ML19317G843
| ML19317G843 | |
| Person / Time | |
|---|---|
| Site: | Rancho Seco |
| Issue date: | 01/06/1977 |
| From: | Reid R Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML19317G838 | List: |
| References | |
| NUDOCS 8004010670 | |
| Download: ML19317G843 (8) | |
Text
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t NUCLEAR REGULATORY COMMISSION 7
o WASHINGTON, D. C. 20666 5
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SACRAMENTO MUNICIPAL UTILITY DISTRICT DOCKET NO. 50-31?
g RANCHO SECO NUCLEAR GENERATING STATION AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 9 License No. DPR-54 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment by Sacramento Municipal Utility District (the licensee) dated October 6,1976, 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 confomity with the application, the provisions of the Act, and the rules and regulations of the Comission; C.
There is reasonable assurance (1) 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 Comission's regulations; t
D.
The issuance of this amendment will not 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 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.
j 1
l 8004010[
2-This license amendment is effective as of the date of its issuance.
3.
FOR THE NUCLEAR REGULATORY C0!HISSION d+ ' h l.'
Y Robert W. Reid, Chief Operating Reactors Branch #4 Division of Operating Reactors
Attachment:
Changes to the Technical Specifications Date of Issuance: January 6, 1977 a*
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' ATTACHMENT TO LICENSE AMENDMENT NO. 9 FACILITY OPERATING LICENSE NO. DPR-54, DOCKET NO. 50-312 Revise Appendix A as follows:
Remove Pages Insert Pages 3-51 4-47 4-47 4-47a 4-47b 4-47c 4-47d The new pages and changes on the revised page are shown by marginal lines.
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RANCl10 SECO UnlT I TECHNICAL SPECIFICATIONS Limiting Conditions for Operations SIIOCK SUPPRESSORS (SNUBBERS) 3.I2 Applicability This specification applies to the operability of safety sysicms' shock suppressors (snubbers) during power operation.
Obj ect ive To assure that safety related snubbers are operable to protect the nuclear system during seismic transients when the reactor is operating.
Specification 1.
During power operation all safety-related snubbers listed in Table 4.14-1 shall be operaole, except as noted in 3 12.2 through 3.12.4 below.
2.
If the requirements of 3.12.1 cannot be met, maintenance shall be allowed during power operation on any safety related snubber listed on Tabic 4.14-1.
If the snubber being repaired is not restored to operability or replaced within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />, the reactor shall be placed in a hot shutdo n condition within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
If operability or replacement is not accomplished wi thin an addi tional 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />, the reactor shall be placed in a cold shutdown condition within 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
3 If a snubber is determined to be inoperable while the reactor is in the cold r'iutdown, hot shutdown or refueling shutdown riode, the snubber shall be made operabic or replaced prior tu reactor startup.
4.
Snubbers may be added to safety related systems without prior URC License AmendmentstoTable4.14-1$rovided.that a revision to Tahic 4.14-1 is included with the subsequent License A.r.cndment request.
Bases Snubbers are designed to prevent unrestrained pipe cotton under dynamic loads as might occur during an carthquake or severe transient, while allowing normal thermal rotion during startup and shutdown. The consequence of an inoperabic snubber is an increase in the probability of structural damage to piping as a result of a seismic or other event ini tiating dynamic loads.
It is therefore required that all snubbers required to protect the primary coolant system or any other safety system or component be operable within a limited time interval during reactor operation.
3.r,1 Amendment No. 9
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RAf1Cli0_SECO UtilT' I
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. TECll!!! CAL SPECIFICATi0!!S S'urveillance Standards 4.14 SHOCK SUPPRESSORS -(SNUBBERS) 1 Appiicability.
1 The follusing surveillance requirements apply as applicable to hydraulic snubbers listed in Toble 4.lh-l.
Obj ec t i ve j.
To verify that ~the hydraulic snubbers will perform:their design function.
Specification
.l.
All hydraulic snubbers whose seal material has been demonstrated by operating experience, laboratory t esting or analy!.is' to be compatible with the operating environment shall be visually inspected.
This inspection shall include inspection of the hydraulic fluid reservoir level, fluid connections and linkage connections to the piping and anchor for integrity in accordance with the follouing schedule:
ilumber of Snubbers Found inoperable During Inspection flext f;equ i red Or During Ins getion Interval in pection Intc rva l 0
18 nonths + 25%
l 1
12 months _T 25%
2 6 months + 25%
3,4 4 conths T 25%
5,6,7 2 months T 25%
-8 1 month I 25t i
The required inspection interval shall not be lengthened raore than one step at a time.
Snubbers may be categorized in two groups, " accessible" or "inaccessibic" based on their accessibility for inspection during reactor operation.
These two groups may be inspected independently accordir.g'to the above schedule.
2.
All hydraulic snubbers whose seal materials are other than ethylenc 4
propylene or material that has been demonstratcJ to be compatible with the operating environment, shall be visually inspected for operability monthly.
3 The initial inspection shall be performed within 6 months from the date j.
of issuance of these specifications.
For the purpose of entering the schedule _in Sg'ecification 6.14.1, it shall be assumed that the facility had been on a 6 mont h inspect ion interval.
l Amendment No. 9 h.h]
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RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS Surveillance Standards 4.
Once each refueling cycle, a representative sample considering different brand makes, different radiation. evels, tempera-l tures, etc. of 10 hydraulic snubbers or approximately 10%
of the hydraulic snubbers, whichever is less, shall be functionally tested for operability including verification of proper piston movement, lock up and bleed. For each unit and subsequent unit found inoperab'le, an additional 10% or ten hydraulic snubbers shall be so tested until no more failures are found or all units have been tested.
However, if all failures are shown to be unique to one brand make, and the NRC concurs in writing with this determination before reactor restart, snubbers of other brand makes need not be tested during the follow-on tests.
Snubbers of rated capacity greater than 50,000 lbs. and snubbers designated in Table 4.14-1 as especially difficult to re=ove or in high radiation area during shutdown need not be functionally tested.
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BASES:
Hydraulic Snubbers 4
All safety related hydraulic snubbers are visually inspected for overall integrity and operability. The inspection will include verification of proper orientation, adequate hydraulic fluid Icvel and proper attachment of snubber to piping and structures.
The inspection frequency is based upon maintaining a constant level of snubber protection. Thus'the required inspection interval varies inversely with the observed snubber failures. The number of inoperable snubbers found during a required inspection determines the time interval for the next, rcquired inspection.
Inspections performed before that interval has elapsed noy be used as a new reference point to determine the next inspection.
However, the results of such carly inspections performed before the original required time interval has clapsed (nominal time less 25%) may not be used to lengthen the required inspcc-ticn interval. Any inspection whose results require a shorter inspection interval will override the previous schedule, j
Cxperience at operating facilities has shown that the required surveillance progra:n j
should assure an acceptable level of snubber performance provided that the seal l
notcrials are compatible with the operating environment.
Snubbers containing seal material which has not been demonstrated by operating experience, lab tests, or analysis to be conpatible with the operating environment should be inspected more f requently (cvery n:cnth) until material compatibility is confirmed or an appropriate changeout is completed.
i Amendment No. 9 4-47a
RANCHO SECO UNIT 1 TECHNICAL SPECITICATIONS Surveillance Standards Bases Examination of defective snubbers at reactor facilitics and material tests performed several laboratories have shown that millable gum polyurethane deteriorates atrapidly under the temperature and moisture conditions present in many snubber locations. Although molded polyurethanc exhibits greater resistance to these conditions, it also may be unsuitable for application in the higher temperature environments. Data are not currently available to precisely define an upper temperature limit for the molded polyurethane.
Lab tests and in-plant experience indicate that scal materials are availabic, primarily cthylene propylene compounds, which should give satisfactory performance under the most severe conditions expected in reactor installations.
To further increase the assurance of snubber reliability, functional tests should be performsa once cach refueling cycle. These tests will include stroking of the snubbers to verify proper piston movement, lock-up and biced. Ten percent or ten snubbers, whichever is less, represents an adequate sample for such tests.
Observed failures on these samples should require testing of additional units.
The intent is to test all snubbers an equal number of times. Those snubbers that have a rated capacity of greater than 50,000 lbs. and snubbers designated in Table 4.14-1 as being in high radiation areas or especially difficult to remove need not be selected for functional tests provided operability was previously verified.
9 6
4-47b Amendment No.
9
RANCll0 SECO UllT l
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TCCHillCAL SPECIFICATIONS surveillance standards
-TABLE 4.14-1 snubbers Accessibic During Power Operations List No.
l. D. 110.
List No.
1.0. flo.
1 xx Ms 20528 sw 1 30 xx 4 sw 20024-3A 2 xx Ms.20521 SV 11 31 xx 4 SW 26101-2 3x MS 20520 SV 3 32 xx 4 Sw 26101-6 4A MS 20521 sw 13 33 xx 4 SW 25023-5A 34 xx 4 su 26101-8A 5 xx Ms 20520 su 5 6x MS 20521 SW 14 35 xx 4 su 25023-8A
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7x Ms 20520 SV 13A 36 xx 4 SW 26100-3 8x MS 20520 su 6 37 xx 4 sw 26100-1A 9 xx Hs 20526 sv 9 38 x 4 SV 26022-13A 10 xx 9 SW 30709-3A 39 xx 4 sw 26025-43 11 xx 9 SW 30708-4 40 x 4 sw 23620-3A 12 xx 9 sw 30708-5A 41 xx 4 su 53520-3 13 xx 9 SV 39709-4 42 xx 4 SW 29101-IA 14 xx 9 SV 30709-3 101 xxx MS 20520 sw 19 15 xx 5 su 20530-7A 102 xxx MS 20521 SW 20 16 xx 5 sV 20529-3A 103 xxx MS 20521 su 22 17 x 5 sV 53520-3 104 xxx Ms 20520 SV 21 18 xx 5 sw 32141-1A 105 xx 10 sw 20553-1A 19 x 5 su 32141-2 106 xx 5 sV 20529-1A 20 x 10 SW 20530-3A 107 xx 5 su 20529-4A 21 xx 12 su 20530-3A 108 xx 5 su 20530-8 22 x 7 SV 32120-1B 109 xx 7 sw 30800-6 23 xx 7 SW 32120-1A 110 xx 7 sv 30800-8 24 xx 7 SV 32120-Ic 111 x 7 su 30800-12 25 xx Ms 20550 sw 1 112 xx 7 sw 30600-14 26 xx Ms 20558 su i 113 xx 7 sw 30804-1 27 xx Ms 20532 SV 1 114 xx 7 sw 30805 28 xx MS 20531 SW I -
115 xx 5 sw 23803-4A 29 x 7 sw 32140-2 116 xx 4 su 60014-4A Modifications to this table due to changes in high radiation areas should be submitted to the NRC as part of the next license amendment.
x Designates snubbers difficult to remove or in a high radiation area during shutdown Ax specification 4.14.4 applies to these snubbers for locl.up testing xxx Exempt due to a rated capacity af greater than 50,000 lbs.
Amendment No.
9 4-47c
RANCHO SECO UNIT I TECilNICAL SPECITICATIONS Surveillance Standards TABLE 4.14-1 Snubbers inaccessible During Power Operations List !!o.
l.D.'No.
List No.
l.D. No.
P5 xx I SV 10' B&W-5 125 xx 1 SV 21021-3 P6 x 1 SV 10 B&V-6 126 xx 1 SV 23823-7A P7 x
! SV 10" B&V-7 127 xx 1 SV 21025-9A 50 x 1 SV 20025-3 128 xx 1 SV 21005-8 51 x 1 SV 20025-1A 129 xx 1 SV 23822-7B 52 xx 1 SV 26020-5A 130 xx 1 SV 21028-2 53 xx
! SV 26524-4A 131 x 1 SV 26020-6A 54 xx 1 SV 50060-8A 132 xx 1 SV 20082-12A 55 xx 1 SV 22000-9 133 xx 1 SV 26521-2A 56 xx 1 SV 26021-5A 134 x 1 SV 21025-6 57 xx 1 SV 26021-7A 135 x
'l SV 23823-13A 58 xx 1 SV 26021-11A 136 xx 1 SV 21501-20 59 xx 1 SV 50063-2A 137 xx I SV 21501-28 60 xx 1 SV 23823-8 138 xx i SV 50050-6A 61 x 1 SV 23620-15A SS-1 xxx SS-1 62 x 1 SV 23625-3A 55-2 xxx SS-2 63 x 1 SV 29122-28A SS-3 xxx SS-3 64 xx 1 SV 29125-7A S5-4 xxx 55-4 65 x 1 SV 29125-7C 55-5 xxx 55-5 66 xx MS 20523 SV2 SS-6 xxx 55-6 67 xx HS 20521 SW17 55-7 xxx SS-7 68 xx 1 SV 21925-9A 55-8 xxx SS-8 69 xx 1 SV 50050-2A SS-9 xxx SS-9 70 xx MS 20520 SV 18 55-10 xxx 55-10 71 xx HS 20522 SW2 55-11 xxx 55-11 72 xx 1 SV 50060-3A SS-12 xxx 55-12 73 xx 1 SV 32140-4 SS-13 xxx SS-13 74 xx 1 SV 32140-2
- _ 55-14 xxx SS-14 75 xx 1 SV 32141-4 55-15 x 55-15 76 xx 1 SV 32141-2 SS-16 xxx SS-16 77 xx 1 SV 50053-2A SS-17 x SS-17 117 xx 1 SV 22000-12 55-18 xxx SS-18 118 xx 1 SV 22000-2A SS-19 xxx SS-19 119 xx 1 SV 22001-2 SS-20 xxx 55-20 120 x 1 SW 21007-7 SS-21 xxx SS-21 121 x 1 SV 21022-5 SS-22 x SS-22 122 xx 1 SW 21006-6A SS-23 xxx 55-23 123 xx 1 SV 23626-1A 55-24 xxx 55-24 124 xx 1 SV 21022-1 x Designates snubbers dif ficult to remove or in a high radiat ion area during shutdown xx Specification 4.14.4 applies to these snubbers for lockup testing xxx Exempt due to a rated capacity of greater than 50,000 lbs.
Modifications to this table due to changes in high radiation areas should be submitted to the NRC as part of the next license amendment.
Amendmenc No. 9 4-47d