ML20073K922
| ML20073K922 | |
| Person / Time | |
|---|---|
| Site: | Surry  |
| Issue date: | 05/01/1991 |
| From: | Berkow H Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20073K927 | List: |
| References | |
| GL-90-09, GL-90-9, NUDOCS 9105130143 | |
| Download: ML20073K922 (14) | |
Text
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UNITED STATES
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NUCLEAR REGULATORY COMMISSION
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WASHING TON, D. C. 20S55
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VIRGINIA ELECTRIC AND POWER COMPANY DOCKET NO. 50-280 SURRY POWER STATION, UNIT NO. 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.156 License No. DPR-32 1.
The Nuclear Regulatory Commission (the Comission) has found that:
A.
The application for amendment by Virginia Electric and Power Company (the licensee) dated January 31, 1991, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Commission's rules and regulations set forth in 10 CFR Chapter I; B.
The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C.
There is reasonable assurance (i) that the activities authorized by this amendment can he conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; D.
The issuance of this amendment will not be inimical to the common 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 Commission's regulations and all applicable requirements have been satisfied.
2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 3.B of Facility Operating License No. DPR-32 is hereby amended to read as follows:
9105130143 010501 PDP ADOCK 05000280 p
! (B) Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No.156, are hereby incorporated in the license.
The licensee shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment is effective as of the date of its issuance.
FOR THE NUCLEAR REGULATORY COMMISSION He bert N. Berkow, Director Project Directorate 11-2 Division of Reactor Projects - 1/11 Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance: May 01, 1991
((p %,)o, UNITED STATES 3
g' NUCLEAR REGULATORY COMMISSION 1 ;
WASHINGTON. D. C. 20555
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VIRGINTA ELECTRIC AND POWER COMPANY DOCKET NO. 50-281 SURRY POWER STATION, UNIT N0. 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 155 License No. DPR-37 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Virginia Electric and Power Company (the licensee) dated January 31, 1991, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Commission's rules and regulations set forth in 10 CFR Chapter I; B.
The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; 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, and (ii) that such activities will be conducted in compliance with the Commission's regulations; D.
The issuance of this amendment will not be inimical to the common 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 Commission's regulations and all applicable requirements have been satisfied.
2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 3.B of Facility Operating License No. DPR-37 is hereby amended to read as follows:
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2 (B) Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 155, are hereby incorporated in the license.
The licensee shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment is effective as of the date of its issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
' B6rbert N. Berkow, Director Project Directorate 11-2 Division of Reactor Projects - 1/11 Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance: May 01, 1991 i
ATTACHMENT TO LICENSE AMENDMENT AMENDMENT NO. 156 FACILITY OPERATING LICENSE NO. DPR-32 AMENDMENT NO. 155 FACILITY OPERATING LICENSE NO. DPR-37 DOCKET NOS. 50-280 AND 50-281 P
Revise Appendix A as follows:
Remove Pages Insert Pages TS 4.17-1 TS 4.17-1 TS 4.17-2 TS 4.17-2 TS 4.17-3 TS 4.17-3 TS 4.17-4 TS 4.17-4 TS 4.17-5 TS 4.17-5 TS 4.17-6 TS 4.17-6 TS 4.17-7 TS 4-17-7 TS 4.17-8 TS 4-17-8 TS 4.17-9 TS 4.17-9 l
1
i TS 4.17-1 4.17 SHOCK SUPPRESSORS (SNUBBERS)
Aceficability Applies to all hydraulic and mechanical shock suppressors (snubbers) which are required to protect the reactor coolant system and other safety related systems. Snubh9rs excluded from this inspection are those installed on non-safety related sistems and then only if their failure or failure of the system on which they are installed would have no adverse effect on any safety related system.
Obiective To specify the minimum frequency and type of surveillance to be applied to the hydraulic and mechanical snubbers required to protect the reactor coolant system and other safety-related systems.
Soecification Each snubber shall be demonstrated operable by performance of the following augmented inservice inspection program and the requirements of Specification 4.0.3. As used in this specification, " type of snubber" shall mean snubbers of the same design and manufacturer, irrespective of capacity.
A.
Visual Insoections 1.
Snubbers are categorized as inaccessible or accessible during
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reactor operation. Each of these categories (inaccessible and accessible) may be inspected independently according to the schedule determined by Table 4.17-1.
The visual inspection interval of each type of snubber shall be determined based upon the criteria provided in Table 4.171.
Amendment Nos. 156 and 155
I TS 4.17 2 i
a B.
Visual Insoection Acceotance Criteria 1.
Visual inspections shall verify that:
a.
the snubber has c.o visible indications of damage or' impaired operability, l
b.
attachments to the foundation or supporting structure are functional, fasteners' for the attachment of the snubber to the c.
component and to the snubber anchorage are functional,.
and d.
in those _ locations where snubber movement can be l
manually induced without disconnecting the snubber, that the snubber has freedom of movement and is not frozen up.
2.
Snubbers which appear inoperable as a result of visual inspections shall be classified as unacceptable and may be reclassified acceptable for the purpose of establishing the next visual inspection interval, provided that; the-cause of the rejection is clearly established and:
a.
remedied for that particular snubber and for other snubbers irrespective of type that may be generically susceptible, and b.
the affected snubber is functionally tested in the as found -
' condition and determined CPERABLE per Specification.
4.17.D or E.
T-When hydraulic snubbers which have uncovered fluid ports are
. tested for. operability, the test shall be performed by starting with--
the piston at the as-found setting and extending the piston rod in the tension mode direction.-
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1 3.
All snubbers found connected to an inoperable common hydraulic l
fluid reservoir shall be counted as unacceptable for determining the next inspection interval, s
Amendment Nos. 156 and 155
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TS 4.17 3 l
4.
A review and evaluation shall be performed and documented to it justify continued operation with an unacceptable snubber, continued operation cannot be justified, the snubber shall be declared inoperable and the action requirements of Specification 3.20 shall be met.
C.
Functional Tests At least once per 18 months during shutdown, a representative 1.
sample of 10% of the total of each type of snubber used in the plant sha!! be functionally tested either in place or in a bench test.
2.
The representative sample selected for functional testing shalt include the various configurations, operating environments and the range of size and capacity of snubbers, This representative sample shall not, to the extent practicable, include those snubbers tested in a previous representative sample.
3.
At least 25% of the snubbers in the representative sample shall include snubbers from the following three categories; the first snubber away from each reactor vessel nozzle.
l a,
b.
snubbers within 5 feet of heavy equipment (valve, pump, turbine, motor, etc), and snubbers within 10 feet of the discharge from a safety relief c.
valve.
l Amendment Nos. 156 and 155
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TS 4.17-4 I
4.
Snubbers identified as *Especially Difficult to Remove" or in *High Radiation Zone During Shutdown" shall also be included in the representative sample.'
In addition to the regular sample, snubbers which iailed the 5.
previous functional test shall be retested during the next test period. If a spare snubber has been installed in place of a failed snubber, then both the f ailed snubber (if it is repaired and installed in another position) and the spare snubber shall be retested. Test results of these snubbers may not be included for the resampling.
6.
For each snubber that does not meet the functional acceptance criteria of Specification 4.17.D or 4.17.E, an additional 10% of that type of snubber shall be functionally tested.
For snubbers of 50 kips and above that are extremely difficult to 7.
remove or in high radiation zones that fail the functional testing, an engineering evaluation is required to determine the failure mode.
If the f ailure is determined to be non generi0, an additional 10% of that category will be tested during the next functional test period.
If any snubber selected for functional testing either fails to lockup 8.
or fails to move,i.e., frozen in place, the cause will be evaluated and if caused by manufacturer or design deficiency all snubbers of the same design subject to the same defect shat! be functionally tested. This testing requirement shall be independent of the requirements stated above for snubbers not meeting the functional test acceptance criteria.
Permanent or other exemptions from functional testing for individual snubbers in these categories may be granted by the Commission only if a justifiable basis for exemption is presented and/or snubber life destructive testing was performed to qualify snubber operability for all design conditions at either the completion of their fabrication or at a subsequent date.
l Amendment Nos. 156 and 155
TS 4.17 5 9.
For the snubber (s) found inoperable, an engineering evaluation shall be performed on the components which are supported by snuboer(s). The purpose of this engineering evaluation shall be to determine 11 the components supported by the snubber (s) were adversely affected by the inoperability of the snubber (s)in order to ensure that the supported component remains capable of meeting the designed service.
D, tiydraulic Snubbers Functional Test Acceotance Criteria 1.
The hydraulic snubber functional test shall verify that:
Activation (restraining action) is achieved within the a.
specified range of velocity or acceleration in both tension and compression.
b.
Snubber bleed, or release rate, where required, is within
'ne specified range in compression and tension.
For snubbers specifically required to not displace under continuous load, the ability of the snubber to withstand load without displacement shall be verified.
E.
Mechanical Snubbers Functional Test Accentance Criteria 1.
The mechanical snubbers functional test shall verify that; The force that initiates free movement of the snubber rod in a.
either tension or compression is less than the specified maximum drag force. Drag force shall not have increased more than 50% since the last functional test, b.
Activation (restraining action) is achieved within the specified range of velocity in both tension and compression, Amendment Nos.156 and 155
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TS 4.17 6 e
Snubber release rate, where required, is within the c.
specified range in compression and tension. For snubbers specifically required not to displace under continuous load, the ability of the snubber to withstand load without displacement shall be verified.
F.
Snubber Service 1.iie Monitofing A record of the service life of each snubber, the date at which the 1.
designated service life commences, and the installation and maintenance records on which the designated service life is based shall be rnaintained as required by Specification 6.5.B.9.
Concurrent with the first inser/ ice viscal inspection and at least 2.
once per 18 months thereafter, the installation and malatenance records for each snubber shall be reviewed to verify that the indicated service life has not been exceeded or w01 not be exceeded prior to the next scheduled snubber service life review.
If the indicated service life will be exceeded prior to the next L
scheduled snubber service life review, the snubber service life shall be reevaluated or the snubber shall be replaced or reconditioned so as to extend its service life beyond the date of the l
next scheduled service life review. This reevaluation, replacement j
or reconditioning shall be indicated in the records.
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l Amendment Nos. 156 and 155
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TS 4.17-7 I
Bases All snubbers are required operable to ensure that the structuralintegrity of the reactor coolant system and all other safety related systems is maintained during and following a seismic or other event initiating dynamic loads. Snubbers excluded from this inspection program are those installed on non-safety related l systems and then only if their failure or failure of the system on which they are installed would have no adverse effect on any safety related system.
The visual inspection frequency is based upon maintaining a constant level of snubber protection to systems. Therefore, the required inspection interval varies inversely with the observed snubber failures and is determined by the number of inoperable snubbers found during an inspection.
Inspections performed before that interval has elapsed may be used as a new reference point to determine the next inspection. However, the results of such early inspections performed before the original required time interval has elapsed
.(nominal time less 25%) may not be used to lengthen the required inspection interval. Any inspection whose results require a shorter inspection interval will override the previous schedule.
When the cause of the rejection of a snubber is ciearly established and remedied for that snubber and for any other snubbers that may be generically susceptible, and verified by inservice functional testing, that snubber may be exempted from being counted as inoperable. Generically susceptible snubbers are those which are of a specific make or model and have the same design features directly related to rejection of the snubber by visual inspection, or are similarly located or exposed to the same environmental conditions such as temperature, radiation, and vibration.
t When a snubber is found inoperable, an engineering evaluation is performed, in addition to the determination of the snubber mode of failure, in order to determine if any safety related component or system has been adversely affected by the inoperability of the snubber. The engineering evaluation shall determine whether or not the snubber mode of failure has imparted a significant effect or degradation on the supported component or system.
Amendment Nos. 156 and 155 l
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TS 4.17 8 l
To provide assurance of snubber functional reliability, a representative sampic of the installed snubbers will be functionally tested during plant shutdowns at 18 month intervals. Functional testing is to be in accordance with ASME Section XI l
1980 Ed., Subsection IWF. Observed failures of these sample snubbers shall require functional testing of additional units.
Hydraulic snubbers and mechanical snubbers may each be treated as a different entity for the above surveillance programs.
The service life of a snubber is evaluated via manufacturer input and information through consideration of the snubber service conditions and associated installation and maintenance records (newly installed snubber, seal replaced, spring replaced, in high radiation area, in high temperature area, etc..
.). The requirement to monitor the snubber service life is included to ensure that the snubbers periodically undergo a performance evaluation in view of their age and operating conditions. These records will provide statistical bases for future consideration of snubber service life. The requirements for the maintenance of records and the snubber service life review are not intended to affect plant operation.
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Amendment flos.156 and 155
I TS 4.17 9 TABLE 4.171 SNUBBER VISUAL INSPECTION INTERVAL NUMBER OF UNACCEPTABLE SNUDDERS Population Column A Column B Column C or Category Extend Interval Repeat Interval Reduce Interval (Notes 1 arc 2)
(Notes 3 ard 6)
(Notes 4 ard 6)
(Notes 5 ard n 1
0 0
1 80 0
0 2
100 0
1 4
150 0
3 8
200 2
5 13 300 5
12 25 400 8
18 36 500 12 24 48 750 20 40 78 1000 or greater 29 56 109
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The next visualinspection interval for a snubber population or category size shall be determined Note 1:
based upon the previous inspection interval and the number of unacceptable snubbers found during that interval. Snubbers are categorized, based upon their accessibility during power operation. as accessible or inaccessible. These categories may be examined separately or jointly. However, the beensee must make and document that decision before any inspection and shall use that decision as the basis upon which to determine the next inspection interval for that category.
'nterpolation between population or category sizes and the number of unacceptable snubbers Note 2:
is permissible. Use next lower inteDer for the value of the limit for Columns A, D, of C if that integer includes a tractional value of unacceptable snubbers as determined by interpolation.
If the number of unacceptable snubbers is equal to or less than the number in Column A, the I
Note 3:
l next inspection interval may be twice the previous interval but not greater than 48 months.
If the number of unacceptable snubbers is equal to or less than the number in Column B. but i
l Note 4:
greater than the number in Column A, the next inspection interval shall be the same as the previous interval
!! the number of unacceptable snubbers is equal to or greater than the number in Column C, the l
Note 5:
next inspection interval shall be two thirds of the previour interval. However, if the number of Unacceptable snubbers is less than the number in Column C. but greater than the number in i
l Column D, the next interval shall be reduced proportionally by interpolation, that is, the previous l
interval shall be reduceo by a factor that is one third of the ratio of the ditierence between the number of unacceptable snubbers tound during the previous interval and the number in Column B to the difference in the numbers in Columns B and C.
The provisions of Specification 4.0.2 are applicable for all inspection intervals up to and Note 6:
in:luding 48 months.
Amendment Nos.156 and 155
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