ML20133Q289
| ML20133Q289 | |
| Person / Time | |
|---|---|
| Site: | Hatch  |
| Issue date: | 08/05/1985 |
| From: | Stolz J Office of Nuclear Reactor Regulation |
| To: | Georgia Power Co, Oglethorpe Power Corp, Municipal Electric Authority of Georgia, City of Dalton, GA |
| Shared Package | |
| ML20133Q291 | List: |
| References | |
| DPR-57-A-112, NPF-05-A-051, TAC 08298, TAC 08310, TAC 48362, TAC 48363, TAC 64157, TAC 64158 NUDOCS 8508150090 | |
| Download: ML20133Q289 (31) | |
Text
p nog [o '
o UNITED STATES g
}',lg NUCLEAR REGULATORY COMMISSION g
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s-WASHING TON, D. C. 20555 o,
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GEORGIA POWER COMPANY OGLETHORPE POWER CORPORATION
?!UNICIPAL ELECTRIC AUTHORITY OF GEORGIA l
i
-CITY OF CALTON, GEORGIA l
i DOCKET NO. 50-321 l
EDNIN I. HATCH NUCLEAR PLANT UNIT NO. I AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.112 i
License No. DPR-57 1.
The Nuclear Regulatory Comissinn (the Comission) has fcund that:
A.
The application for amendment by Georgia Power Company, et al.,
i (the licensee) d:ted November 19, 1984, 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; 8.
The facility will operate in conformity with the application, 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, and (ii) 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 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, and paragraph 2.C.(2) of Facility Operating License No. DPR-57 is hereby amended to read as follows:
850015o090 850805 PDR ADOCK O y
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Technical Specifications The Technical Specificatiens contained in Appendices A and fl, as revised through Amendment No.184, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment is effective immediately, to be implemented within 30 days of its date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
/
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\\ v John lT. Stolz, Chief Operating Reactors Branch #4 Division of Licensing
Attachment:
Changes to the Technical Specifications Date of Issuance: August 5, 1985 1
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ATTACHMENT TO LICENSE AMENDMENT NO.112 FACILITY OPERATING LICENSE NO. DPR-57 DOCKET NO. 50-321 Replace the following pages of the Appendix "A" Technical Specifications with the enclosed pages. The revised pages are identified by Amendment number and contain a vertical line indicating the area of change.
Perove Insert iv iv ix ix 3.f> '0a through 3.6-109 3.6-10a through 3.6-10d 3.6-31 3.6-31 3.6-32 3.6-32 6-20 6-20 I
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Section Section Page LBiITING CENDITIONS FCR OPETATICN SUFVEILIIFCE FECUIRD1MS 3.6 PRIMAFY SYS7D1 ECUNCARY 4.6 PRIMARY SYS7IE FOUt:DAPY 3.6-1 A.
Reactor Coolant Heatup A.
Reactor Coolant Heatup 3.6-1 and Cooldown and Cooldown B.
Reacter Vessel T aperature E.
Reactor vessel Taperature 3.6-1 and Pressure and Pressure C.
Reactor Vessel Head Stud C.
Reactor Vessel Head Stud 3.6-2 Tensioning Tensioning D.
Idle Recirculation loop D.
Idle Recirculation Ioop 3.6-2 Startup Startup E.
Recirculation Pmp Start E.
Recirculation Pmp Start 3.6-3 F.
Feactor Coolant Chanistry F.
Reactor Coolant Chmistry 3.6-4 G.
Feactor Coolant Leakage G.
Reactor Coolant Leakage 3.6-7 H.
Safety and Felief Valves H.
Safety and Felief Valves 3.6-9 I.
Jet Pteps I.
Jet Pumps 3.6-9 J.
Fecirculation Pmp Speeds J.
Recirculation Pump Speeds 3.6-10 K.
Structural Integrity of K.
Structural Integrity of Primary Systm Boundary Primary Systen Poundary 3.6-10 L.
Snutbers L.
Snubbers 3.6-10a 3.7 CCt. TANNER.T SYSTD$
4.7 CCtTAImaT SYSTDT 3.7-1 A.
Primary Contaiment A.
Primary Contaiment 3.7-1 B.
Standby Gas Treatment Systs B.
Standby Gas Treatment Systm 3.7-10 C.
Secondary Contalment C.
Secondary Contaiment 3.7-12
- D.
Primary Contairrtent D.
Primary Centaiment 3.7-13 Isolation Valves Isolation Valves 3.6 FADICACTINT MATERIAIS 4.8 PADICACTIVE FATEPIAIS 3.6-1 A.
Miscellaneous Radioactive A.
Miscellaneous Radioactive 3.9-1 Materials Sourt.es Materials Sources 3.9 AL"XILIARY EIIC7RICAL SYST&.S 4.9 AUXILIARY ELECTRICAL SYSTIMS 3.9-1 A.
Fequirments for Pe3ctor A.
Auxiliary Electrical 3.9-1 startup Systes I4uipment iv Amendment No.17,112
I.
LIST OF TABLES
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(Continued)
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Table Title i
Pace 4
4.6-1 In-service Inspection Program 3.6-11 i
3.7-1 Primary Containment Isolation Valves 3.7-16 1
3.7-2 Testable Penetrations with Double 0-Ring Seals 3.7-21 I
3.7-3 Testable Penetrations with Testable Bellows 3.7-22 i
3.7-4 4
Primary Containment Testable Isolation Valves i
3.7-23 3.13-1 Fire Detecters 3.13-2 3.13-2 Fire Hose Stations i
3.13-9 3.14.1-1 Radioactive Liquid Effluent Monitoring j
Instrumentation 3.14-2
)
3.14.2-1 j
Radioactive Gaseous Effluent Monitoring Instrumentation 3.14-7 1
4.14.1-1 Radioactive Liquid Effluent Monitoring 3.14-4 Instrumentation Surveillance Requirements t
4.14.2-1 3
Radioactive Gaseous Effluent Monitoring 3.14-11 4
Instrumentation Surveillance Requirements 4.15.1-1 Radioactive Liquid Effluent Sampling and 3.15-2 Analysis Pregram i
4.15.2-1 Radioactive Gaseous Waste Sampling and 3.15-10 Analysis Program 3.16.1-1 Radiological Environmental Monitoring Program 3.16-4 3.16.1-2 Reporting Levels for Radioactivity Concentra-3.16-7 4
tions in Environmental Samples 1
4.16.1-1 Lower Limit of Detection 3.16-8 6.2.2-1 Minimum Shift Crew Composition 6-4 6.9.1.7-1 Environmental Radiological Monitoring Program Summary 6-18
)
6.9.2-1 Special Reporting Requirements 6-19 4
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Amendments Nos. 6, 0, 179.112 ix
3/4.6.L SM TFEFS LINITIFC-CGQITICN EG CFEFATICN 3.6.L All snubbers
- shall be CFEP/1LC.
'Ibc cnli snutters excludec fra' this requirment are those installed on non-safety relatec systes and then only if their failure or failure at tre systar en which they are installec would have no ccverse effect on any saf ety-relatec systut.
AFFLICALILIn': Ccnditions 1, 2, anc 3.
ACTICN:
hitn cne or core snutbers inoperable, within 72 tcure re. place or restere tre inoperacle sndter (s) to OFEFIELE status anc perter an engineering evaluation per Specification 4.6.L.3 on the supportec ca ponent or declare the supportec syster. Inoperable ano follow the appropriate lielting conditien of operation statenent(s) for tnat systa.
ELTVEILUSCE FICUI'Fa25 4.6.L Each sndter shall be dmonstrated CFEPIE E by perfontance of the tollowing inservice inspection progmt.
1.
Visual InsFections All safety-related snubcers shall be visually exanined to verify sndter operability.
Visual inspections shall te perfern ce in accordance with the following schecule:
No. Incperable Endoers Sdsequent Visual per Insrection Furloa Inst 4.ction Feriod" 0
16 rrenths + 25%
1 12 nonths 7 25%
2 6 rtonths 7 25%
3, 4 124 days 7 25%
5, 6, 7 62 days 7 25%
8 or trore 31 days 7 25%
- te sndbers n4ay be categorized into two groups
"tose accessible-anc these inaccessible curing reactor operation. Each group tray te inspected independently in accordance with the above senedule.
2.
ylsual Inscecticn Accet:tance Criteria Visual inspections shall verify (1) that there are no visirle indications of carrage or irrpairec OFEFAEILITY, (2) attactnents to the founcation or supportirc structure are secure, and (3) for trechenical snubbers where crurter novatent can be tranually induct.d, the snt.tters snall te instectcc as follows:
ta) At each refuelinc, I
- The appitcatie snurters sns11 re icentified in plant procedures.
)
- 'Ite inspction interval snall not ce lengtncnce nere tnan ene etcp at a ti:t e.
r;m' - LTIT 1 3.6-10s Amendment No. 77, 112
3/4.6.L SNITEIPS SIMTILIANCE FFCUIFD:.ENTS (Continuco) systms associated with the safety-related mechanical snlbers shall be inspectec to dete=ine if there has been a severe dynmic event.
(b) In the event or a severe cynamic cvent, snurcers in that systern which experienced the event shall be inspectec during the refueline outage to assure the snutters have freecm or novment and are not frozen up.
The inspctica shall consist of verifying free.cm of motion using one of the following:
(i) t4anually induced snutter nioveent ; (ii) stroking the nechanical snutber through its full range of travel. If one or acre rechanical snutbers are fcune to be frozen up during this inspction, those snutbers shall te replaced (or overhauled) before returning to power.
Re-instectlen shall subsquently be perfomed according to the schccule of 4.6.L.1, but the scop of the exm.inaticn shall be limitec to tne systes associated with the safe.ty-relatec mechanical snutters.
Snutters which appar inogratle as a result of visual inspections may be determined CFEABIE for the purpose of establishing the next visual inspction interval, provicing that (1) the cause of the rejection is clearly establishec and rmecied for that particular snutter and for other snuttus that nay be scnerically susceptibler anc (2) the af tectec snunter is functicnally tested in the "as found" condition and determanec CFEPJIIE per Specification 4.6.L.4 or 4.6.L.5, as applicable.
Powever, if a hydraulic snutter is found to contain less tnan the rquirec minimm volme or reserve fluid or if visitle signs of leakage are present, the snutter shall te detern.ined inoperable and cannot be determined CFEPMII via functional testing for the purpose of establishing the next visual inspction interval.
3.
Ttnctional %sts At least once per 18 months during shutscwn, a representative smple of 10% of the total of each type (hycraulic or rechanical) safety-related snutter in use in the plant shall be functionally tested either in place er in a bench test.
For eacn snurter that does not nest the functienal test acceptance criterie of Epecitication 4.6.L.4 or 4.6.L.5, an additional smple of at least 1/2 the size of the initial lot of that type of snutter 2nall be functionally tested.
Functional testing snall centinue until no acditional ineb ratle snucters of a particular type are founo within a smple or until all sarety-related snutters of tnat type have been functicnally tested.
The representative sample selected for functional testing shall include the various configurations, oprating enviroments and the range of size and capacity of snuttsers.
The representative ssple shall be selected randnly frm the total population or safety-related snutt.ers. At least 25% of the snutters in the FMG - LtIT 1 3.6-lCb Amendments flos. $7
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3/L.E.L SNGEEPS ELM'EILUFCE FECUIFD;RTS (Continuec) representative san.ple shall include snutt.ers fren. the follcwing three categories:
1.
7he first snutter away fra ecch reactor vessel no:rle, 2.
Snubbers within 5 feet of heavy equipent (valve, pun p, turbine, motor, etc.), ano 3.
Snutbers within 1C feet o t' the cischarge tra a
safety-relief valve.
Snutters identified in plant procedures as "Especially Difficult to Restove" or in "High Fadiation Zones turing Shutaown" shall also be included in the representative ssple*.
The pcpulations of safety-related hydraulic anc safety-relate.c nechanical snutbers may te usec jointly or separately cs the tacts for tne smplinc plan.
In adcition to the regular smple, snubbers placed in the sme location as snutters wrien failec the previces functienal test snall be retested during the next test period.
Test results cf these snurters shall not te included in the smpling plan.
If any snutber selected for functional testing either fails to lockup or fails to cove, i.e.,
frozen in place, the cause will te evaluated and if caused by manufacturer or design deliciency all snubbers of the see design subject to the sme defect shall te functionally tested.
' Itis testing ruquirment shall be inde&ncent of the requirtstents stated ateve for snubters not p.eeting the functional test criteria.
For the snutter(s) found inoperatle, an engineering evaluaticn stall be perfomed on the cm.pnents which are supported by tne snutber (s). The purgse of this er.gineering evaluation chall te to deter:nine if the ccnponents supported by the snutter(s) were acversely affecteo ty the inoperatility of the enutter (s) in traer to ensure that the supprted cmponent rmains capable of nectine tre designe.d service.
4.
Fvcraulic Enutbers R:nctional 'fest teceptance Criteria ine hycraulic cnutter renctional test shall verity that:
- Femanent or otner exmptions Irmi functional testing for inoividual snutters in those categories n.ay be grantec by tne ccrntission only it.a justifiatle basis for exutption is prese.nted and/or snutter life destructive testing was perfomeo to qualify snutber operability for all oesign conditions at eitter tre cmpletion or tr.cir f abrication or at a curstquent date.
FA'ICH - LUIT 1 3.6-1Cc Amendments Nos. J/.
51,112
3/4.6. L ShW EEPS SmVEILUMI RECUIFF.ENIS (Centinued) a.
Activation (restraining action) is achieved within the specified range of velocity or acceleration in both tension and carpression.
b.
Endber bleed, or release rate, where rq uireo, is within the specified range in carpression or tension.
Etr sndbers specifically rquired to not displace uncer continuous load, the ability of the sndber to withstand load without displacetent shall be veritied.
5.
Mechanical Sndbers Evnetional Test Acceptance criteria The mechanical sndber functional test shall verify that:
i a.
The snutber operates freely over the stroke in both te.nsion and carpression.
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b.
The force that initiates free n.oveent of the snutter rod in j
either tension or ccrpression is less than the specified n.aximurr drag force.
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c.
Activation (restraining action) is achieved within the specified range of velocity or acceleration in both tension and carpression.
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6.
thit Cutace Inaccessible Sndber Inspection In the event that all inaccessible snutters are inspected, functionally tested, and repaired as necessary during a unit outage, and that it is
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thus dmonstrated that all inaccessible sndbers are oprable, the schedule in Specification
- 4. 6. L.1 may be re-entered on a 6-n.onth inspection interval for the inaccessible sn d bers.
7.
Sndber Service Life Monitorina A record of the service life of each snubter, the date at which the designated service life ccmeences and the installation and maintenance records on which the desicnated service life is based shall be i
maintained as rquired by Spdification 6.10.2.n.
1 Concurrent with the inservice visual inspection perforned during the i
first refueling outage following issuance of this amenchent and at
{
1 east once per 18 months thereaf ter, the installation anc maintenance records for each safety-related andber shall be reviwed to verify that the indicated service life has not t+en exceeded or will not te i
exceeded by more than 10% prior to the next scheduled snutber service i
lire reviw.
If the indicated service life will be exceeded by more than 10% prior to the next scheduled snutt.wr service life review, the snutter service life shall be reevaluated or the snutt4r shall be i
replaced or reconditioned so as to extend its service life beyond the date of the next screduled servic+, life review.
The results of the 4
l reevaluation may be used to justify a change to the service life of the
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snutt er.
This reevaluation replac mant or reconditioninc, snall ce l
indicated in the records.
i FMCF - LFIT 1 3.6-10d Amendments Nos. #,
i H.Il2 s
m_
PMES 3/4.6.L ShTEEEES All snutbers are required CPERAELE to ensure that the structural integrity of the reactor coolant systs and all other safety-related systes is raintained during and following a seimic or other event initiating i
dynamic loads.
Snutbers excluded frm this inspection prograr. are those j
installed on nonsafety-related systes and then only if their failure or failure of the systs on which they are installed, would have no adverse effect on any safety-related systs.
The visual inspection fraquency is based upon maintaining a constant level of snutber protection to systes. Werefore, the ts;uired inspection interval varies inversely with the observed snutter failures and is determined by the nutber of inoperable snubbers found during an inspection.
Inspections performed before the interval has elapsed may be used as a new reference point to determine the next inspection.
However, the results of such early inspections perfoured refore the original required time interval l
has elapsed (nominal time less 25%) may not be used to lengthen the rquired inspection interval Any ins;4ction whose results re:;uire a shorter inspection interval will override the previous schedule.
htm the cause of the rejection of a snutter is clearly estr.blished and reedied for the snubber and for any other snuobers that may be generically susceptible, and verifisc ty inservice functior.al testing, that snutter may be ex spted frm being countec as inoperable.
Generically susceptible j
snutbers are those which are of a specific make or model and have the see i
design features directly related to rejection of the snubber by visual l
inspection, or are similarly located or exposed to the same envirorrental conditions such as te perature, radiation, and vibration.
(
4 i
hten a snutber is founc inoperable, an engineering evaluation is performed, in addition to the determination of the snubber mode of f ailure, i
in order to determine if any safety-related emponent or syste has been l
adversely affected by the inoperability of the anubber.
De engineeri'ng
(
evaluation shall determine whether or not the snubber mode of failure has
}
imparted a significant effect or degradation on the supported empenent or systs.
To provide assurance of snubter functional reliacility, a representative saple of the installed snutters will be functionally tested curinc plant shutdowns at 18-month intervals. Cbserved failures cf sarple snutters shall re;uire functional testing of additional units.
Hydraulic snutters and mechanical snubbers may each te trea ed as a i
different entity for the above surveillance programs.
i HAKE - t%IT 1 3.6-31 i
AmendmentNo.Jf[112
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BAES 3/4.6.L SIBEERS (Continued)
'Ite 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 te.perature
- area, etc...).
Tr.e requirment to monitor the snubber service life is l
included to ensure t!.st the snubbers periodically undergo a perfomance evaluation in view of their age and operating conditions.
These records 1
will provide statistical bases for future consideration of snubber service life.
'Ihe rq uirerrents for the maintenance of records and the snubber service life review are not intended to affect plant operation.
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HA M - UNIT 1 3.6-32 Amendment No. 7, 112 i
OISISTRATIVE CCNTROL RECCRD RETENTION (Ccntinued)
Recorcs of raciatien exposure for all incivicuals entering raciatien c.
centrol areas.
d.
Reccrds of gasecus and licuid racicactive material releasec tc the environs.
e.
Reccrds of transient or cperational cycles for these unit ecccenen:s icentifiec in Table 5.7.1-1.
j f.
Recercs of reacter tests anc experiments, g.
Reccrds of training anc cualificatien fcr curren mercers of the unit staff.
' n-service inscecticns perferrec cursuant to these h.
Reccrcs of i
Tecnnical Scecifications.
1.
Recercs cf Cuality Assurarce activities recuirec cy tre CA Manual.
J.
Reccres of reviews perforreo fcr changes mace to ::::cecures er ecuicment er reviews cf tests anc experiments cursuant tc 10 CFR 50.59.
k.
Reccres cf meetings cf the FRS anc SRE.
1.
Reccrcs for Envircnmental Qualificaticn wnien are ecverec encer the previsicns of paragra;n 6.15.
m.
Reccres of analyses recuirec by the Raciclegical Envircnmental Mcnitoring Prcgram, n.
Records of the service lives of all safety-related hydraulic and mechanical snutters including the date at which the service life ccenences and associated installation and maintenance records.
6.11 RACIATICN FCGTECTION FRCGFAM Prececures fer perscnnel radiaticn prctection shall te precarec censistent witn the recuirements of 10 CFR Part 20 and snail be a;crevec, maintained arc achered to for all cceratiens invciving persennel raciation expcsure.
6.12 HIGH RADIATICN AREA 6.12.1 In lieu of the "centrol cevice" cr " alarm signal" recuirec by paragrapn 20.2C3(c)(2) of 10 CFR 20, eacn hign radiaticn area in whicn the intensity of radiaticn is greater than 100 mrem /hr but less than ICCO mrem /hr shall te barricaced and censpicucusly posted as a high radiation area ard entrarce theretc snall be cent clied by recuiring issuance of a Raciaticn herk Permit +.
Any individual er grcup of incivicuals permitted
- Nealtn Fnysics perscnnel, or perscnnel esccrted by Health Physics cerscnnel in accorcance with approvec emergency prececures, shall be exempt from the RhP issuance recuirement curing the performance of their assignec radiatien p;ctection duties, proviced they cceply with approved radiation prctecticn prececures fer entry into high raciaticn areas.
HATCH UNIT 1 6-20 A;nendment No.)HI f, AYg.
10/U/20. D C.d
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UNITED STATES y*
g NUCLEAR REGULATORY COMMISSION r, -
-l WASHINGTON, D. C. 20555 T;
f GEORGIA POWER COMPANY OGLETFORPE POWER CORPORATION MUNICIPAL ELECTRIC AUTFORITY OF GEORGIA CITY OF DALTCN, GEORGIA DOCKET NO. 50-366 I
EDWIN I. HATCH NUCLEAR PLANT, UNIT NO. 2 AMENDMENT TO FACILITY OPERATING LICENSE Anendment No. 51 1
License No. NPF-5 i
j 1.
The Nuclear Regulatory Comission (the Commission) has found that:
A.
The application for amendment by Georgia Power Company, et al.,
(the licensee) dated November 19, 1984, 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; 8.
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 I
in compliance with the Comission's regulations; 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 Commission's regulations and all applicable requirements have been satisfied.
l 2.
Accordingly, the license is amended by changes to the Technical l
Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. NPF-5 is hereby amended to read as follows:
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j Technical Specifications The Technical Specifications contained in Appendices i
A and B, as revised through Amendment No. 51, are i
hereby' incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment is effective immediately, to be implemented within 30 days of its date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION i
- }
/
/
.f}e c.
JohW F. Stolz, Chief )
a Operating Reactors Branch Ed Division of Licensing
Attachment:
l Changes to the Technical Specifications i
Date of Issuance: August 5, 1985 t
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ATTACHMENT TO LICENSE AMENDMENT N0. 51 FACILITY OPERATING LICENSE N0. NPF-5 DOCKET NO. 50-366 Peplace the following pages of the Appendix "A" Technical Specifications with the enclosed pages. The revised pages are identified by Amendment number and contain a vertical line indicating the area of change.
Remove Insert VIII VIII XIII XIII 3/4 7-11 through 3/4 7-18 3/4 7-11 through 3/4 7-18 B 3/4 7-?
8 3/4 7-2 8 3/4 7-3 B 3/4 7-3 6-18 6-18
INDEX l
l LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION PAGE 3/4.6 CONTAINMENT SYSTEMS 3/4.6.1 PRIMARY CONTAINMENT Primary Containment Integrity........................
3/4 6-1 P rima ry Con ta i nment Lea kage..........................
3/4 6-3 Primary Containment Air Lock.........................
3/4 6-6 MSIV Leakage Control System..........................
3/4 6-7 Primary Containment Structural Integrity.............
3/4 6-8 i
Primary Containment Internal Pressure................
3/4 6-9 I
Drywell Average Air Tempera tu re......................
3/4 6-10 t
3/4.6.2 DEPRESSURIZATION SYSTEMS Suppression Chamber..................................
3/4 6-11 l
Suppres sion Pool Cool ing.............................
3/4 6-14 3/4.6.3 PRIMARY CONTAINMENT ISOLATION VALVES.................
3/4 6-15 3/4.6.4 VACUUM RELIEF Suppression Chamber - Drywell Vacuum Breakers........
3/4 6-33
. Reactor Building - Suppression Chamber Vacuum j
- Breakers...........................................
3/4 6-35 3/4.6.5 SECONDARY CONTAINMENT Seconda ry Conta inment In tegri ty.......................
3/4 6-36
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Secondary Containment Automatic Isolation Dampers.....
3/4 6-37 3/4.6.6 CONTAINMENT ATMOSPHERE CONTROL Standby Gas Treatment System.........................
3/4 6-40 Primary Containment Hydrogen Recombiner Systems......
3/4 6-43 Primary Containment Hydrogen Mixing System...........
3/4 6 44 3
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HATCH-UNIT 2 VII i -
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It'DEY.
. LIlu"IIU CCt'DITIO'S FOR CPFPATIrF N'D SUP1WDKE PIPUIPH'E?"S ScrICri PAGE 3/4.7 PIl2T SYSTE'S 3/4.7.1 SDNICE t ATER SYS"n'S Pesidual Heat Pe-cval Service Water System.....
3/4 7-1 Service tkter Systems..........................
3/4 7-3 3/4.7.2 MAIN COtfrPCL ROctt DNIPOtENTAL CCHIPCL SYS.'E!.
3/4 7-5 3/4.7.3 REACICR COFE ISCLATICM CDCLIFC SYSIDt.......... 3/4 7-9 3/4.7.4 SWBBEFS....................................... 3/4 7-11 3/4.7.5 SEALED SCCPCE CCe?!M2r7CIC :.................... 3/4 7-19 3/4.7.G FIRE SUPPPESSICti SYSrn!S Fire Suppression tr ter Systen.................. 3/4 7-21 a
Sprinkler Systems..............................
3/4 7-25 Icw Pressure CO2 Qistens.....................
3/4 7-27 Fire Hose Stations.............................
3/4 7-22 3/4.7.7 PCT"PXEICM FIRF. PAFRIEFS...................... 3/4 7-30 3/4.7.8 ShWCC OF CLASS I S"EtICL*IS............... 3/4 7-31 3/4.G YLirTPICAL PCFEP. SYSTH*S 3/4.8.1 A.C. SCU*CEF A.C. Ecurces-Oceratirg.........................
3/*,S-1 A.C. Scurces-Shutdown..........................
3/4 S-9 3/4.8.2.
OnsITr. PerTn CII DIPUTIcN FYSrTPs.
A.C. Distributica - operating..................
3/4 6-10 A.C. Distribution
.tutdmn................... 3/4 e-12 D.C. Distributicn - Cperating.................. 3/4 8-13 D.C. Distribution - thutdown................... 3/4 6-16 A.C. Circuits Inside Prir.ary Containment.......
3/4 8-17 Prinary Contain"w.t Penetration Conduc*w r Overcurrent Protective Devicas.................
3/4 0-12 F :rC" - UlTr 2 VIII Amendment No. 51
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INDEX BASES SECTION PAGE f
REACTOR COOLANT SYSTEM (Continued)
~
3/4.4.8 STRUCTURAL INTEGRITY B 3/4 4-6
{
3 /4. 5 EMERGENCY CORE COOLING SYSTEMS 3/4.5.1 HICH PRESSURE COOLANT INJECTION SYSTEM B 3/4 5-1 3/4.5.2 AUTOMATIC DEPRESSURIZATION SYSTEM B 3/4 5-1 i
?
3/4.5.3 LOW PAESSURE CORE COOLING SYSTEMS t
Core Spray System B 3/4 5-2 Low Pressure Coolant Injection System B 3/4 5-3
}
3/4.5.4 SUPPRESSION CHAMBER B 3/4 5-3
}
3/4.6 CONTAINMENT SYSTEMS 1
3/4.6.1 PRIMARY CONTAINMENT INTEGRITY i
s Primary Containment Integrity B 3/4 6-1 i
Primary Containment Leakage B 3/4 6-1 i
Primary Containment Air Lock B 3/4 6-1 4
MISV Leakage Control System B 3/4 6-2 4
Primary Containment Structural
)
Integrity B 3/4 6-2 l'
Primary Containment Internal Pressure B 3/4 6-2 4
l Drywell Average Air Temperature B 3/4 6-2 3/4.6.2 DEPRESSURIZATION SYSTEMS B 3/4 6-3 i
3/4.6.3 PRIMARY CONTAINMENT ISOLATION VALVES B 3/4 6-4 j
3/4.6.4 VACUUM RELIEF B 3/4 6-5 3/4.6.5 SECONDARY CONTAINMENT B 3/4 6-5 l
i s
{
3/4.6.6 CONTAINMENT ATMOSPHERE CONTROL B 3/4 6-5 1
i HATCH-UNIT 2 XII i
Amendment No. 48
INDI BASES SECTION PACE 3/4.7 PLANT SYSTEMS 3/4.7.1 SERVICE WATER SYSTEMS
' ~ B 3/4 7-1 3/4.7.2 MAIN CONTROL ROOM ENVIRONMENTAL CONTROL SYSTEM 3 3/4 7-1 3/4.7.3 REACTOR CORE ISOLATION COOLING l$
SYSTEM 3 3/4 7-1 3/4.7.4 SNilBBERS B 3/4 7-2 f
3/4.7.5 SEALED SOURCE CONTAMINATION 3 3/4 7-3 3/4.7.6 FIRE SUPPRESSION SYSTEMS B 3/4 7-3 3/4.7.7 PENETRATION FIRE BARRIERS B 3/4 7-4 3/4.7.8 SETTLEMENT OF CLASS I STRUCTURES B 3/4 7-4 3/4.8 ELECTRICAL POWER SYSTEMS B 3/4 8-1 3/4.9 REFUELINO OPERATIONS 3/4.9.1 REACTOR MODE SWITCH 3 3/4 9-1 3/4.9.2 INSTRUMENTATION B 3/4 9-1 3/4.9.3 CONTROL ROD POSITION B 3/4 9-1 3/4.9.4 DECAY TIME B 3/4 9-1 3/4.9.5 SECONDARY CONTAINMENT 3 3/4 9-1 3/4.9.6 COMMUNICATIONS B 3/4 9-2 3/4.9.7 CRANE AND HOIST OPERABILITY B 3/4 9-2 3/4.9.8 CRANE TRAVEL-SPENT FUEL STORAGE POOL B 3/4 9-2 3/4.9.9 WATER LEVEL - REACTOR VESSEL AND and WATER LEVEL - SPENT FUEL STORAGE 3/4.9.10 POOL B 3/4 9-2 3/4.9.11 CONTROL ROD REMOVAL B 3/4 9-2 3/4.9.12 REACTOR COOLANT CIRCULATION B 3/4 9-3 l
HATCH-UNIT 2 XIII Amendment No. %,51
l 4
LIANT SYST&.S 3/4.7.4 Shu B DS LIMITING CCbDITION FOR OPEPATION 3.7.4 All snubbers
- shall be operable. The only snubbers excludal frcrr. this requireent are those installed on non-safety related systes and then only if their faiure or failure of the systs on which they are installed would have no adverse effect on any safety-related syste.
j APPLICABILITY: Conditions 1, 2, and 3.
ACI' ION:
l j
With one or more snutters inoperable, within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> replace or restore the j
inoperable snubber (s) to OPERAELE status and perform an engineering i
evaluation per Specification 4.7.4.c on the supported cortponent or d(clare
]
the supported systs inoperable and follow the appropriate ACTICN statment for that syste.
l SUFVEILIA!CE FECCIPEINIS j
4.7.4 Each snubber shall be deonstrated OFERAELE by perfocrance of the following' inservice inspection progre and the requirments of Specification 4.0.5.
a.
Visual Inseections All safety-related snutbers shall be visually exmined to verify snubber operability.
Visual inspections shall be perfor:ted in accordance with the following schedule:
No. Inoperable Snubbers Subsequent Visual i
per Inspection Period Inspection Period **#
1 0
18 months + 25%
1 12 months 7 25%
2 6 months I 25%*
3, 4 124 days 7 25%
5,6,7 62 dayc I 25%
8 or more 31 days 325%
ne snubbers may be categorized into two groups:
Those accessible and those inaccessible during reactor operation. Each group may be 4
inspected independently in accordance with the above schedule.
7
- The appli.able snutters shall be identified in plant procedures.
- The inspection interval shall not be lengthened more than one step at a time.
i
- 2 e provisions of Specification 4.0.2 are not applicable.
HATC21-UNIT 2 3/4 7-11 Amendment No.51 i
.m.-_.
---,.,_~~...,,..~_._mm...
1 PIRIT SYST&S St*RVEILIRG RECUIRDID.TS (Continued) b.
Visual Inspection Acceotance Criteria i
Visual inspections shall verify (1) that there are no visible indications of daage or impaired OPEPABILITY, (2) attactnents to the foundation or supporting structure are secure, and (3) for mechanical snubbers where snubber moveent can be manually induced, the snutbers shall be inspected as follows:
(a) At each refueling, systes associated with the safety-related mechanical snubbers shall be inspected to determine if there has been a severe dynamic event.
(b) In the event of a severe dynmic event, snubbers in that systen which experienced the event shall be inspected during the refueling outage to assure the sndbers have freeds of moveent and are not frozen up.
i 1
The inspection shall consist of verifying freedcs of motion using one of the following:
(i) Manually induced snubber l
movecent; (ii) stroking the mechanical snubber through its full range of travel.
If one or more mechanical snubbers are found to be frozen up during this inspection, those snubbers shall be replaced (or overhauled) before returning to power.
Re-inspection shall subsequently be perfonted according to the schedule of 4.7.4.a, but the scope of the examination shall be limited to the systens associated with the safety-related mechanical snubbers. Snubbers which appear inoperable as a result of visual inspections may be determined OPERABIE for the purpose of establishing the next visual inspection interval, providing that (1) the cause of the rejection is
]
clearly established and reedied 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 determined OPEPABLE per Specification 4.7.4.d or 4.7.4.e, as applicable.
However, if a hydraulic snubber is found to contain less than the required minimum volme of reserve fluid or if visible signs of leakage are present, the snubber shall be determined inoperable and cannot be detemined OPEPAELE via functional testing for the purpose of establishing the next visual inspection interval.
c.
Ebnetional Tests
)
At least once per 18 months during shutdown, a representative j
satple of 10% of the total of each type (hydraulic or j
mechanical) safety-related snutber in use in the plant shall be functionally tested either in place or in a bench test.
i For each snubber that does not meet the functional test acceptance criteria of Specification 4.7.4.d or 4.7.4.e, an 1
additional seple of at least 1/2 the size of the initial lot of that type of snubber shall be functionally tested.
i HAto! - CNIT 2 3/4 7-12 Amendment No. 51 I
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PI M SYS1L'.S StM'EIIIEE REOUIREMENTS (ContinuW)
Ebnctional testino shall continue until no additional inoperable snubbers of a particular type are found within a smple or until all safety-related snubbers of that type have been functionally tested.
The representative smple selected for functional testing shall include the various configurations, operating envirorcents and the range of size and capacity of snubbers.
The representative smple shall be selected randmly frm the total population of safety-re.iated snubbers.
At least 25% of the snubbers in the representative saple shall include snutters fem the following three categories:
1.
The first snubber away frmi each reactor vessel nozzle, 2.
Snutbers within 5 feet of heavy quipt.cnt (valve, pump, turbine, motor, etc.), and 3.
Snubbers within 10 feet of the discharge fem a safety relief valve.
Snutters identified in plant procedures as "F. specially Difficult to Psove" or in "liigh Radiation Zones turing Shutdown" shall also be included in the representative smple*.
The populations of safety-related hydraulic and safety-related mechanical snutbers may be used jointly or separately as the basis for the smpling plan.
In addition to the regular sm ple, snutbers placed in the sme location as snutters which failed the previous functional test shall be retested during the next test period.
Test results of these sn'&tcrs shall not be includec in the smpling plan.
If any snubber selected for functional testing either fails to lockup or fails to move, i.e., frozen in place, the cause will be evaluated and if caused by manufacturer or design deficiency all snutbers of the see design sub]ect to the see defect shall te functionally tested.
This testing equirment shall be independent of the rquirments stated ateve for snutbers not meeting the functional test :cri teria.
For the snubber (s) found inoperable, an engineering evaluation shall be perfomed on the cmponents which are supported by the snubber (s). The purpose of this engineerino evaluation shall te to determine if the cmponents supported by the snubber (s) were adversely affected by the inoperability of the snubter(s) in order to ensure that the supported cmponent reains capable of necting the designed service.
- Femanent or other exerrptions frce functional testing for individual snutters in those categories may be granted by the Cmnission only if a justifiable basis for exmption is presented and/or snubber life destructive testing was perfomed to qualify snubber operability for all design conditions at l
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either the empletion of their fabrication or at a subsquent date, i
HA701 - UNIT 2 3/4 7-13 Amendment flo. 51
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FIANT SYS' IDS i
St'RVEIIIANCE RECUIRD*D11S (Continued) d.
Hydraulic Snubbers n:nctional test Acceptance Criteria The hydraulic snubber functional test shall verify that l
1.
Activation (restraining action) is achieved' within the specified range of velocity or acx:eleration in both tension and cm pression.
i 2.
Snutter bleed, or release rate, where raquired, is within the specified range in empression or tension.
For snutters specifically required to not displace under i
continuous load, the ability of the snubber to withstand load without displaceent shall be verified.
e.
Mechanical Snubbers Functional Test Acceptance Criteria The mechanical snubber functional test shall verify that:
I l
'l.
The snubber operates freely over the stroke in both i
tension and cm pression.
i 2.
The force that initiates free movment of the snubber rod j
in either tension or empression is less than the specified maximte drag force.
i 3.
Activation (restraining action) is achieved within the
{
specified range of velocity or acceleration in both l
tension and cmpression.
t j
f.
Unit Outace Inaccessible Snubber Inspection i
i in the event that all inaccessible snubbers are inspected, functionally tested, and repaired as necessary during a unit i
outage, and that it is thus deonstrated that all inaccessible j
snubbers are operable, the schedule in Specification 4.7.4.a j
may be re-entered on a 6-month inspection interval for the f
inaccessible snubbers.
i
~
g.
Snubber Service I.ife Monitorinc 1
A record of the service life of each snubber, the date at l
which the designated service life ccmwences and the installation and maintenance records on which the designated service life is based shall be maintained as required by j
Specification 6.10.2.n.
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HATCH - L2:IT 2 3/4 7-14 Amendment No. 51 1
1 f
PIANT SYSMS StETILUJEE RECUIRIKEh'IS (Continued)
Concurrent with the inservice visual inspection performed during the first refueling outage following issuance of this amendrent and at least once per 18 nonths thereafter, the installation and maintenance records for each safety-related snutter shall te reviewed to verify that the indicated service life has not been exceeded or will not be exceeded by more than 10% prior to the next scheduled snubter service life review.
If the indicated service life will be exceeded by more than 10% prior to the next scheduled snubter service life review, the snubber service life shall be reevaluated or the snutber shall be replaced or reconditioned so as to extend its service life beyond the date of the next scheduled service life review.. 'Ihe results of the reevaluation may be used to justify a change to the service life of the snubber.
This reevaluation, replacerent or reconditioning shall te indicated in the records.
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t, wa m - t.UIT 2 3/4 7-15 Amendment No. 51
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l FA KH - llUIT 2 3/4 7 16 hnendment No. 51
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(D115 PAGE LEIT BUJE INH 2. TIC?MY) t t
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!!A7al - WIT 2 3/4 7-17 Amendment No. 51 M
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y I'MQ! - LNIT 2 3/4 7-18 Amendment No. 51 1
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(THIS PAT LEIT BUJE Ih*IETIONALLY) t l
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3/4.7 PI M T SYST& S i
BASES I
REAC'IOR CCFE ISCLATTCN CrOI n:C SYSTE (Continued) i ne surveillance requirerrents provide adequate assurance that PCIC will te OFDAB12 when required. Although all active cmponents are testable and full flow can be deonstrated by recirculation during reactor operation, a emplete functional test rquires reactor shutdown.
ne ptzrp discharge piping is I
maintained full to prevent water haner dmage and to start cooling at the I
earliest mm.ent.
3/4.7.4 S WEBE9S All snutters are required 0FDABIE to ensure that the structural integrity of the reactor coolant system and all other safety-related systes is maintained during and following a seismic or other event initiating dynmic loads. Snubbers excluded fra this inspction progem are those installed on nonsafety-related systerts and then only if their failure or failure of the system on which they are installed, would have no adverse effa:t on any safety-related system.
De visual inspection frequmcy is based ugn maintaining a constant level of snubber protection to systes. Therefore, the required inspection interval varies inversely with the observed snutter failures and is determined by the ntseter of inoperable snutbers found during an inspction.
Inspections performed before the interval has elapsed may be used as a new reference point to detemine the next inspection.
- However, the results of such early l
inspections prfomed before the original required tine interval has elapse (ncerinal time less 25%) may not be used to lengthen the required incrc: tion interval.
Any inspectien who:e results require a shorter inspection interval will override the previous schedule.
khan the cause of the rejection of a snucber is clearly establisted and remedied for the snutter and for any other snutters that may te generically susceptible, and verified ty inservice functional testing, that snutter may te exepted frm. heing counted as inoperable.
Generically susceptible snuttert are those which are of a specific make or model and have tre sme desig, features directly related to rejection of the snutter by visual inrpection, or are similarly located or exposed to the see envirorstental conditions such as tarperature, radiation, and vibration.
khe a snutber is found inograble, an engineering evaluation in performM, l
in addition to the determination of the snubter mode of failure, in order to t
determine if any safety-related ccrrponent or syste has been advernely affected l
by the inogrability of the snubber.
De engineering evaluation chall l
determine whether or not the snubber mode of failure has imparted a significant effect or degradation on the supported emponent or syste.
l To provide assurance of snutter functional reliability, a representative suple of the installed snubbers will be functionally tested during plant
(
shutdowns at 10-fronth intervals.
Ceserved failures of saple enutters shall require functional testing of additional units.
Ilydraulic snutbers and mechanical snutters ma to treated as a different entity for the above surveillance progres.y each IfAMI - (SIT 2 L 3/4 7 2 Amendment No, )c,51
FIRrr smuts UN;ts 3/4.7.4 s"UnrIrf: (Continued) 1
%e service life of a enubber is evaluated via mnufacturer input and infomstion through consideration of the snubber service conditions ary!
associatal installation and mintenance records (newly installed snubber, seal replacod, spring replaced, in high radiation area, in high temperature area, etc...).
We requirement to renitor the snubber service life is includal to ensure that the anubbers perio31cally undergo a performneo evaluation in view of their ago and operating conditions.
%ese records 1
will provide statistical tunes for future consideration of snubber servico life.
We requirenents for the mintenaneo of records and the snubimr service life review are not intended to affect plant operation.
3/4.7.5 SEMID notmcr CrttrNtImTION to limitations on scaled sourco renovable contamination ensure that tho total body or individual organ irradiation does not exceed allowable limita in the event of ingestion or inhalation of the ocurce mterial.
We limitaticas on renovable contamimtion for sources requiring leak testing, including alpha emittern, is based on 10 CpR 70.39(c) limits for plutenlun.
Cuantities of interest to this smcification which are exerpt frem tho leakage testing are consistent with the criteria of 10 CFR Part 30.11-20 and 70.19.
Isakago from sources excludal from the requirenents of this specification is not likely to represent more than one maxinun pernissible bcr3y burden fer total bo3y irradiation if the source material is inhalo! or irrJested.
3/4.7.6 FIPr stTPPrc :Ict! SWms Wo OPENGILIn* of the fire suppression systera ensures that adequato fire supprossion capability is available to confino and extinguish firec occurring in any portion of the facility Where safety-related equiment is located. The tiro suppression system consista of the water synten, spray and/or sprinklers, CD, and fire hose stations.
The co11cetive cambility 2
of the fire su:pression n/ ster.s in adoquato to minhizo potential da vigo to safety-related equipment and is a mjor element in Om facility firo protection program.
In the event that portions of the firo supprocsion syntems are inoperablo, alternato inckup fire fighting equiment in requirol to be mde availablo in the affactoi areas until the inoparable equiment is renterol to nervice.
In Oto event the fire surprennion water nyntom tecerns increrablo, immediate corrective measures must be taken since this system providos the mjor fire suppression capability of the plant.
The requirement for a twenty-four hour report to the Cce,ninnion providon for prompt evaluation of the acceptability of the corrective reanuren to provido adeqmte fire i
suppression cambility for the continued protection of the nuclear plant.
I WCQl-U!!IT 2 D 3/4 7-3 Amendment No.51
PLANT SYSTEMS BASES 3/4.7.7 PENETRATION FIRE BARRIERS The functional integrity of the penetration fire barriers ensures that fires will be confined or adequately retarded from spreading to adjacent portions of the fac,ility.
This design feature minimizes the possibility of a single fire rapidly involving several areas of the facility prior to detection and extinguishment.
The penetration fire barrhrs are a passive element in the facility fire protection program and are subject to periodic inspections.
During periods of time when the barriers are not functional, a contin-uous fire watch is required to be maintained in the vicinity of the affected barrier until the barrier is restored to functional status unless the OPf.RABILITY of the fire detection instruments, providing coverage of the fire detection zones on each side of the non-functional barriers, has been demonstrated.
3/4.7.8 SETTLEMENT OF CLASS 1 STRUCTURES In order to assure that settlement does not exceed predicted and allowable settlement values, a program has been established to conduct a survey at the site.
The allowable total and dif ferential settlerrent values are based on original settlement predictions, in establisning these tabulated values, an assumption is made that pipe and conduit connections have been designed to safely withstand the stresses which would develop due to total and differential settlement, i
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HATCH - UNIT 2 B 3/4 7 4
ACMXNfSTRATfVE CCNTROL FECCRD RETENTICN (Centinued) c.
Recc cs of raciation excesure for all incivicuals enterirg racia:!cn cent:cl areas.
c.
Recc;cs of gasecus arc licuic racicactive material relessec tc tne envir:ns.
e.
Recc cs of transient c: cce:aticnal cycles fe; these unit cerccrerts icentifiec in Table 5.7.1-1.
f.
Recc:cs of reactor tests ano experiments.
g.
Recc:cs of training arc cualificaticn fc cc::ent mercers cf tre unit
- staff, h.
Recc:cs of in-service inscecticns cc ferre:
cursuant to trese Tecnnical Scgelficatiens.
1.
Re:::cs cf Cuality Assurance activities recui:ec :y tre CA vanual.
J.
Re:::cs of reviews cc:fe: eo fc crarges ma:e to c:::ccures c:
ecui: rent c: reviews of tests ano excerirents cursuant t: 1C CFR 50.!?. -
k.
Rec::cs of meetings of the FPS and SFB.
1.
Recc cs fer Envircreental cualificaticn.nien are ccve:ec unce tre previsiens of parag:::n 6.15.
m.
Recercs of analyses recuired by the Racici:gi:s1 Envi:creental Henitcring Prcgram, n.
Records of the service liven of all safety-relatn3 hydraulic and mechanical snubters, including the dat6 at which the service life comences and associated installation and maintenance ru:ords.
6.11 AACIATICN An0TECTICN RACCFN Prececures fc cersennel raciatien c::tecticn shall te cre:arec censistent.ith the recuirecents cf 10 CFR Part 20 and shall te accrevec, esintaine: anc schered to for all ecoratiens involving corsennel raciati:n evcesure.
6.12 HICH Ra0IATICN aAra 6.12.1 In lieu of the "centrol cevice" or " alarm signal" re Jirec cy caragracn 20.2CJ(c)(2) of 10 CFR 20, eacn nign raciatien area in =nich the intensity of raciatien is greater than ICO mrem /hr but less than 1CCO erem/nr sns11 ce barricacco and conspicuously costec as a hign raciaticn area and entrar:e thereto snall te centrollec ey recuiring issuance of a Raciaticn kerk permite.
Any incivicual er greco of incivicuals permittec
- Meaien Fnysics persennel, or corsennel esecrtec by Healtn pnysics corsenrel in accc:cance with accrevec emergency prececures, shall be exempt frcm the Rwp issuance recuirement curing the performance of their assionec racistien protection cuties, proviced they cceoly with accrovec raciatien protecticn procecures for entry into hiCn radiaticn areas.
g HATCH UNIT 2 6-18 Y,h.nh/M190.M
- -