ML19331E164
| ML19331E164 | |
| Person / Time | |
|---|---|
| Site: | Rancho Seco |
| Issue date: | 08/23/1977 |
| From: | Reid R Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML19331E165 | List: |
| References | |
| NUDOCS 8009080671 | |
| Download: ML19331E164 (15) | |
Text
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THIS DOCUMEsT'CONTAINS POOR QUAUTY PAGES UNITED STATES
/
- >g NUCLEAR REGULATORY COMMISSION J"
4 WASHINGTON. D. C. 20506
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,o SACRAMENTO MUNICIPAL UTILITY DISTRICT DOCKET NO. 50-312 RANCHO SECO NUCLEAR GENERATING STATION AMENDMENT TO FACILITY OPERATING LICENSE Amendnent No.13 License No. DPR-54 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The applicatioi for amendment by hacramento Municipal Utility District (the licensee) dated l4ovember 26, 1976, as revised June 21,1977, complies with the standards and requirements of the Atomic 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 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 (11) that such activities will be conducted in compliance with the Comission's regulations; D.
The issuance of this amendment will not be inimical to the coneson defense and security or to the health and safety of the public; and E.
The 1 nuance of this amendment is in accordance with 10 CPR Part 51 of the Comission's regulations and all applicable mquirements have been satisfied.
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- Accordingly, the license is amended by changes to the Technic Specifications as indicated in the attachment to 2.
No. DPR-54 is hereby amended to read as follows:
(2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No.13, are The licensee hereby incorporated in the license.shall operate the fac Technical Specifications.
This license amendment is effective as of the date of its 3.
issuance.
FOR THE NUCLEAR REGULATORY C0f9
, $4 ^kI Robert W. Reid, Chief Operating Reactors Branch f4 Division of Operating Reactors
Attachment:
Changes to the Technical Specifications Date of Issuance:
August 23, 1977 O
ca ATTACHMENT TO LICENSE AMENDMENT NO. 13 FACILITY OPERATING LICENSE NO. DPR-54 DOCKET NO. 50-312 4
Revise Appendix A as follows:
Remove Pages insert Pages 3-13 3-13 3-13a 3-14 3-14 3-14a 3-14a 4 4-50 4 4-57 New pages and changes on the revised pages are shown by marginal lines.
Page 3-14 is unchanged and is included for convenience only.
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4 RANCHO SCCO UNIT I TECHNICAL SPECIFICATIONS Limiting Conditions for Operation 3.1.6.9 Primary-to-secondary leakage through the steam generator tubes shall. be limited to I GPM total for all steam generators. With any steam generator tube leakage greater than 1 GPM, reduce leakage to less than i GPM; or bring the reactor to cold shutdown conditions within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />.
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3.1.6.10 if reactor shytdown is required due to Section 3.1.6.9,' restore the inoperabic gcnerator(s) to operable status by plugging the leaking tubes prior to i.ncreasing the average temperature above 200 F.
I Baset l
Every reasonabic e." fort will be made to reduce reactor coolant 1cakage in-cluding evapo ative losses (which.may be on the order of 0.5 gpm) to the louest possible rate and at least below I gpm in order to prevent a large I
leak f rom nasking the presence of a smaller leak. Evapora tive' losses identified during stcetup testing of 0.5 gpm are not considered part of
.the.1 gpm unidentified leakage. Water inventory balances, radiation l
monitoring equipment, boric acid crystalline deposits, and physical in-
,spections can disclose reactor coolant leaks. Any leak of radioactive l
fluid, whether from the reactor coolant system primary boundary or not can be a serious problew with respect to in-plant radioactivity contamina-tien and cleannp or it could develop into a still more serious problem; therefore, first indications of such leakage will be followed up as soon as pract i, cable.
Altheegh some leak rates on the order of gpm may be tolerable from a dose point of vice, especially if they are to closed systems, it must
- be recogni zed thot leaks in the order of drops per minute through any of the ualls of'the primary system could be_ indicative of materials l
failure such as by stress ' corrosion cracking.
If depressurization, j
isolation am!/or other. safety neasures are not taken promptly, these I
small breaks could develop ~into much larger leaks, possibly into a gross. pipe rnp ore. Therefore, the nature of the leak, as well as j
the rugnitude of the leakaoc riust be considered in the safety evaluatio'n.
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I Amendment No. 13 j
3-13
O RANCil0 SECO UNIT I TECHNICAL SPECIFICATIONS Limiting Conditions for Operation Bases (continued)
When the source of leakage has been identified, the situation can be evaluated to determine if operation can safely continue. This evaluation will be performed by the Operating Staf f and will be documented in wri ting and approved by the Superintendent. Under these conditions, an allowable reactor coolant system leakage rate of 10 gpm has been established. This explained leakage rate of 10 gpm is also well within the capacity of one high pressure injection pump and makeup would be available even under the loss of off-site power condition.
If Icahage is to the Reactor Building it may be identified by one or more of the following methods:
A.
Sumn Levels - All Reactor Building leakage is collected in the I;eactor Building sumps.
These sumps drain by gravity in.c a 120 gallen Reactor Building drain accumu-lation tank. The drain accumulation tank is used to measure the drain flow with level indicators at 20 gallons and 120 gallens. The tank is dumped into the East decay heat.cmoval pump room sump. The f requency of dum' ping the accumulation tank and time interval between levels are recorded'in the Control Room and are direct measures of the flow rate.
Depending on the level at which the tank is dumped, the tinie to confirm.a 1 gpm leak is between 40 minutes and 120 minutes.
Amendment No.
13-3-13 a
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RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS Limiting Conditions for Operation Frequency of operation of the East DHR pump
- room sump pumps is recorded in the control room to provide verification of proper operation of the Reactor Building draic accumulation tank.
Since the Reactor Building drain system collects drainage from 1
all components in the Reactor Building. 4 change in drain flow 7
does not necessarily indicate a reae'.or coolant system leak.
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One method available for determining if the additional drain flow is reactor coolant is to collect drainage in the drain accumulation tank, draw a sample from the tank, and analyse the l
sample for boric acid concentration and radioactivity.
B.
Radioactivity - Changes in the reactor coolant leakage rate in~the Reactor Building may cause changes in the control room indication of the Reactor Building atmosphere particulate and gas radioactivi-ties and of the Reactor Building radiation monitors.
The response time for the radiation monitors to detect a given leak rate are dependent on the coolant activity level and the minimum detector sensitivity.
For a leak rate of 1 Apm, the followins gaseous radiation monitor i
response times were calculated:
Coolant Activity Response. Time 1% defective fuel 67 seconds 0.1% defective fuel 5.3 minutes The airborne particulate radiation monitor response time is dependent upon the speed of filter paper advance which, during j
normal operation, will be the slow speed. Thus, assuming either l
0.1 percent defective fuel and a 1 gym leak or expected corro-sion product activity and a 1 gym leak, the response time will be about 1 to 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />. This time period is associated with filter tape movement from the point of particle deposition to the detector. If leakage is indicated by another leak detection method, the filter paper can be manually advanced to verify that a substantial leak has occurred. By stopping the filter tape advance mechanism, an integrated sample can be taken over a short period of time (e.g. 5 minutes) for a quick evaluation of i
the situation.
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1-RANCHO.SECO UNIT 1 TECHNI CAL SPECIFICATIONS Response Time Excluding Filter Coolant Activity Advance 1% defective fuel 40 seconds 0.1% defective fuel 41 seconds No defective fuel, corrosion products only 18 minutes
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C.
Reactor Ccolant' inventory - Total reactor coolant system leakage
. rate is periodically determined by comparing indications of reactor power, coolant temperature, pressurizer water level and makeup tank level over'a time interval. -All of these indications are recorded.
Since the pressurizer level is maintained essentially constant by the pressurizer level-controller, any coctent lcahage is replaced by coolant fron the makeup tank resulting in a tank level decreasc.
The makeup tank capacity is 31 gallons per inch of height and each graduation on the level recorder represe5ts'I inch of tank height.
This inventory monitoring method is capable of detecting changes on the order of 31 gallons. A 1 gpm leak would therefore be detectable within approximately one-half hour.
As describcd above, in addition to direct observation, the means of detecting reactor coolant leakage are based on two different princi-pies, i.e., activity and sump level and reactor coolant inventory measurementc. Two systems of di f ferent principles provide, there-fore, diversified wa/ i of detecting leakage to the reactor building.
The urper 11mit' of 30 gpm is based on the contingency of a complete loss of plant power. A 30_ gpm loss of water in conjunction with a complete loss of plant power and subsequent cooldown of the reactor coolant system by the, r
turbine bypass' system (set at 1,040 psia) and steam driven cmergency feed-water pump uould require core than 60 minutes to empty the pressurizer from the combined effect of system leakage and contraction. This will be ample time to restore electrical power to the plant and makeup flow to the reactor coolant system.
The plant is expected to be operated in a manner such that the secondary coolant will be normally maintained within those chemistry limits found to result in negligibic corrosion of the steam generator tubes.
If the secondary coolant chenistry is consistently not maintained within these chemistry' limits, over some period of time localized corrosion could occur and might result in stress corrosion cracking. The; extent of cracking during ~ plant operation would be limited by thc. limitation of steam generator tube leakage between the priraary. ccolant systc.n and th: secondary coolant system (primary-to-secondary.leaka;c u 1 GPM).
Cracks having a primary-to-secondary leakage less than this limit during nperation will have an adequate margin of safety to withstand the loads f rposed during nornal operatien and by postulated accidents. : Operating piants have demonstrated that primary-to-secondary leahr;c of IJ CfM car. be detected by monitoring thc sc:cadary coolant.
leakage in excess of this limit will require plant shutdown during which the lcaking tubes will be located and plugged.
Amendment No.
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PAGES 4 4-50 ARE RESERVED FOR SECTION 4.16 l
Amendment No. 13 4 48 50
w RANCHO SECO UtilT I l
TECHNICAL SPECIFICATIONS Surveillance Standards 4.17 STEAM CENFRATORS 4
Appilcability Applies to inservice inspection of the steam generator tubes.
i Obicctive To verify the operability of each steam generator and ensure the structural integrity of the tubes as part of the reactor coolar.t boundary.
Specificatinn Each steam generator shall be demonstrated OPERABLE by perfor ni.nce of the following augmented inservice inspection program and the requiren:ents of Speci ficat ion 1.3 4.17.1 Stean Generator Sar.ple Selection and inspection Each steam generator shall be determined OPERABLE during shutde.in by selecting and inspecting stcara generators as specified in Table 4.17-l.
4.17.2 Steam Cencrator Tube Sample Selection and Inspection The steam generator tube minimum sample size, inspection resul t classi fication, and the corresponding action requi red shall be as specified in Table 4.17-2, The inservice inspec-tion cf s team generator tubes shall Le performed at the frcquencies speci fied in Specification 4.17-3 and the inspected tubes shall be verified acceptable per the accep-tance criteria of Specification 2.17.4.
The tubes selected for these inspections shall include at least 3% of the total nuaber of tobcs in both stcam generators and be selected on a random basis except:
a.
If experience in similar plants with similar water cheialstry indicates critical areas to be inspected, then at least 50% of the tubes inspected shall be from these critical areas.
13
~ Amendment No.
4-51 i_
RANClic SECO UNIT I TECilNICAl. SPLCIFICAll0NS Surveillance Standards 4.17.2 (continued) b.
The first sample inspection during inservice inspection (sub-sequent to the first inservice inspection) of each steam generator shall include:
1.
All nonplugged tubes that previously had detectable wall penetratinns (>20%), and 2.
Tubes in those areas where experience has indicated poten-tial problems.
The second and third sampic inspections during cach inservice c.
inspection nmy be less than a full tube inspection by concentrating
(.electinq nt least 50% of the tubes to bc inspected) the inspec-tion on those areas of the tube sheet array and on those portions of the tubes where tubes :,ich imperfections were previously found.
d.
A tube inspection (pursuant to Specification 4.17.4.5) shall be per-formed on each selected tube.
If any selected tube does not permit the passage of the eddy current probe for a tube inspection, this shall be recorded and an adjacent tube shall be selected and subjected to a tube inspection (" Adjacent" is interpreted to 'sean the nearest tube capable of being inspected.) Tubes which do not permit passage of the eddy current probe will be censidered as degraded tubes when classifying inspection results.
The results of cach sample inspection shall be classified into one 5
of the following three categories:
Ca t e qp_ry, inspection Results C-1 Less then 5% of the total tubes ins ected are degradco tubes and none of the inspectcd tubes are defective.
C-2 One or more tubes, but not more than 1% of the total tubes inspected are defective, or between 5% and 10% of the total tubes inspected are de-graded tubes.
C-3 More than 10% of the total tubes inspected are degraded tubes or more than 1% of the inspected tubes are defective, thite:
In all inspections, previously degraded tubes mus t c>.fii h i t signi fican t (>101) further wall penetrations to 1.c includt.d in the above percentage' calculations.
1,17,3
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ic etirrel irh.e rvi ce insec< t ien of s team generator tubes
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. m pec t i..n hall be perf ormed during the j
fit : si 'o 1 i n ti eut e.
5itne.:uent i ns e r v i c.c Inspections shall I.e p. r l o n. d.: t inter vals of not less than I? nor more than 24 l
Amendment No. 13 4 52
4.17.3 Inspection Frequencies (Continued) calendar months af ter the previous inspection.
If two consecu-tive inspections following service result in all inspection results falling into the C-1 category or if two consecutive inspections demonstrate that previously observed degradation has not continued and no significant additional degradation
-has occurred, the inspection interval may be e,xtended to a maximum of once per 40 months.
b.
If the results of thc' Inservice inspection of a steam generator conducted in accordance with Table 4.17-2 at 40-month intervals falls in Category C-3, the inspection trcquency shall be increased to at 1 cast once per 20 months.
The increase in inspection frequency shall apply until a subsequent inspection meets the conditions specified in 4.17.3a and the interval can he extended to a 40-month period.
c.
Additional, unscheduled Inservice inspections shall be per-formed on each steam generator in accordance with the first sample inspection specified in Table 4.17-2 during the shut-down subsequent to any of the following conditions:
- l. ' Primary-to-tecondary tube leaks (not including leaks originating from tube-to-tube sheet welds) in excess of the limits if Specification 3.10, 2-A seismic occurrence greater than the Operating Basis Earthquake, 3
A loss-of-coolant accident requiring automatic actuation of the engineered safeguards, or 4.
A main steam line or feedwa er line brea as defined in tFc FSAR.
4.17.h Acceptence Criteria a.
As used in this Specification:
1.
leperfection means an exception to the dimensions, finish or contour of a tube from that required by fabrication drcuings or. sreci fications. Eddy-current testing Indi-cotions of less than 200 of the nominal tube wsil thick-nuss, if detcetable, may be considered as imperfections.
2.
Decradation econs a service-induced cracking, wastage, wear or general corrosien occurring on either inside or outside of a tube.
_.. _. 1 Amendmeac No. 13 4
4.17.4 Acceptance Criteria 3
,Dearaded Tube _ means a tube containing imperfections }20%
of the nominal wall thickness caused by degradation.
4.
Defective Tuba means a tube containing an imperfection
_40% of the nonimal tube wall thickness unimes higher limits are shown acceptable by analysis. Defective tubes shall be plugged.
5 Tube inspection means an inspection of the steam generator Lebe f rom the point of entry completely to the point of exit (except as noted in 4.17.2c).
b.
The steam generator shall be determined OPERABLE after completing the carresponding actions required by Table 4.17-2.
4.17.5 Report s Folliaing each inservice inspection of steam generator tubes, the a.
nur.iher of tubes plugqcd in cach steam generator shall be reported to the CommiM ion within 15 days.
b.
'lhe results of the steam generator tube Inservice inspection shall be included in the Annual Operating Report for the' period in uhtch this inspection was completed. This report shall include:
1.
t!un.ber and extent of tubes inspected.
2.
i.ocation and percent of wall-thickness penetratior. for ecc.h indicalinn of an imperfection.
3 Identification of tubes plugged.
c.
Re< ul ts of steam generator tube inspections which fall into l
Category C-3 and require notification of the Commission shalI t.e reported pursuant to Spect fIcation 6.9 prior to re an+t inn of plant operation. The written followup oT this report. hall provide a description of Invcettgations conducted to e reemine cau e of the tulie degradation and corrective n a?.o ret. tchen to prevent recurrence.
Ba+.es W Sniveill.inie f.. qu i s e wn t - for inr.pection of the stt am generator tubes ensure l
t h.it t he
.t i nc t ural integrity of thi., portion of the RCS will be maintained. The l
surveillante requirev4.nts of steam generator tubes are based on a modification of Ut.W - Standard Technical Specifications dated June 1,1976.
Inservice inspection Amendment No. 13 4-54
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Bases (Con tinued) of steam generator tubir.g is essential in order to maintain surveillance of the conditions of the tubes in the event that there is evidence of mechanical damage or progressive degradation due to design, manufacturing errors, or inscr-vice conditions that lead to corrosion.
Inservice inspection of steam generator tubing also provides a means of characterizing the nature and cause of any tube degradation so that corrective measures can be taken.
Vastacc-type defects are unlikely with AVT chemistry treatment of the secondary coolant. However, even if a defect should develop in service, it will be found during scheduled inservice steam generator tube examinations. Plugging will be required for defcctive tubes. Steam generator tube inspections of operating plants hava demonstrated the capability to reliably detect degradation that has penetrated 20% of the original tube wall thickness.
Whencycr the results of any stca.n generator tubing inservice inspection fall into Category C-3, these results will be reported to the Commission pursucnt to Sp'eci-fication 6.9 prior to resumption of plant operation.
Such cases will be con-sidered by the Corriissicn on a case-by-case basis and may result in a requi rement for analysis, laboratory examinations, tests, additional cody-current inspection and revision of the Technical Specifications, if necessary.
r-Amendment No. 13 '
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TABLE 4.17-1 R.
MINIMUM NUMBER OF STEAM GEtEP.ATORS TO BE INSPECTED DURlHG INSERVICE INSPECTION'
.a w
Preservice inspection No 3;o. of Steam Generators per Unit Two -
First inservice inspection AII Second & Subsequent inservice inspection Onel T
rn as Table Notation:
1.
The Inservice inspection may be Ilmited to one steam generator on a rotating schedule encompassing 6% of the tubes in the steam generator if the results of the first or previous inspections indicate that both steam generators are performing in a ilke manner. Note that under some circumstances, the operating condi-tions in one steam generator mcy be found to be more severe than tiose in the other steam generator. Under such circumstances the sampic sequence shall be modified to inspect the most severe conditions.
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STEAP. GENERATOR TUBE INSPECT 10:1 l
IST SAPPLE INSPECilCN 2!:0 SAMPLE INSPECTICN 3RC ?3 stE !!;SPECTION I
y Sample S!ze lP.ccult Action Ecquired Res _.i :
I Acti'n R' quired l
Result Action Required o
e A minimum of C-1 None n/A u
N/A l
N/A N/A 5 of the Tubes per C-2 Plug defective C-1 None N/A N/A S.G.
tubes and inspect additional 2S of C-2 Pleg defective tubes and C-1 t;one the tubes in this,
inspect additional 45 of S.G.
the tubes in this S.G.
C-2 PI defective tubes i
C-3
?: erm action for C-3 retit of first sample C-3 Perform action for C-3 N/A N/A result of this sample
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E C-3 inspect all tubes The other Hone N/A N/A In this S.G.,
plug S.G.
is defective tubes C-1 and inspect 25 of the tubes in the The other Perform action for C-2 N/A N/A other S.G.
S.G.
Is result of second sample C-2 Notification to NRC pursuant to specification 6.9 The other Inspect all tubes in N/A N/A S.G. is each S.G. and plug C-3 defective tubes.
Notification to NRC pu rs uan t to specifica-tion 6.9 6
S' Where n is the number of steam generators ' inspected. during an Inspection
?
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