4)
Local PDR Wanda Jones EButcher PD4 Reading PNoonan(3)
ACRS (10)
KHeitner GPA/PA l
JCalvo ARM /LFMB OGC-Rockville DHagan EJordan,
Plant File PD4/L Q PD4/PM N OGC-Rockyllje JCalvo//$
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UNITED STATES y
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April 7,1988 Docket No. 50-267 Mr. R. O. Williams, Jr.
Vice President, Nuclear Operations Public Service Company of Colorado Post Office Box 840 Denver, Colorado 80201-0840
Dear Mr. llilliams:
SUBi1ECT: FORT ST. VRAIN NUCLEAR GENERATING STATION, AFFNDMENT NO. 59 TO FACILITY OPERATING LICENSE NO. DPR-34 (TAC NO. 64439) e The Cornission has issued the enclosed Amendment No. 59 to Facility Operating License No. OPR-34 for the Fort St.' Vrain Nuclear Generating Station. This amenchent consists nf charges to the Technical Specifications (TS) in response to your application dated December 23,1986(P-86671)assupplementedbyyour letter dated December 17, 1987 (P-87412).
The arendment deletes the tabular listing of safety-related snubbers from the Fort St. Vrain Technical Specifications.
A copy of the Safety Evaluation is enclosed. The Notice of Issuance will be included in the Comission's next Bi-weekly Federal Register notice.
Sincerely.
h Kenneth L. Heitner, Project Panager Project Directorate - IV Divisicn of Peactor Projects - III, IV, Y and Special Projects Office of Nuclear Reactor Regulation
Enclosures:
1.
Amendment No. 59 to OPR-34 2.
Safety Evaluation cc w/ enclosures:
See next page
Mr. R. O. Williams, Jr.
Public Service Company of Colorado Fort St. Vrain ec:
Mr. D. W. Warembourg, Manager Albert J. Hazle, Director Nurlear Engineering Divisien Radiation Control Division Public Service Corpany Department of Health of Colorado 4210 East lith Avenue P. O. Box 840 Denver, Colorado 80220 Denver, Colorado 80201-0840 Mr. David Alberstein, 14/159A Mr. R. O. Williams, Jr., Acting Manager GA Technologies, Inc.
Nuclear Prcduction Division Post Office Dox P5608 Public Service Corpany of Colorado San Diego, California 92138 16805 Weld County Road 19-1/2 Platteville, Colorado 80651 Mr. H. L. Brey, Manager Nuclear Licensing and Fuel Division Mr.P.F.Tomlinson,fianager Public Service Company of Colorado Quality Assurance Divrsion Public Service Company of Colorado P. O. Box 840 Denver, Colorado 80201-0840 16805 Weld County Road 19-1/2 Platteville, Colorado 80651 Senior Resident Inspector U.S. Nuclear Regulatory Comission Mr. R. F. Walker P. O. Box 640 Public Service Company of Colorado Platteville, Colorado 80651 Post Office Box 840 Denver, Colorado 80201-0840 Kelley, Star.sfield & 0'Donnell Public Service Company Building Commitment Control Progran Roon 900 Coordinator 550 15th Street Public Service Company of Colerado Denver, Colorado 80202 2420 W. 26th Ave. Suite 100-0 Denver, Colorado 80211 Regional Administrator, Region IV U.S. Nuclear Regulatory Co# mission 611 Ryan Plaza Drive Suite 1000 Arlireton, Texas 76011 Chairman, Board of County Comissioners of Weld Courty, Colorado Greeley, Celorado 80631 Regional Pepresentative Radiation Programs Environinental Protection Agency 1 Denver Place 999 18th Street, Suite 1300 Denver, Colorado 80202-2413
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NUCLEAR REGULATORY COMMISSION a
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W ASHING TON, D. C. 20655
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l PUBLIC SERVICE COMPANY OF COLORADO DOCKET NO. 50-267 FORT ST. VRAIN NUCLEAR GENERATING STATION AltEN0 MENT TO FACILITY OPEP.ATING LICENSE Amendment No. 59 License No. OPR-34 1.
The Nuclear Regulatory Comissinn (the Comission) has found that:
A.
The application for amendtnent by Public Service Company of Colorado (the licensee) dated December 23, 1906 as supplemented December 17, Energy Act of 1954, as amended /the Act)quirements of the Atemic 1987, complies with the standards and re
, and the Corinission's rules and regulations set forth in 10 CFR Chapter I; B.
The facility will operate in conformity with the application, as amended, the provisions of the Act, and the rules and ragulations of the Comission; C.
There is reasonable assurance:
(i) that the activities authorized by this amendment can be cenducted without endangering the health and safety of the public, and (ii) that such activities will be cerducted in compliance with the Comission's regulations; i
D.
The issuance of this license amendment will rot be inimical to the comon defense and security or to the health and safety of the public; and E.
The issuance of this amendnent is in accordance with 10 CFR Part 51 of the Comission's iegulations snd all applicable requirements have
'been satisfied.
N'e'!! ? e a n 7pp
2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendr.ent, and paragraph 2.0.(2) of Facility Operating License No. DPR-34 is hereby amended to read as follows' (2) Technical Specifications The Technical Specifications centained in Appendices A and B as revised through Anendment No.59, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
3.
The license at:en hant is effective as of its date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION f ' ($4N Jose A. Calvo, Director Project Directorate - IV
,l Division of Reacter Projects - III, IV, V and Special Projects Office of Nuclear Peactor Regulation
Attachment:
Changes to the Technical Erceifications i
Date of Issuance: April 7, 1988 f
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ATTACHMENT TO LICENSE AffEtTFENT NO. 59 FACILITY OPERATING LICENSE NO. OPR-34 DOCKET NO. 50-267 Replace the following pages of the Appendix A Technical Specifications with j
the attached pages as indicated, the revised pages are identified by ar.endment rumber and contain vertical lines indicating the areas of change.
Pemove Insert 4.3-7 4.3-7 4.3-8 4.3-8 4.3-9 to 4.3-16 5.3-9 5.3-9 5.3-10 5.3-10 5.3-11 5.3-11 5.3-15 5.3-15 i
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Fort St. Vrain 41 Technical Specifications Amendment No. A7,51 Page 4.3-7
$secification t.C0 4.3.10 - Shock Suporessors ($nubbers) -
f.imitime Condition for Operation a) The reactor shall not be operated at power unless all l
shock suppressors (snubbers) supporting Class ! piping l
l systems are operable except as noted in b) through d) of this LCO.
i l
b) With one or more snubbers removed from service in 4 Class ! system or subsystem, within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> replace I
or restore the snt@ber(s) to operable status. If one l
or more snwbber(s) is found inoperable, within 72 e
l hours replace or restore the inoperable snubber (s) and perform an engineering evaluation per Specification SR 5.3,8.c) on the supported component or declare the supported system inoperable and follow the appropriate action statement for that system, c) If the requireeents of a) and b) of this LC0 cannot be met, an orderly shutdown shall be initiated and the reactor shall be in a low power condit;cn within 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />.
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d) If a shock suppressor is determined to be inoperable while the reactor is in the shutdown or refueling f
- mode, the suppressor shall be made operable or replaced prior to reactor operation at power.
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Fort St. Vrain #1 Technical Specifications Amendment No. U,59 Page 4.3-8 f
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8 asis for Specification LC0 8.3.10
$ hock suppressors (snubbers) are designed to prevent unrestrained pipe motion under dynamic loads, as might occur during an earthquake, while allowing normal thermal motion during startup and shutdown. The consequence of an insperable snubber is an increase in the probability of structural damage to piping resulting from the dynaadt.
Ioads produced by a seismic event.
It is therefore necessary that all snubbers required to protect ti e e
Class ! systems, subsystees, or components be operable during reactor power operation.
Because snubber protection is required only during relatively low probability events, a period of 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> is allowed for repair or replacement. In case a shutdown is required, the allowance of 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br /> to reach a low power condition will permit an orderly power reduction consistent with standard operating procedures.
Since reactor geration at power should not be conducted with defective safety-related equipment, reactor power operation is prohibited with inoperable snubbers, except as stated above.
~
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5i Fort St. Vrain #1 Technical Specifications
^
Amend 6 nt No. #,59 Page 5.3-9 activity level decreases to less than 10% of the limit of LC0 4.3.8, at which time weekly sampling may be resumed.
Salis for Specification SR 5.3.7 Th6 specification surveillance interval is adequate to monitor the activity of the secondary coolant.
i
$pecification SR 5.3.8 -
Shock Spooressors ($nubbers)
Surveillancq The following surve'111 ance requirements apply to all Class ! piping system shock suppressors (snubbers):
a) Visual Inspections The first in-service visual inspection of snut;bers shall be performed within sin sonths from issuance of l
this Technical $pecification (Amena." : M). For the purpose of entering the schedule described in this section. it shall be assumed that ths facility had been on a sia-month inspection interval.
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Fort St. Vrain #1 Technica' Specifications Amendment No. AJ, 59 Page 5.3-10 i -
The first in-service visual inspection of snubbers l
shall include all Class I piping system snubbers.
If J
I f
less than two snubbers are found inoperable during *.he first in-service visual inspection, the secc1d in-f, service visuai 17spection shall be performed 12 months l
I plus or minus 25% frca the date of ths. first inspection.
Otherwise, subsequent visual inspn tions shall be performd in accordance with the following l
scredale:
s
?
/{
humber of Inouerable r
Snukbers per inspection Subsequent Visual period Inspection period
- l 0
18 Months plus or minus 25%
1 12 Months plus or minus 25%
2 6 Months plus or minus 25%
3, 4 124 Days plus or minus 25%
5,6,7 62 Days plus or minus 25%
8 or more 31 Days plus or mini!r 25%
1 l
- The insps. tion irterval shall not be lengthened more than one step at a time >
b) Visual insper.tfen Acceptance Criteria l
Visual inspecttens shall verify (1) that there arit no t
y l
visible indications of damage or impaired operability, l
(2) attachments to the foundation or suoporting structure are secure, and (3) in those locatiens where snubber movement-can be manually induced without l
disconnecting the snubber, that the srubber has l
l freedom of movement and is not seized. Snubbers which appear incperable as a result of visual I
r a
y <
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Fort St. Vrain #1 i
Technical Specific 4tions Amendment No. 47, 39 Page 5.3-11 In.pections may be determined operable for the purpose of establishing the next visual inspection interval, providing that (1) the cause of.the rejection is clearly estabitshed and remedied for that particular snubber and for other snubbers that may be generically susceptible, and (2) the affected snubber is functionally tested in the as-found condition and l
determined operable per Sections 5.3.8.d) and 5.3.8.e).
However, when the fluid port of a hydraulic snubber is found to be uncovered, the snubber shall be determined inoperable and cannc4 be determined OPERABLE via functisnal testing for the purpose of establishing the next visual inspection interval. All snubbers connected to an insperable common hydraulic fluid reservoir shall be counted as inoperable
- snubbers, e) Functional Tests At least once' per 18 months (not to exceed 22 1/2 l
months),a representative sample of each type of snubber shall bo tested using one of the following sample plans: The sample plan (s) shall be s*lected l
prior to the test period and cannot be changed during the test period. The NRC Regional Administrator shall I
be notified in writing of the sample plan (s) selected for each type of snubber prior to the test period or the sample plan (s) used in the prior test period shall be implemented:
- 1) At least 10% of the total of the type of snubber shall be functionally tested either in place or in a bench test. For each snubber of that type that does not meet the functional test acceptance criterie of Specification SR 5.3.8.d) or SR 5.3.s..), an additional los of that type of r
3 Fort St. Vrain #1 Technical Specific ions Amendment No. 47.
Page 5.3-15 f) Exemption From Visu_al Inspection or Functional Tests Permanent er other exemptions from the surveillance program for individual snubbers may be granted by the l
Commission if a justifiable uasis for exemption is l
presented.
I g) Record keepina Record keepir;g shall consist of:
9
- 1) A historical record for each snutber shall be maintained.
e
- 2) Concurrent with the first in-service visual inspection and at least once per refueling cycle thereafter, the historical records for each l
snubber shall be reviewed to determine any trends t
that may adversely affect service life.
- 3) The maximum expected service life for the various seals, seal materials, and applicatioas shall be determined and established based on engineering information and the seals shall be replaced so that the maximum expected service life will not be exceeded during a period when the snubber is required to be OPEP.ABLE. This monitoring program shall be fully implemented within 22 1/2 months from the issu4 hee of this Technical Specification (Amendment 39).
_. ~ _. _..,_.
i 4 00 UNITED STATES
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NUCLEAR REGULATORY COMMISSION
~j WASHING TON,0. C. 20555 l
SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT N0. 59 O FACILITY OPERATING LICENSE N0. OPR-34 T
PUBLIC SERVICE COMPANY OF COLORADO FORT ST. VRAIN NUCLEAR GENERATING STATION DOCKET NO. 50-267
1.0 INTRODUCTION
By letter dated December 23, 1986, Public Service Company of Colorado proposed changes in the technical specifications (TS) of the Fort St.
Vrain Nuclear Generating Station. The changes involve the deletion of the snubber tables and a clarification of the requirements for performance of an engineering evaluation o'n inoperable snubbers. The licensee's application was made in response to NRC Generic Letter 84-13 "Technical Specifications for Snubbers", dated May 3, 1984. These chanaes are intended to eliminate the need for frequent TS amendments to incorporate changes in the snubber listings. The staff requested additional infoma-tion from the licensee by letter dated October 19, 1987. The licensee prctided this additional information by letter dated December 17, 1987.
?.0 EVALUATION The NRC staff indicated in the referenced Generic Letter that it had l
reassessed the inclusion of snubber listings within the TS and concluded l
that such listings were not necessary provided the snubber TS are redified to specify which snubbers are required to be operable. The licensee's requested changes to the TS would delete the tabular listings of snubbers and add the criteria requiring all snubbers to be operable except those snubbers on non safety-related systems whose faileires would have no adverse effects on any safety-related systems.
We have reviewed the current TS together with the proposed changes and compared these changes with the model TS provided in the Generic Letter.
l From our review, we find that the proposed changes are administrative in I
nature and do not authorize any physical changes to the plant's safety-related structures, systems or components. Any physicci changes in snubber quantities, types or location would have to be reviewed under the provisi6ns of 10 CFR 50.59 to detemine if an Unreviewed Safety l
Ouestion exists. Therefore, the proposed changes would not in any way reduce availability of those snubbers which are provided to ensure that the structural integrity of the reactor coolant system and all other safety-related systems is maintained during and following a seismic or other transient events.
Based on the above discussion and the fact that the proposed changes are consistent with guidance provided in the Generic Letter, we have determined that the proposed changes are acceptable.
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3.0 ENVIRONMENTAL CONSIDERATION
The amendment involves a change in the installation er use of a facility component located within the restricted area as defined in 10 CFR Part 20.
The staff has determined that the amendment involves no significant increase in the amounts, and no significant change in the types, of any effluents that may be released offsite, and that there is no significant increase in individual or cumulative occupational radiation exposures.
The Commission has previously issued a proposed finding that the amendment involves no sienificant hazards consideration and there has been no public comment on such finding. Accordingly, the amendment meets the eligibility criteria for categorical exclusion set torth in 10 CFP Section 51.22(c)(9).
Pursuant to 10 CFR 51.22(b), no environmental impact statement or environ-mental assessnent need be prepared in connection with the issuance of the amendment.
4.0 CONCLUSION
The staff has concluded, based on the considerations discussed above, that:
(1) there is reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed manner, and (2) such activities will be conducted in compliance with the Commission's regulations, and the issuance of the amendment will not be inimical to the common defense and security or to the health and safety of the public.
Date: April 7,1988 Principal Contributors:
M. Hartzman, EMEB/ DEST 8
4
April 7,1988 Docket No. 50-267 Mr. R. O. Williams, Jr.
Vice President, Nuclear Operations Public Service Company of Colorado Post Office Box 840 Denver, Colorado 80201-0840
Dear Mr. Williams:
SUBJECT:
FORT ST. VRAIN NUCLEAR GENERATING STATION, AMENDMENT NO. 59 TO FACILITY OPERATING LICENSE NO. DPR-34 (TAC NO. 64439)
The Connission has issued the enclosed Amendment No. 59 to Facility Operating License No. DPR-34 for the Fort St. Vrain Nuclear Generating Station. This amendment consists of changes to the Technical Specifications (TS) in response to your application dated December 23, 1986 (P-86671) as supplemented by your letter dated December 17,1987(P-87412).
e The amendment deletes the tabular listing of safety-related snubbers from the Fort St. Vrain Technical Specifications.
A copy of the Safety Evaluation is enclosed. The Notice of Issuance will 0
be included in the Cenrission's next Bi-weekly Federal Register notice.
Sincerely,
/s/
Kenneth L. Heitner, Project Manager Project Directorate - IV Division of Reactor Pro,iects - III, IV, V and Special Projects Office of Nuclear Reactor Regulation
Enclosures:
1.
Amendtrent No. 59 to DPR-34 2.
Safety Evaluation cc w/ enclosures:
See next page DISTRIBUTION:
Docket File JPartlow NRC PDR TBarnhart(4)
Local PDR Wanda Jones EButcher PD4 Reading PNoonan (3)
ACRS (10)
KHeitner GPA/PA JCalvo ARM /LFMB OGC-Rockville DHagan EJordan,
Plant File PD4/LA3(
PD4/PM N OGC-Rockyj PD4/D/7%
4 L
JCalvo gf 8 PNoonanJ KHeitner:sr e
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8 UNITED STATES 8
h NUCLEAR REGULATORY COMMISSION 5
"l WASHINGTON, D. C. 20555 t
p April 7,1988 Docket No. 50-267 Mr. R. O. Williams, Jr.
Vice President, Nuclear Operations Public Service Cor.pany of Colorado Post Office Box f;40 Denver, Colorado 80201-0840
Dear Mr. Williams:
SUBi1ECT: FORT ST. VRAIN NUCLEAR GENERATING STATION, AFFNDMENT NO. 59 TO FACILITY OPERATING LICENSE NO. DPR-34 (TAC NO. 64439)
=
l The Cornission has issued the enclosed Amendment No. 59 to Facility Operating License No. DPR-34 for the Fort St.' Vrain Nuclear Generating Station. This amendment consists of charges to the Technical Specifications (TS) in response to your application dated Pecember 23,1986(P-06671)assupplementedbyyour
+
letter dated December 17, 1987 (P-87412).
l l
The anendment deletes the tabular listing of safety-related snubbers from the Fort St. Vrain Technical Specifications.
A copy of the Safety Evaluation is enclosed. The Notice of Issuance will be included in the Comission's next Bi-weekly Federal Register notice.
Sincerely, Kenneth L. Heitner, Project Panager Project Directorate - IV Division of Reactor Projects - III, l
IV, Y and Special Projects Office cf Nuclear Reactor kegulation i
Enclosures:
1.
Amendment No. 59 to OPR-34 l
2.
Safety Eva,1uation cc w/ enclosures:
See next page
f.
Mr. R. O. Williams, Jr.
Public Service Company of Colorado Fort St. Vrain Cs
. W. Warembourg, Manager Albert J. Hazle, Director Mr. '
Nuclear Engineering Division Radiation Control Division Public Service Cor.pany Department of Health of Colorado 4210 East lith Avenue P. O. Box 840 Denver, Colorado 80220 Denver, Cciorado 80201-0840 Mr. David Alberstein, 14/159A Mr. R. O. Williams, Jr., Acting Manager GA Technologies, Inc.
Nuclear Production Division Post Office Box F5608 Public Service Corpany of Colorado San Diego, California 92138 16805 Weld County Road 19-1/2 Platteville, Colorado 80651 Mr. H. L. Brey, Manager Nuclear Licensing and Fuel Division Mr.P.F.Tomlinson,ganager Public Service Compary of Colorado Quality Assurance Division Public Service Company of Colorado P. O. Box 840 Denver, Colorado 30201-0840 16805 Weld County Road 19-1/2 Senior Resident Inspector U.S. Nuclear Regulatory Comission Mr. R. F. Walker j
j P. O. Box 6!0 Pub' tic Service Company of Colorado Platteville, Colorado 80651 Post Office Box 840 Denver, Colorado 80201-0840 Kelley, Stansfield & 0'Donnell l
Public Service Company Building Comitment Control Progran Roon 900 Coordinator 550 15th Street Public Service Company of Colorado Denver, Colorado 80202 2420 W. 26th Ave. Suite 100-D Denver, Colorado 80211 Regional Adninistrator, Region IV U.S. Nuclear Regulatory Comission 611 Ryan Plaza Drive, Suite 1000 l
Arlington, Texas 76011 Chairman, Board of County Comissioners l
of Weld Courty, Colorado Greeley,'Celorado 80631 Regional Representative Radiation Programs Environmental Protection Agency 1 Denver Place 999 18th Street, Suite 1300 Denver, Colora:fo 80202-2413 l
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gf UNITED STATES g
{? 3 NUCLEAR REGULATORY COMMISSION 5
j WASHING TO N, D. C. 20555
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PUBLIC SERVICE COMPANY OF COLORADO DOCKET NO. 50-267 FORT ST. VRAIN NUCLEAR GENERATING STATION AlfENDMENT TO FACILITY OPERATING LICENSE Amendment No. 59 License No. DPR-34 1.
The Nuclear Regulatory Comissinn (the Comission) has found that:
A.
The application for amendtnent by Public Service Company of Colorado (the licensee) dated December 23, 1986 as supplemented December 17, 1987, complies with the standards and requirements of the Atemic Energy Act of 1954, as amended (the Act), and the Comission's rules and regulations set forth in 10 CFR Chapter I; B.
The facility will operate in conformity with the application, as amended, the provisions of the Act, and the rules and regulations of the Comission; C.
There is reasonable assurance:
(1) that the acti" '
athorized by this amendment can be conducted without endant
( M health and safety of the public, and (ii) that such activuRs will be conducted in compliance with the Comission's regulations; D.
The isscance of this license amendment will rot be inimical to the comon d3fense and security or to the health and safety of the public; and I
i E.
The issuance of this amendment is in accordance with 10 CFR Part 51
(
of the Comission's regulations and all applicable n'equirements have
- been satisfied.
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r 2-2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amenocent, and paragraph 2.D.(2) of Facility Operating License No. DPR-34 is hereby amended to read as follows:
(2) Technical Specifications The Technical Specifications centained in Appendices A and B, as revised through Amendment No. 59, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
3.
The license accrdrant is effective as of its date of issuance.
FOR THE HUCLEAR REGULATORY COMMISSION e
d Mdw
,4v,-c Jose A. Calvo, Director Project Directorate - IV Division of Reactor Projects - III.
IV, Y and Special Projects Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical l
Specifications l
Date of Issuance: April 7,1988 l
l l
8 4
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ATTACHMENT TO LICENSE Af'Ef'CFENT NO. 59 FACILITY OPERATING LICENSE NO. OPR-34 DOCKET NO. 50-267 Replace the following pages of the Appendix A Technical Specifications with the attached pages as indicated. the revised pages are identified by amendment number and contain vertical lines indicating the areas of change.
Pemove Insert 4.3-7 4.3-7 4.3-8 4.3-8 4.3-9 to 4.3-16 5.3-9 5.3-9 5.3-10 5.3-10 5.3-11 5.3-11 5.3-15 5.3-15
- e a
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rort St. Vrain ti' Technical Specifications Amendment No. 47,59 Page 4.3-7 loecification LCO4.3.10-ShockSuppgessori_{$yutStes}-
Limitiyo Cenditlin_fo L eoratict 0
a) The reactor sna11 not be operated at power unless all I
shock suppressors (snab5ers) supporsing fits: 1 piping l
systems are operable except as noted in b) through d) of this LCO.
l b) With c r.
or more snubbers removed from service in a Class I system or subsystem, within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> replace t
restore the snu,bber(s) to operable status. If one l
or 1
or more snubber (s) is found inoperable, within 72 l
hours replace or restore the inoperable snubber (s) and perform an engineering evaluation per Specification SR 5.3.8.c) on the supported componant or declare the supported system inoperable and follow the appropriate action statement for that system.
c) If the requirements of a) and b) of this LCO cannot be met, an orderly shutdown shall be initiated and the reactor shall be in a low power condition within 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />.
d) If a shock suppressor is determined to be inoperable while the reactor is in the shutdown or refueling I
- mode, the suppressor shall be made operable or replaced prior to reactor operation at power.
I 1
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9
E Fort St. Vrain #1 Technical Specifications Amendment No. 47,59 Page 4.3-8 I
I Basis for Specification LCO 4.3.10 Shock suppressors (snubbers) are designed to prevent unrestrained pipe motion under dynamic loads, as might occur during an earthquake, while allowing normal thermal motion during startup and shutdown. The consequence of an inoperable snubber is an increase in the probability of structural damage to piping resulting from the dynande leads produced by a seismic event.
It is therefore neces sa ry that all snubbers required to protect the Class I systees, subsystems, or components be operable during reactor power operation.
Because snubber protection is required only during relatively low probability events, a period of 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> is allowed for rezair or replacement. In case a shutdown is required, the allowance of 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br /> to reach a low power condition will pe rmi t an orderly power reduction consistent with standard operating procedures.
Since reactor operation at power should not be conducted with defective safety-related equipment, reactor power operation is prohibited with inoperable snubbers, except l
as stated above.
9
,,3,
-Fort 5%. Vrain #1 Technical Specifications Amendment No, f/,59 Page 5.3-9 activity level decreases to less than 10% of the limit of LCO 4.3.8, at which time weekly sampling may be resumed.
Basis for Specification SR S.3.7 The specification surveillance interval is adequate to monitor the activity of the secondary coolant.
Specification SR S.3.8 -
Shock Suppressors (Snubbers)
Surveillance The following surve'111ance requirements apply to all Class I piping system shock suppressors (snubbers):
a) Visual inspections The first in-service visual inspection of snubbers shall be performed within six months from issuance of l
this Technical Specificatien (Amendment 39). For the purpose of entering the schedule described in this section, it shall be assumed that the facility had been on a six-month 16spection interval.
4-
l Fort St. Vrain #1 Technical Specifications Amendment No. f7, 59 Page 5.3-10 The first in-service visual inspection of snubbars I
shall include all Class I piping system snubbers.
If 1955 than two snubbers are found inoperable during the first in-service visual inspection, the second in-service viaual inspection shall be performed 12 months plus or minus 25% from the date of the first inspection.
Otherwise, subsequent visual inspections shall be performed in accordance with the following schedule:
Number of Inocerable Snubbers per Inspection Subsequent Visual period Inspection Period
- O 18 Months plus or minus 25%
1 12 Months plus or minus 25%
2 6 Months plus or minus 25%
3, 4 124 Days plus or minus 25%
5, 6, 7 62 Days plus or minus 25%
8 or more 31 Days plus or minus 25%
- The inspection interval shall not be lengthened more than one step at a time.
b) Visual Inspection Acceptarce Criteria Visual inspections shall verify (1) that there are no visible indications of damage or impaired operability, (2) attachments to the foundation or supporting J
structure are secure, and (3) in those locations where snubber movement can be manually induced without disconnecting the snubber, that the snubber has l
freedom of movement and is not seized. Snubbers which appear inoperable as a result of visual
Fort St. Vrain el Technical Specific AmendmentNo.47,gions Page 5.3-11 inspections may be determined operable for the purpose of establishing the next visual inspection interval, providing that (1) the cause of.the rejection is clearly established and rem @ died for that particular snubber and for other snubbers that may be generically susceptible, and (2) the affected snubber is functionally tested in the as-found condition and l
determined operable per Sect.'ons 5.3.8.d) and 5.3.8.e).
However, when the fluid port of a hydraulic snubber is found to be uncovered, the snubber shall be determined inoperable and cannot be deterstned OPERABLE via functional testing for the purpose of establishing the next visual inspection interval. All snubbers connected to an inoperable common hydraulic fluid reservoir shall be counted as inoperable
- snubbers, c) Functional Tests q
At least once' per 18 months (not to exceed 22 1/2 months),a representative sample of each type of snubber shall be tested using one of the following sample rians: The sample plan (s) shall be selected prior to the test period snd cannot be changed during the test period. The NRC Regional Administrator shall be notified in writing of the sample plan (s) selected for each type of snubber prior to the test ;trics or I
tne sample plan (s) used in the prior test period shall be implee.ented:
- 1) At least 10% of the total of the type of snubber shall be functionally tested 31ther in place or in a bench test. For each snubber of that type that does not meet the functional test acceptance criteria of Specification SR 5.3.8.d) or SR 5.3.8.e), an additional 10% of that type of
Fort St. Vrain #1 2
Technical Specific Amendment No. 47 gions Page 5.3-15 f) Exemption From Visual inspection or Functional Tests Permanent or other exemptions from the surveillance program for individual snubbers may be granted by thi l
Cosnission if a justifiable basis for exemption is l
presorted.
I g) Record Keeping Record keeping shall consist of:
e
- 1) A historical record for each snubber shall be maintained.
- 2) Concurrent with the first in-service visual j
inspection and at least once per refueling cycle t
thereafter, the historical re:ceds for each l
scubber shall be reviewed to determine any trends that may adversely affect service life.
- 3) The maximum expected service life for the various seals, seal a.iterials, and applications shall be l
determined and established based on engineering information and the seals shall be replaced so that the maximum expected service life will not be exceeded during a period when the snubber is required to be OPERABLE. This monitoring program i
shall be fully implemented within 22 1/2 months l
from the issuance of this Technical Specification (Amendment 39).
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UNITED STATES y
g NUCLEAR REGULATORY COMMISSION 7.
- j WASHINGTON, D. C. 20555
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SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO. 59 TO FACILITY OPERATING LICENSE NO. DPR-34 PUBLIC SERVICE COMPANY OF COLORADO FORT ST. VRAIN NUCLEAR GENERATING STATION DOCKET NO. 50-267
1.0 INTRODUCTION
By letter dated December 23, 1986, Public Service Company of Colorado proposed changes in the technical specifications (TS) of the Fort St.
Vrain Nuclear Generating Station. The changes involve the deletion of the snuhber tables and a clarification of the requirements for performance of an engineering evaluation oh inoperable snubbers. The licensee's application was made in response to NRC Generic Letter 84-13, "Technical Specificetions for Snubbers", dated May 3, 1984 These chances are intended to eliminate the need for frequent TS amendments to incorporate changes in the snubber listings. The staff requested additional infoma-tion from the licensee by letter dated October 19, 1987. The licensee provided this additional information by letter dated December 17, 1987.
2.0 EVALUATION The NRC staff indicated in the referenced Generic letter that it had reassessed the inclusion of snubber listings within the TS and concluded that such listings were not necessary provided the snubber TS are modified to specify which snubbers are required to be operable. The licensee's requested changes to the TS would delete the tabular listings of snubbers and add the criteria requirino all snubbers to be operable except those snuhbers on non safety-related systems whose failures would have no adverse effects on any safety-related systems.
We have reviewed the current TS together with the proposed changes and compared these changes with the model TS provided in the Generic Letter.
From our review, we find that the proposed changes are administrative in nature and do not authorize any physical changes to the plant's safety-related structures, systems or components. Any physical changes in snubber quantities, types or location would have to be reviewed under the provisions of 10 CFR 50.59 to detemine if an Unreviewed Safety Duestion exists. Therefore, the proposed changes would not in any way reduce availability of those snubbers which are provided to ensure that the structural integrity of the reactor coolant system and all other safety-related systems is maintained during and following a seismic or other transient events.
Based on the abovt discussion and the fact that the proposed changes are consistent with guidance provided in the Generic letter, we have detemined that the proposed changes are acceptable.
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3.0 ENVIRONMENTAL CONSIDERATION
The amendment involves a change in the installation or use of a facility component located within the restricted area as defined in 10 CFR Part 20.
The staff has determined that the amendment involves no significant increase in the amounts, and no significant change in the types, of any effluents that may be released offsite, and that there is no significant increase in individual or cumulative occupational radiation exposures.
The Commission has previously issued a proposed finding that the amendment involves no significant hazards consideration and there has been no public comment on such finding. Accordingly, the amendment meets the eligibility criteria for categorical exclusion set forth in 10 CFP Section 51.22(c)(9).
Pursuant to 10 CFR 51.22(b), no environnental impact statement or environ-mental assessnent need be prepared in connection with the issuance of the amendment.
4.0 CONCLUSION
The staff has concluded, based on the considerations discussed above, that:
will not be endangered by operation in the proposed manner, and (2) public (1) there is reasonable assurance that the health and safety of the such activities will be conducted in compliance with the Commission's regulations, and the issuance of the amendment will not be inimical to the common defense and security or to the health and safety of the public.
t l
Date: April 7,1988 Principal Contributorst M. Hartzman, EMEB/ DEST 4
April 7,1988 Docket No. 50-267 Mr. R. O. Williams, Jr.
Vice President, Nuclear Operations Public Service Company of Colorado Post Office Box 840 Denver, Colorado 80201-0840
Dear Mr. Williams:
SUBJECT:
FORT ST. VRAIN MUCLEAR GENERATING STATION, AMENDMENT N0. 59 TO FACILITY OPERATING LICENSE NO. DPR-34 (TAC NO. 64439)
The Comission has issued the enclosed Ar.endment No. 59 to Facility Operating License No. DPR-34 for the Fort St. Vrain Nuclear Generating Station. This amendment consists of changes to the Technical Specifications (TS) in response to your application dated December 23, 1986 (P-86671) as supplemented by your letter dated December 17, 1987 (P-87412).
The amendment deletes the tabular listing of safety-related snubbers from the Fort St. Vrain Technical Specifications.
A copy of the Safety Evaluation is enclosed. The Notice of Issuance will be included in the Comission's next Bi-weekly Federal Register notice.
i l
Sincerely,
/s/
Kenneth L. Heitner, Project Manager Project Directorate - IV Division of Reacter Pro.iects - III, IV, Y and Special Projects Office of Nuclear Reactor Regulation i
Enclosures:
1.
Amendment No. 59 to DPR-34 2.
Safety Evaluation ec w/ enclosures:
See next page DISTRIBUTION:
Docket File JPartlow NRC PDR TBarnhart(4) local PDR Wanda Jones EButcher PD4 Reading l
PNoonan (3)
ACRS(10)
KHeitner GPA/PA JCalvo ARM /LFMB OGC-Rockville DHagan EJordan,
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UNITED STATES y
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- j WASHINGTON D. C. 20555 g
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April 7,1988 Docket No. 50-267 Y
Mr. R. O. Williams, Jr.
Vice President, Nuclear Operations Public Service Company of Colorado Post Office Box 840 Denver, Colorade 80201-0840
Dear Mr. Williams:
SUBi1ECT: FORT ST. VRAIN NUCLEAR GENERATING STATION, AFFNDMENT NO. 59 TO FACILITY OPERATING LICENSE N0. DPR-34 (TAC NO. 64439)
The tennission has issued the enclosed Amendnent No. 59 to Facility Operating License No. OPR-34 for the Fort St.' Vrain Nuclear Generating Station. This amendment consists of charges to the Technical Specifications (TS) in response to your application dated Pecember 23, 1986 (P-86671) as supplemented by your letter dated December 17, 1987 (P-87412).
The arendment deletes the tabular listing of safety-related snubbers from the Fort St. Vrain Technical Specifications.
A copy of the Safety Eveluation is enclosed. The Notice of Issuance will be included in the Corr 11ssion's next Bi-weekly Federal Register notice.
Sincerely, h
Kenneth L. Heitner, Project Manager Project Directorate - IV Division of Reactor Projects - III, IV, Y and Special Projects Office of Nuclear Reactor Regulation
Enclosures:
1.
Amendment No. 59 to DPR-34 2.
Safety Evaluation cc w/ enclosures:
See next page
Mr. R. O. Williams, Jr.
Public Service Company of Colorado Fort St. Vrain cc:
Mr. D. W. Wsrembourg, Manager Albert J. Hazle, Director Nurlear Engineering Division Radiation Control Division Public Service Company Department of Health of Colorado 4210 East lith Avenue P. O. Box 840 Denver, Colorado 80220 Denver, Colorado 30201-0840 Mr. David Alberstein,14/159A Mr. R. O. Williams, Jr., Acting Manager GA Technologies, Inc.
Nuclear Preduction Division Post Office Box P5608 Public Servica Corpany of Colorado San Diego, California 92138 16805 Weld County Road 19-1/2 Platteville, Colorado 80651 Mr. H. L. Brey, Manager Nuclear Licensing and Fuel Division Mr.P.F.Tomlinson,Qanager Public Service Company of Colorado Quality Assurance Division Public Service Company of Colorado P. O. Box G40 Denver, Colorado 80201-0840 16805 Weld County Road 19-1/2 Senior Resident Inspector U.S. Nuclear Regulatory Comission Mr. R. F. Walker P. O. Box 640 Public Service Company of Colorido Platteville, Colorado 80651 Post Office Box 840 Denver, Colorado 80201-0880 Kelley, Star;sfield & 0'Donnell Public Service Company Building Comitment Control Program Roon 900 Coordinator 550 15th Street Public Service Company of Colorado Denver, Colorado 80202 2420 W. 26th Ave. Suite 100-0 Denver, Colorado 80211 Regional Administrator, Region IV U.S. Nuclear Regulatory Comission 611 Ryan Plaza Drive, Suite 1000 Arlington, Texas 76011 Chairman, Board of County Comissioners of Weld Courty, Colorado Greeley, Colorado 80631 Regional Representative Radiation Programs Environmental Protection Agency 1 Denver Place 999 18th Street, Suite 1300 Denver, Colorado 80202-2413 9
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UNITED STATES E"
p, NUCLEAR REGULATORY COMMISSION O
.j WASHINGTON, D. C. 20555
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PUBLIC SERVICE COMPANY OF COLORADO DOCKET NO. 50-267 FORT ST. VRAIN NUCLEAR GENERATING STATION AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 59 License No. DPR-34 1.
The Nuclear Regulatory Comission (the Comission) has found t4at:
A.
The application for amendtnent by Public Service Company of Colorado (the licensee) dated December 23, 1986 as supplemented December 17, 1987, complies with the standards and requirements of the Atemic Energy Act of 1954, as amended (the Act), and the Comission's rules and regulations set forth in 10 CFR Chapter I; B.
The facility will operate in conformity with the application, as amended, the provisions of the Act, and the rules and regulations of the Comission; C.
There is reasonable assurance:
(i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, an' (ii) that such activities will be conducted in compliance with the Comission's regulations; D.
The issuance of this license amendment will rot be inimical to the comon defense and security or to the health and safety of the public; and E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Comission's regulations and all applicable require:nents have
- been satisfied.
GE&fi760 98 7/f
2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.0.(2) of Facility Operating License No. DPR-34 is hereby amended to read as follows:
(2) Technical Specifications The Technical Specifications centained in Appendices A and B, as revised through Amendment No. 59, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
3.
The license amendrant is effective as of its date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
=
d ' GlN Jose A. Calvo, Director e
Project Directorate - IV Division of Reactor Projects - III, IV, Y and Special Projects Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Srceifications Date of Issuance: April 7,1988 l
l
ATTACHMENT TO LICENSE AftEP:CFENT NO. 59 FACILITY OPERATING LICENSE NO. DPR-34 DOCKET N0. 50-267 Replace the following pages of the Appendix A Technical Specifications with the attached pages as indicated. the revised pages are identified by ar.endment number and contain vertical lines indicating the areas of change.
Pemove Insert 4.3-7 4.3-7 4.3-8 4.3-8 4.3-9 to 4.3-16 5.3-9 5.3-9 5.3-10 5.3-10 5.3-11 5.3-11 5.3-15 5.3-15 i
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Fort St. Vrain #1 Technical Specifications Arnendment No. //, 51 Page 4.3-7
!Decification LCO 4.3.10 - Shock Suppressors (Snubbers) -
Limitino Condition for Operation a) The reactor shall not be operated at pewsr unless all i
shock suppressors (snubbers) supporting Class Ing l
systems are operable except as noted in b) through d) of this LCO.
l b) With one or more snubbers removed from service in a Class I system or subsystem, within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> replace I
or restore the snypber(s) to operable status. If one l
or more snubber (s) is found inoperable, within 72 t
l hours replace or restore the inoperable snubber (s) and perform an engineering evaluation per Specification SR 5.3.8.c) on the supported component or declare the supported system inoperable and follow the appropriate action statement for that system, c) If the requirements of a) and b) of this LCO cannot be met, an orderly shutdown sht11 be initiated and the reactor shall be in a low power condition within 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />.
d) If a fNck suppressor is determined to be inoperable while the reactor is in the shutdown or refueling
- mode, the suppressor shall be made operable or replaced prior to reactor operation at power.
I I
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,__x
Fort St. Vrain #1 Technical Specifications Amendment No. 37,59 Page 4.3-8
[
l I
Basis for Specification LCO 4.3.10 Shock suppresso"s (snubbers) are designed to prevent unrestrained pipe motion under dynamic loads, as afght occur during an earthquake, while allowing normal thermal motion during startup and shutdown. The consequence of an inoperable snubber is an 'ncrease in the probabili,ty of structural damage to piping resulting from the dynamic loads produced by a seismic e v.;n t.
It is therefore necessary that all snubbers required to protect the Class I systems, subsystems, or components be operable during reactor power operation.
Becauw snubber protection is required only during '
relatively low probability events, a period of 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> is allowed for repair or replacement. In case a shutdown is required, the allowance of 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br /> to reach a hw power condition will permit an orderly power reduction consistent with standtrd operating procedures.
Since reactor operation at power should not be conducted with defective safety-related equipment, reactor power operation is prohibited with inoperable snubbers, except as stated above.
O
Fort St. Vrain #1 Technical Specifications Amendment No. f 7,59 Page 5.3-9
(
activity level decreases to less than 10% of the limit of LCO 4.3.8, at which time weekly sampling may be resumed.
Jasis for Specification SR 5.3.7 The specification surveillance interval is adequate to ovattor the activity of the secondary coolant.
Specification SR 5.3.3 -
Shock Suppressors (Snubbers)
Surveillance ire following surve'111ance requirements apply to all Class I piping system shock suppressors (snubbers):
a) Visual Insoections The first in-service visual inspection of snubbers i
shall be performed within six months from issuance of l
this Technical Specification (Amendment 39). For the purpose of entering the schedule described th this sectiet, it sha?1 be assumed that the facility had been on a six-month inspection interval.
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Fort St. Vrain #1 Technical Specifications Amendeint No. 47, 59 Page 5.3-10 The first in-service visual inspection of snubbers I
shall include all Class T piping system snubbers.
If less than two snubbers are found inoperable during the first in-service visual inspection, the second in-4 service visual inspection shall be performed 12 months plus or minus 25% from the date of the first inspection, Otherwise, subsequent visual inspections shall be perfsreed ir accordance with the following schedule:
s Number of Inoperable 5n deeri per Inspection Subsequent Visual period inspection period" 0
18 Months plus or minus 25%
1 12 Months plus or minus 25%
2 6 Months plus or minus 25%
J, 4 124 Days plus or minus 25%
5,6,7 02 Days plus or minus 25%
8 or more 31 Oays plus or minus 25t
- The inspection interval shall not be lengthened niore than one step at a time, b) Visuel inspection Acceptance Criteria l
Visual inspections shall verify (1) that there are
.3 i
visible indications of damage or impaired operability.
(2) attachments to the foundatt5n or supporting structure are secure, and (3) in those locations where l
l snubber movement can be manually induced without i
disconnecting the snubber, that the snuboer has l
freedom of movement and is not seized. Snubbers which l
appear inoperable as a result of visual i
l
?
C Fort Sto Vrain el Technical Specific AmendmentNo.47,btions Page 5.3-11 inspections may be determined operable for the purpose of establishing the next visual inspection intersal, providing that (1) the cause of.the rejection is clearly established and rentedied for that particular snubber and for other snutb9rs that may be generically susceptible, and (2) the affected snubber is functionally tested in the as-found condition and l
dete r.11ned operable per Sections 5.3.8.d) and 5.3.8.e).
However, when the fluid port of a hydraulic snubber is found to be uncovered, the snubber shall be determined inoperable and cannot be determined OPERABLE via functional testing for the purpose of establishing the next visual inspection interval. All snubbers connected to an inoperable common hydraulic fluid re servoir shall be counted as inoperable snubbers.
c) Functional Tests At least once' per 18 months (not to exceed 22 1/2 months),a represtritative sample of each type of
(
Snubber shall be tested using one of the following sample plans: The sample plan (s) shall be selected prior to the test period and cannot be changed during the test pefiod. The NRC Regional Administrator shall be notified in writing of the sample plan (
selected for each type of snubber prior to the test W riod or the sample plan (s) used in the prior test period shall be implemented:
- 1) At least 10% of the total of the type of snubber shall be functionally tested either in place or in a bench test. For each snubber of thet type that does not meet the functional test acceptance criteria of Specification $R 5.3.8.d) or $R 5.3.8.e), an additional 10% of that type of t
F
Fort St. Vrain el Technical Specific Amendment No. 47, Nions Page 5.3-15 f) Exemption From visual inspection or Functional Tests Permanent or other exactions from the surveillance program for individual snubbers may be granted by the l
Commission if a justifiable basis for exemption is l
presented.
I g) Record Keeping Record keeping shall consist of:
e
- 1) A historical record for each snubber shall be maintained.
e
- 2) Concurrent with the first in-service visual inspection ano at least once per refueling cycle thereafter, the historical records for each l
snubber shall be reviewed to determine any trends that may adversely affect service life.
32 The maximum expected service life for the various seals, seal materials, and applications shall be determined and established based on engineering i
information and the seals shall be replaced so tnat the maximum expected service life will not be exceeded during a period when the snubber is required to be OPERABLE. This monitoring program Shall be fully implemented within 22 1/2 months f
from the issuance of this Technical Specification (Amendment 39).
F
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UNITED STATES e
g NUCLEAR REGULATORY COMMISSION y
"j W ASHING TON. D. C, 205$5
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SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT h0. 59 TO FACILITY OPERATING LICENSE NO. OPR-34 PUBLIC SERVICE COMPANY OF COLORADO FORT ST. VRAIN NUCLEAR GENERATING STATION DOCKET NO. 50-267
1.0 INTRODUCTION
By letter dated December 23, 1986, Public Service Company of Colorado proposed changes in the technical specifications (TS) of the Fort St.
Vrain Nuclear Generating Station. The changes involve the deletion of the snuhber tables and a clarification of the requirements for performance of an engineering evaluation o'n inoperable snubbers. The licensee's application was made in response to NRC Generic Letter 84-13. "Technical Specifications for Snubbers", dated May 3, 1984. These chances are intended to eliminate the need for frequent TS amendments to incorporate changes in the snubber listings. The staff requested additional informa-tion from the licensee by letter dated October 19, 1987. The licensee provided this additional information by letter dated December 17, 1987.
2.0 EVALUATION The NRC staff indicated in the referenced Generic Letter that it had reassessed the inclusion of snubber listings within the TS and concluded that such listinps were not necessary provided the snubber TS are modified to specify which snubbers are required to be opertble. The licensee's requested changes to the TS would delete the tabular listings of snubbers and add the criteria requiring all snubbers to be operable except those snubbers on non safety-related systems whose failures would have no adverse effects on any safety-related systems.
We have reviewed the current TS together with the proposed changes and compared these changes with the model TS provided in the Generic Letter.
From our review, we find that the proposed changes are administrative in nature and do not authorize any physical changes to the plant's safety-related structures, systems or components. Any physical changes in snubber quantities, types or location would have to be reviewed under the provis'ibns of 10 CFR 50.59 to detemine if an Unreviewed Safety Duestion exists. Therefore, the proposed changes would not in any way reduce availability of those snubbers which are provided to ensure that the structural integrity of the reactor coolant system and all other safety-related systems is maintained during and following a seismic or other transient events.
Based on the above discussion and the fact that the proposed changes are consistent with guidance provided in the Generic Letter, we have detemined that the proposed changes are acceptable.
U Yy 1 ? Tj$$
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3.0 ENVIRONMENTAL CONSIDERATION
The amendment involves a change in the installation or use of a facility component located within the restricted area as defined in 10 CFR Part 20.
The staff has determined that the amendment involves no significant increase in the amounts, and no significant change in the types, of any effluents that may be released offsite, and that there is no significant increase in individual or cumulative occupational radiation exposures.
The Commission has previously issued a proposed finding that the amendment involves no significant hazards consideration and there has been no public coerent on such finding. Accordingly, the amendment meets the eligibility criteria for categorical exclusion set forth in 10 CFP Section 51.22(c)(9).
Pursuant to 10 CFR 51.22(b), no environnental impact statement or environ-mental assessnent need be prepared in connection with the issuance of the amendment.
4.0 CONCLUSION
The staff has concluded, based on the considerations discussed above, that:
(1) there is reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed manner, and (2) such activities will be conducted in compliance with the Connission's regulations, and the issuance of the amendment will not be inimical to the comon defense and security or to the health and safety of the public.
Date: April 7, 1988 Principal Contributors:
M. Hartzman, EMEB/ DEST I
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