ML20245B791
| ML20245B791 | |
| Person / Time | |
|---|---|
| Site: | Hatch  |
| Issue date: | 04/17/1985 |
| From: | GEORGIA POWER CO. |
| To: | |
| Shared Package | |
| ML20245B770 | List: |
| References | |
| FOIA-87-76 10AC-MGR-04-0, 10AC-MGR-4, NUDOCS 8707010301 | |
| Download: ML20245B791 (173) | |
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. GEORGIA POGT.2 C0!!PANY l l
IIATCH GUCLEAR PLA!!T l PAGE (1 vF 3h - - l l DOCU"ENT TYPE: ' I DOCUiIEi;T iiU!!3ER: ADt!INISTRATIVE CONTROL PROCEDURE I 10AC-!!GR04-0 l DOCUPI:4T . TITLE: , DEFICIENCY CONTROL SYSTE}!
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_X._ SAFETT RELATED . _. __ 903-SAFETY RELATED EXPIRATI0tl DATE: !!/A 1 1 REV.I I APPROVED l l APPROVED l (EFFECTIVE l10. I DESCRIPTIO!! l DEPT. ?tGR. I DATE IGEUERAL ttGR.I DATE I DATE I I e i I ( l g h7 / i i
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!!GR-0002 Rev. 1 F o z i? - 1 7 7 c, 8707010301 870619 PDR FOIA MURPHY 87-76 PDR Of/'/
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e CEORGIA PONER C0;:PAUY I liATCH HUCLEAR PLANT l PAGE 2 0F 39 DOCU:iDiT TYPE: 1 DOCU;1EiiT liUli3ER: l ADMI!!ISTRATIVE C0!! TROL PROCEDURE I 10AC-!!GR04 -0 DOCUItENT TITLE: } REVISION: I DEFICIEllCY C0!! TROL SYSTEli 1 0 TA3LE OF CON'IENTS Section EAg5 1.0 ptJECTIVE .................................. 4 2.0 6PPLICABILITY .............................. 4
3.0 REFERENCES
................................. 4
- 3.1 DEVELOPl!EliTAL REFEREUCES . . . . . . . . . . . . . . . . . 4 3.2 IIIPLEMENTING REFEREtiCES . . . . . . . . . . . . . . . . . . 4 i l
i 4.0 JESPO!:SIBILITIES ........................... 5 l l 4.1 G E :E RAL tiA!!AG ER . . . . . . . . . . . . . . . . . . . . . . . . . . 5 I 4.2 PLA::T REVIEll 30ARD (PRS) ................. 5 l 4.3 OPERATION S DE PART !EllT . . . . . . . . . . . . . . . . . . . . 5 4.4 EllGI!!EERIUG DEPART!!ENT . . . . . . . . . . . . . . . . . . . 6
. 4.5 REGULATORY C0!!PLIANCE SECTION ............ 6 4.6 QUALITY CONTROL SECTION .................. 6 5.0 Jug 2UIREMENTS ............................... 7 5.1 PERS0!!NEL REQUIRE 11EliTS . . . . . . . . . . . . . . . . . . . 7 5.2 MATERIAL AND EQUIP! TENT . . . . . . . . . . . . . . . . . . . 7 s
5.3 SPECIAL REQUIREMEIITS ..................... 7 6.0 PRECAUTIOfiS/ LIMITATIONS .................... 7 6.1 PRECAUTIONS .............................. 7 6.2 LIMITATIONS .............................. 7 7.0 PREREQUISITES .............................. 7 llGR-0001 Rev. O
o s , i GEORGIA POWER C0ilPANY l EATCil NUCLEAR PLA!!T l PAGE 3 0F 39 DOCUMENT TYPE: 1 DOCU;iE!;T NU:13ER: I ADMINISTRATIVE CONTROL PROCEDURE I 10AC-MGR04-0 DOCUZ'ENT TITLE: l REVISIDH: 1 DEFICIE!!CY CONTROL SYSTE 1 1 0 ;
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TABLE OF CONTENTS Section l'.agg 8.0 PROCEDURE .................................. 7 i 8.1 CORRECTIO!! 0F DEFICIENCIES l (CONDITIONS ADVERSE TO QUALITY) .......... S 8.2 SIGNIFICAllT CONDITIONS ADVERSE TO QUALITY ............................... 10 8.3 DEFICIENCY CLASSIFICATION ................ 10 S.4 DEFICIENCY PROCESSI!iG .................... 11 G.5 TAGGIIiG .................................. 14 8.6 DISPOSITIO!!ING liATERIAL DEFICIEMCIES .. . . . 14 3.7 ROOT CAUSE DETERMIliATI0I! A::D 1 L0tlG TER;I CORRECTIVE ACTIO!! . . . . . . . . . . . . . . 17 j 0.3 DEFICIEliCY REPO RT CRAllGE . . . . . . . . . . . . . . . J. 17
. 8.9 RECORDS .................................. 17 l
l A t t a c tme n t s 1 Significant Conditions Adverse To Quality ................................. 18 2 Deficiency Report (DR) ..................... 31 3 Supplemental Report ........................ 34 4 Deficiency Report Change Form .............. 35 5 Deficiency Report Log ...................... 36 6 Hold Tags .................................. 37 7 QC lloid Tag Log ............................ 38 8 Deficiency Reporting Flowchart ............. 39 11GR-0001 Rev. 0
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. GEORGLA POWER COMPANY l EATCH NUCLEAR PLAllT l PAGE 4 0F 39 j LOCUMENT TYPE: I iX)CU.1EUT null 32.:
1 ADMINISTRATIVE CONTROL PROCEDURE I 10AC-MGR04-0 ; DOCUMENT TITLE: l REVISION: 1 DEFICIENCY COUTROL SYSTDI I O l 1.0 OBJECTIVE I This procedure establishes the requirements and responsibilities for acconplishing the four major components of Deficiency Control: ; 1.1 Preparing and processing deficiency reporting documents; I 1.2 Reviewing and determining disposition of deficiency items; 1.3 Detensinin-g ceficiency reportaoility to higher authorities, and 1 1.4 Analyzing deficiency causes and preventing recurrences. ) l 2.0 APPLICA3ILITY l l Tnis procedure applies to all ceficiencies whetner af fecting equipnent, procedures or personnel. ] 3.0 REFEREI:CES 3.1 DEVZLOP!AhTAL REFERD!CES 3.1.1 AUSI 316.7 - 1976. Sections 5.2.6. 5.2.11 and 5.2.14 1 l 3.1.2 AUSI 345.2 - 1977. Sections 16 ano 17 I 3.1.3 AJSI/ASME NQA 1979 Suppleuent 15-5 3.1.4 ASME Code Section III ilCA4000 (tlinter 1982 Adcenca) Article 4134:15 3.1.5 10CFR50 Appendix 3. Criterion XV 3.1.6 10CFR50.59, Changes. Tests 6 Experinents 1 4 3.2 IMPLEllENTING REFERENCES 3.2.1 Quality Assurance Manual 3.2.2 FSAR Unit 2. Chapter 17 - Quality Assurance Controls. Sections 17.2.15 6 17.2.16 liGR-0001 Rev. O
a l CEORGIA POUER C01:PAHY l EATCH NUCLEAR PLANT l PAGE 5 0F 39 DOCUMENT TYPE: l 30CUI.E11T UU:13ER: I ADt!INISTRATIVE CONTROL PROCEDURE l 10AC-:!GR04-0 DOCUMENT. TITLE: l REVISIOil: 1 I DEFICIE14CY CONTROL SYSTE t l 0.
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3.2.3 10CFR21. Reporting of Defects and Noncompliances 3.2.4 10CFR50.72. Immediate Notification Requireuents for Operating i
!!uclear Power Reactors ]
l 3.2.5 10CFR50.73. Licensee Event Report System j 3.2.6 100FR50.54(X). Conditions of Licenses 4.0 RESPOUSIBILITIES 4.1 GEliERAL !!ANAGER Ensures that the Deficiency Control System meets nuclear in-dustry standards ano satisfies both regulatory requirenents and Plant Macen couaitments. 4.2 PLA:IT REVIEU BOARD (PRD) 4.2.1 Serves as advisory board to the General '.!anager. ! 4.2.2 Revieus reportability assessacnts for operational Deficiency Reporcs (DRs). 1 4.2.3 Assesses operational deficiencies and determines the ef fect l on plant operations. 1
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4.2.4 Reviews the assessment of material deficiencies that are l potentially 10CFR21 reportable. Q-Listed and dispositioned l as repair or use as is. i I 4.3 OPERATIONS DEPARTMENT I I The Operations Department, under the direction of tne llanager of Operations, is responsible for: l l 4.3.1 Evaluating the ef fect of operational deficiencies on plant operations. 4.3.2 Determining whether tne operational conditions or problems l are significant and/or reportable per Attachment 1 and 40AC-REG 02-0. Federal and State Reporting Requirements. MGR-0001 Rev. O
I l l GEORGIA POWER C0ilPANY l i IIATCH NUCLEAR PLANT l PAGE 6 0F 39 !i DOCUMENT TYPE: l DOCUllE!;T I!Ulli:ER: 1 ADMINISTRATIVE CONTROL PROCEDURE I 10AC "GR04-0 DOCUMENT TITLt.: l REVISION: 1 " DEFICIE1!CY CollTROL SYSTEM l 0 , , l 4.4 ENGINEERING DEPART!IENT l The Engineering Department, unoer the direction of the Manager of Engineering, is responsible for: l 4.4.1 Reviewing design enanges and procedural changes brought about by the deficiency resolution and corrective action processes. . l 4.4.2 Dispositions material deficiencies for Q-listed material that j are designated repair or use as is. j 4.5 REGULATORY COMPLIANCE SECTION l The Regulatory Compliance Section under the direction of the l
!Ianager of Engineering, is responsible for: j i
4.5.1 Evaluate deficiency reportability and assign responsibility for root cause determination and long term corrective action. 4.5.2 Tracking long tem corrective action. 4.5.3 Preparing reports to higher authorities uhen required for l reportable ceficiencies. ) 4.5.4 Tracking all DRs through close-out. 4.6 QUALITY CONTROL SECTION The Quality Control Section, under tne direction of the llanager of Engineering, is responsible for: 4.6.1 Maintaining a Deficiency Report Log and QC lloid Tag Log. 4.6.2 Assigning QC personnel to af fix and remove QC lloid Tags to/f rom materially deficient items. 4.6.3 Assuring closed out DRs are complete. 4.6.4 Dispositioning non-Q and' Q-listed material deficiencies categorized as rework or reject. MGR-0001 Rev. O
1 B e i GEORGIA P0 TIER CO:!PANY l
!!ATCH NUCLEAR PLANT l PAGE 7 0F 39 DOCUMENT TYPE: l DOCU:lEt.T !;UllBER:
l ADMINISTRATIVE CONTROL PROCEDURE l 10AC-:iGl'.04-0 DOCUMEld TITLE: l REVISIO!!: ' I DEFICIENCY CONTROL SYSTEM l 0 5.0 REOUIRE'1ENTS 5.1 PERSONNEL REQUIREMENTS Those personnel involved in the deficiency control / corrective action process shall receive specific training in the principles and requireuents of this procedure. 5.2 11ATERIAL AND EQUIPMEtiT M/A - Not applicable to this procedure. 1 5.3 SPECIAL REQUIRE:1ENTS N/A - Not applicable to tnis procedure. 6.0 PRECAUTIONS / LIMITATIONS 6.1 PRECAUTIONS j l U/A - Not applicable to this procedure. j 1 6.2 LI!!ITATIONS l l N/A - Not applicable to tais procedure. 7.0 PRE *!EOUISITES
!!/A - tiot applicable to this procedure. l 8.0 PROCEDITRE Various actions can be taken to resolve probleus (deficiencies) considered detrimental to the safe operation of Plant Hatch.
The urgency of the proolem shall dictate the immediacy of initial problem resolution (corrective action). Prompt corrective action shall always be that which places the plant in a safe condition. Deviations from procedures shall only be autnorized to preserve reactor fuel integrity, preserve life or prevent unnecessary equipment damage. MGR-0001 Rev. 0
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GEORGIA POWER C0!IPAhV l HATCH NUCLEAR PLANT l PAGE 8 0F 39 DOCUMENT TYPE: DOCUlIENT UUll3ER: ! l l . ADNIRISTRATIVE CONTROL PROCEDURE l 10AC-!!GR04-0 l l DOCUMENT TITLE: l REVISION: I DEFICIENCY CONTROL SYSTE!! l 0' , , 8.1 CORRECTION OF DEFICIENCIES (CONDITIONS ADVERSE TO QUALITY) 1 8.1.1 It is reasonable to expect that during the operational lifetime of Plant liatch conditions may arise that j will require actions to be taken to either upgrade or maintain tne unit (s) in a safe and reliable status. The normal methods for affecting change to improve reliability or to correct defects that reduce reliability are the various administrative controls systems that have been established to identify and either correct or improve these conditions. The administrative processes for 4 correcting defects or causing improvements are identified I below. 8.1.1.1 A !!aintenance Work Order (IfUO) is used to control the correction of defects in station equipment (See l 50AC-!!NT01-0. Haintenance Program). i 6.1.1.2 A Request for Engineering Review (RER) is used to ' initiate and control modifications to station equipment (Sec 40AC-EUG03-0. Design Control). 8.1.1.3 The material deficiency section of a Deficiency aeport ; is used to control and process nonconforming materials. l parts, and components identified during receipt l inspections required in 50AC-IITL01-0. Control of Purchased llaterial and 40AC-EUG07-0. Control of Special Nuclear Material (SNM). 8.1.1.4 A Temporary Procedure Change Form or a Procedure / Instruction Request Form is used to control the development of or revision to Plant Hatch Procedures and Instructions (See AG-ADM-01-07 83. Preparation and Control of Administrative Instructions, and 10AC-MGR03-0. Preparation and Control of Procedures). 8.1.1.5 The Training Request or Training Directive is used to identify request, and document the training needed when a problem was causeu by personnel error (See 70AC-TRN01-0. Plant Training Program). MGR-0001 Rev. O i
I GEORGIA POUER COMPANY l RATCH NUCLEAR PLANT l PAGE 9 0F 39 DOCUMENT TYPE: l DOCUllEUT UUMBER: I ADMINISTRATIVE CONTROL PROCEDURE l 10AC-l!GR04-0 DOCUHFIT TITLI.: l REVISION: 1 DEFICIENCY CONTROL SYSTEM i 0 The normal administrative processes described in subsection 8.1.2 8.1.1 should be used by Plant Hatch employees when he/she wishes to effect changes or correct problems. They,should seek sovice from tneir immediate supervisor when they are having a problem identifying which aaministrative process to use. The Deficiency Report (DR) shall always be used to correct problems judged to be significant. The criteria for judging problem significance is explained in section 8.2 of ! this procedure. Tae uutter of significance. however, does not precluce the use of a DR to correct a problem. This means that the euployee may initiate a DR at any time or in any situation to report problems or initiate changes to l improve plant reliability. l l 8.1.3 The acministrative process described above provide for safety and tecnnical review of recoumended changes and improveuents. A Da shall be initiated by tne reviewer if in his/her opinion the problem being corrected by enese processes is' considered significant. This will initiate a unnagement review into ] the root cause of the probleu and initiate the actions necessary to correct the prooien in a way to prevent its ! recurrence. 6.1.4 Personnel are not precluded from reporting significant safety concerns independently. Tney may nave their concerns addressed by either initiating a DR. reporting directly to plant supervision or manageuent, reporting via the Quality Concerns program, reporting directly to Quality Assurance or reporting directly to tne MRC. These are listed in the preferred sequence for reporting. The Manager of the Administrative. Finance and Human Resources Department shall assure that Docuuent Control posts the notices to individuals required by 10CFR19.11. including any notice of violation of radiological working conditions, proposed or imposed civil penalty or order issued pursuant to subsection B of 10CFR2. These documents shall be posted as a minimum in the hallway of the Service Building the main Control Room and the first floor hallway of the Simulator Building.
!!GR-0001 Rev. O
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I GEORGIA POUER COMPANY l RATCH NUCLEAR PLAUT l PAGE 10 0F 39 DOCU!!ENT TYPE: 1 DOCUMEUT !;U!I3ER: I ADMINISTRATIVE CONTROL PROCEDURE l 10AC-MGR04-0 DOCUhEht TITLE: I REVISION: I DEFICIENCY CONTROL SYSTEli I O l
. . l 8.1.5 Department Managers snall assure that personnel witnin their department are adequately trained in the cetnods of initiat-ing corrective action. Tuis training shall. as a minimuu.
quality tne incividual in the aduinistrative contro'is to initiate change where he/she identifies conditions adverse to quality. 8.2 SIGNIFICANT CuNu1TIONS ADVERSE TO QUALITY Significant Conditions Adverse to Quality will norually require - initiation of a Deficiency Report (DR). During the Operations phase of Plant flatch, the conditions described in Attachment 1 shall be considered Significant Conditions Adverse to Quality. 40AC-REG 02-0. Federal and State Reporting Requirements, defines tne requirements and responsibilities for identification. review, approval and submittal of reports tnat are either periodic or non periodic. When judging the. significance of'an event or condition. 40AC-REG 02-0 should be consulted. Attachuent 1 is a compilation of cne non periodic reporting requirenents contained in 40AC-REG 02-0. as well as those other conditions considered significant by plant management. _ U.3 DEFICIEUCY CLASSIFICATION i Deficiency Reports shall be classifiec as either operational 1 or unterial for reporting purposes. The classification shall be based on the criteria specified below. ) 8.3.1 Doe ra t io nn i Deficiency The deficiency shall be classified as 'an operational defici-- ency if it relates to procedures, personnel or operable equipment used in the operation of tne plant.- This includes those systems and controls used ror plant protection and for the protection of the public.- ,) 8.3.2 !!aterini Def ic ienev The deficiency shall be classified as a material deficiency if it relates to any activity that controls material from development of its specification to its installation and up to declaration of operability. MGR-0001 Rev. O
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I GEORGIA POWER COMPANY l RATCH NUCLEAR PLANT l PAGE 11 0F 39 DOCUP.ENT TYPE: l DOCUMENT JUMBEft: i 1 ADUINISTRATIVE CONTROL PROCEDURE I 10AC-:lGR04-0 DOCUMENT TITLE: l REVISION: 1 DEFICIENCY CONTROL SYSTEM l 0 8.4 DEFICIENCY PROCESSING I UilIE l ! l I i l If a deficient item needs to be installed. a Conditional l j l Release will be obtained from Engineering in accord- l l ance wita 50AC-trILO2-0. Identification and Control of I I Material and Equipuent. 1 I l A Deficiency Report (DR) similar to that shown in Attachnent 2 shall be used to report material and operational deficiencies as specified belou. Da sequential numbers shall be obtained l trom Quality Control. who snall maintain a DR log similar to l tnat shown in Attaennent 5. ! 8.4.1 ' Condition Ioentification Upon identification, the person icentifying the ueficiency shall couplete blocks 1 through 15. The Dn shall indicate tne af fected unit (s) and the report nuuber. Iteu 15. Shift Supervisor Notification, needs to be coupleted iumediately in caergency situations and unen pronpt action is necessary to preclude dauage to the plant (s) or personnel. Items 13. 15. and 16 through 20 are not required for material ceficiencies. 8.4.2 Shift Suoervisor Evaluation of Goerationni Deficiencies The applicable Shift Supervisor shall complete iteus 16 through 20. This section nay be completed after the fact where the condition or event is being corrected by imple-menting emergency procedures. In an energency condition. the Shif t Supervisor shall cake notification to plant management and outside agencies as identified in 40AC-REG 02-0. Federal and State Reporting Requireuents and as required by 30AC-0PS03-0. Plant Operations. The Shift Supervisor shall send the DR to the Superintendent of Regulatory Compliance or his designee. HGR-0001 Rev. O
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GEORGIA POWER C0!!PANY l dATCH NUCLEAR PLAllT I PAGE 12 uF 39 DOCUMENT TYPE: l JOCU E T LU"Ila.: I ADMINISTRATIVE CONTROL PROCEDURE l 10AC "GR04-0 DOCUt:ENT TITLE: 1 JLVISIOU: I ! DEFICIEUCY CONTROL SYSTci 1 0 - ! C.4.3 f!aterini Deficiene" Evaluation l LEGE I I i l Monconforming material installed in tne plant l
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I shall be hanoled as an operational deficiency. l ( (See Section 8.3). 1 1:sterial probleas shall oe evaluated and dispositioned by tne Superintencent of Ouality Control or his designee. If any of tne attributes itenized under iten 21 of'the DR cre checked "Yes", an engineerin; evaluation of tue dispo-sition snall be required and itens 22 tarou;n 26 snall be coupleted. If the deficiency is consi-cred potentially 10CFR21 reportaole .af ter evaluation by ne;ulatory Coupli-ance, a supplenental report sinilar to tant shoun in Attacauent 3
- shall be coupleted.
II all attribuces listed unuer iteu 21 are *no", the Superin- I tencent of 0C shall disposition aut assign uisposition res-ponsibility. These actions shall oc docuuenteu on a DR Continuation Sheet, similar to tnat snoun in Attachaent 2. :
, uncre necessary. Quality Control sna11 verify action )
conpletion and close out tne Du sy conpicting itens 26 and
- 27. The coupleted DR shall ta' en be forvarced to the Docunent Control Center for filing.
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8.4.4 Deficienev Sienificar.ce and aer.ortabiliev Evnluntion The significance and reportaoility of ceficiencies snall be reviewed by Regulatory Coupliance. Attachment 1 of tnis procedure identifies significant. conditions adverse to quality to assist in this evaluation. 40AC-REG 02-0, Federal and State Report Requireuents, iuentifies the reports , required of Plant Hatch. It also defines report development. ' review, approval and submittal responsiailities. The f assigned responsibility required in itcas 22 and 23 of tae DR should be consistent with these requireuents. 21GR-0001 Rev. O
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. CEORCIA POUER COMPA!!Y l RATG1 ilUCLEAR PLA!!T I PAGE 13 0F 39 DOCUMENT TYPE: i 00CUhEilT !!U::BER:
1 ADHIlilSTRATIVE CONTROL PROCEDURE I 10AC-:!G304-0 DOCUMEN'T TITLE: 1 REVISIO!!: l DEFICIE!!CY C0tlTROL SYSTEli l 0 8.4.5 Plant Review Board (PRB) Review I The PRB shall review the actions recommended to date by ! completing item 25 of the DR and forwarding it to t'e h General Itanager as necessary. The completed DR shall then be sent back to degulatory Compliance for corrective action and report tracking. 8.4.6 Root Cause Determination And Action Tnken To Prevent Recurrence Regulatory Compliance shall retain the original DR and forvard a supplemental report form to the department, section or individual assigned responsibility for determin-ing root cause and that corrective action necessary to preclude problem recurrence. The assigned department, section or inuividual shall take that action necessary to prevent problem recurrence and develop the necessary required reports. They shall assign a report nuuber in accoraance witu their department's directions. This report nuacer snall ue entered on tne' original DR. item 24. and trackeu oy Regulatory Compliance. Root cause analysis shall-determine the generic reasons for tne deficiency. The result of tnis analysis shall be classified as eitner an Equipment Failure. Procedure Inadequacy. Personnel Error, or Design Inadequacy. A supplemental report shall be used to describe the analysis. 8.4.7 Corrective Action Verification and Close Out The responsible department superintendent or nis designee shall confirm completed actions and inform Regulatory Com-pliance of completion. He shall report deficiencies identified in tne confirmation process to degulatory Compliance and initiate a deficiency report change in. accord- . ance with Section 8.8 as necessary. Quality Control shall I close out the DR wnen notified by Regulatory Compliance, verifying all corrective actions have been' coupleted. The
, individual performing tne verification shall sign and date item 27 upon completion. The individual assigned close out responsibility shall close the DR in the DR Log and forward the completed DR to Regulatory Compliance.. Regula-tory Compliance shall send the completed DR to Document Control for filing when satisfied that all actions have been completed.
HGR-0001 Rev. O
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CEORGIA POWER C0hPANY l HATCH NUCLEAR PLANT I PAGE 14 0F 39 DOCUMENT TYPE: l DOCUME!!T liUMBCR: 1 ADt1IIIISTRATIVE CONTROL PROCEDURE l 10AC-MGR04-0 DOCUMENT TITLE: 1 REVISI0ti: I
-DEFICIE!!CY CONTROL SYSTEM l 0* ,
8.5 TAGGIllG 8.5.1 A QC Hold Tag, similar to that shown in Attachment 6. shall be af fixed to deficient material items by Quality Control when required to prevent the inadvertent use .of that item i or equipment. - Use of these tags will be in accordance with approved Engineering Department procedures. j l 8.5.2 A QC Hold Tag Log. similar to that shown in Attachment 7. - I shall be used to recora the issuance and removal of tags from deficient items. l l 8.5.3 Isolation of deficient components ' or systems shall be I controlled in accorcance with 30AC-OPS 01-0. Control of Clearances and Tags. 1 o.6 DISPOSITIO!!ING I!ATERIAL DEFICIE.iCIES 1 3.6.1 The dispositioning process sha'11 consioer tae f ollowing: o.6.1.1 The specific desi;;n/ functional requireuents of the iteu or component. i l 8.6.1.2 The ef fect of the failure on these design / functional )
. requirements.
8.6.1.3 If deviation from the base design _ vill coupromise or degrade plan,t safety (i.e.. an engineering evaluation anc j in some cases a 10CFR50.59 evaluation uay be required). ' 8.6.1.4 Identification of tne neces'sary work activities required for rework. 8.6.1.5 Identification of design documents necessary to accomplish tne specific work activities required for J reVork. 8.6.1.6 Identification of special processes or' evaluations required to support the activity. MGR-0001 Rev. O
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GEORGIA POUER C0!!PANY l HATCH NUCLEAR PLANT l PAGE 15 0F 39 DOCUI1ENT TYPE: 1 DOCU:EUT hUMBER: I ADtlINISTRAT,IVe. CONTROL PROCEDURE l 10AC-IIGR04-0 DOCUMENT TITLE: 1 REVISION: I DEFICIENCY CONTROL SYSTEM l 0' . . 6.6.1.7 Identification of HDE and/or functional testing requirements. 8.6.1.8 An operability reassessment, particularly when it is appropriate to change from inoperable to operable states before, during. or after completion of itmas specified , i in tne cisposition. 8.6.2 listerial deficiencies shall be dispositioned in one of the , following ways:
- 8. 6 . 2.1 Use As Is: The nonconforming material is accepted uitnouc further work, because the deficiency will not degrade the quality of tne material or iteu or the .
functional capability of tue iteu. system or structure. f An engineer assigned by tne SPES shall write a justifica- , tion for tne deviation frou cesign requiremento. Any . l required document changes shall be appropriately identified. 1 8.6.2.2 depair: The deficient itaa is restored to a condition so that it functions reliably and safely even thougn it still any not conform to the original requirement. Procedures for repair. drawings sketches ano other supporting cocuments are attached to the IIHO as outlined i in 50AC-In!T01-0. :taintenance Program. i 8.6.2.3 Rework: The deficient item is made to conform to a prior specified requirement by renachining, reassembling, replacing. or otner corrective means. This disposition does not include processes uhien, for example, usy alter the properties of the base material or veld filler material.- Procedures for rework activity and sketenes or drawings are attached to the tiUO as outlined in 50AC-MNT01-0. Maintenance Program. 8.6.2.4 Reject: The material or item is unsuitable for its intended purpose and as a result may not be used. MGR-0001 Rev. O
I GEORGIA POUER COMPANY l HATCH NUCLEAR PLANT l PAGE 16 0F 39 1 DOCUMENT TYPE: 1 DOCU;tEUT DUM3Ca: l ADMINISTRATIVE CONTROL PROCEDURE l 10AC-MGR04-0 DOCUMENT TITL5: I aEVISIGH: 1 DEFICIENCY CONTROL SYSTEll l 0 , b.6.3 After approval, signatures are obtained. The following is required for eacn disposition. Use As Is and Rework dispositions shall be made on the Suppleuental Report Form. 8.6.3.1 Use As Is: A written justification by an assigned , engineer is required for the deviation from desi;n j requirements. j l 1 8.6.3.2 Repair: The superintendent of the group performing
- l repair or his designee shall ensure that repair activi-vities are accomplished in accordance with repair proce-cures, drawings and instructions. Upon completion of re-pair activities. QC shall verify acceptability on the DR.
8.6.3.3 Rework: The superintendent of tne group perforuing rework or nis designee shall ensure that necessary rework i activities-are accouplished in accordance witn approved departmental procedures, drawings and instructions. Upon coupletion of rework activities, QC shall verify accept-ability on the DR. 1 8.6.3.4 Reject: Requires removal of the item frou the work area and scrapping or returning the iteu to the supplier._ Use of tne item in a non-Q function is acceptable providing it is so stated on the DR disposition. 8.6.4 Disposition may authorize installation, operation or other activities associated witn a unterial deficient item providing the follouing conditions are met: 8.6.4.1 The DR describes the interim activity (installation, further testing, etc.). 8.6.4.2 The iten could not be used for a safety related function. 8.6.4.3 The deficient condition does not adversely affect the activity for which it is being used. 8.6.4.4 Identification and traceability of the deficient it em is maintained by conditional release defined in 50AC-MTLO2-0. Identification and Control of Material and Equipment. MGR-0001 Rev. O
I i I GEORGIA POUER COMPANY l RATCH tfUCLEAR PLANT l PAGE 17 OF 39 DOCUMENT TYPE: 1 DOCUMENT GUtlSCR: 1 ADMINISTRAT,IVE CONTROL PROCEDURE l 10AC-MGR04-0 DOCUMENT TITLE: l REVISION: I DEFICIENCY CONTROL SYSTEI! l 0' . . 8.7 ROOT CAUSE DETER;!INATION AND LONG TERM CORRECTIVE ACTION 8.7.1 Analysis to determine root cause and corrective action to prevent recurrence are only performed on those items identified in Attachment 1 (Significant Conditions Adverse to Quality). This analysis shall be recorded on the DR. j 8.8 DEFICIENCY REPORT CRAUGE I l 6.8.1 Uhen an individual nas a valid reason for changing a DR. j he or she will initiate a Deficiency Report Change Foru. -l similar to tnat shown as Attachment 4. The following l information will be provioed: 8.8.1.1 Type of DR to which the change applies; i.e. operational or material. ' l 3.8.1.2 uuuber of the DR to uhich the change applies. I 8.8.1.3 Reason for change. 8.8.1.4 Description of desired change. 8.o.l.5 Signature and date of individual requesting change. 8.8.2 The change form will be forwarded to Regulatory Coupliance. Regulatory Compliance will review the change foru and deter-uine the level of authority needed to approve the change. The change form will be foruarded to the nighest authority who has approved the DR to unich the'enange applies to date. 8.8.3 Disapproved and approved changes are attached to the original DR. I or 8.9 RECORDS Deficiency control documentation shall be maintained in accor-dance with 20AC-ADM02-0. Plant Records Management. MGR-0001 Rev. 0
I ATTACHIENT __1__ l l PAGE 18 0F 39 I GEORGIA POUER.COMPAliY l ATTACH!EllT: HATCH NUCLEAR PLA!!T l PAGE 1 0F 13 I , DOCU!ENT TYPE: 1 DOCUIEllT NU11BER: ) ADI'INISTRATIVE C0tiTROL PROCEDURE l 10AC-11GR04-0 l DOCU!.ENT TITLE: 1 REVISION: ) DEFICIENCY C0l! TROL PROCEDURE IO l 1 - ATTACH!iEllT TITLE. ~ SIGNIFICA!!T C0!!DITI0 tis ADVERSE TO QUALITY l CONDITIOff REQUIRElENT
- 1. Report of radioactive contamination 10CFR10.205(b)(2) !
of a package of radioactive material. I
- 2. Report of excessive levels of radiation 10CFR20.205(c)(2) external to a package of radioactive material. -
- 3. Theft or loss of licensed material 10CFR20.402(a)(b)
- 4. Incident involving byproduct. source 10CFR20.403(a)(b) or Special Nuclear Material. l
- 5. Overexposure and excessive levels of 10CFR20.405(a) radiation and concentrations of 10CFR19.13(d) radioactive material.
- 6. Any report of a failure of Plant Hatch 10CFR21.1(a) to comply with any applicable rule, '
regulation or order of the NRC or the Plant Hatch License issued by the NRC.
~
- 7. Repor*.ing of Def ects and Noncompliances A. Plant Hatch, or any licensed activity 10CFR21 at Plant Hatch, or a BASIC COMPO!!ENT supplied to or for Plant Hatch or its operation, f ails to comply with the Atomic Energy Act of 1954, as amended. or any applicable rule, regulation, order or license of the Commission relating to SUBSTANTIAL SAFETY HAZARDS.
B. Plant Hatch or any licensed activity at 10CFR21 Plant Hatch, or a BASIC C0!!PO!!ENT supplied to or for Plant Hatch or its operation contains DEFECTS which could create a SUBSTA!!TIAL SAFETY HAZARD. MGR-0009 Rev. O
F l , l ATTACHIENT ___,1___ l l PAGE 19 0F 39 l GEORGIA POUER COMPA!!Y l ATTACH!ENT: HATCH NUCLEAR PLANT l PAGE 2 0F 13 1 DOCUMENT TYPE: l DOCU!EtiT NUlIBER. ADMINISTRATIVE CONTROL PROCEDURE l 10AC-MGR04-0 g DOCUt4ENT TITLE: l REVISI0t!: DEFICIENCY CONTROL SYSTEM l 0 l' i ATTACHMENT TITLE: ' ~ SICNIFICANT CONDITIONS ADVERSE TO QUALITY . 1 CONDITION Rf.QUIRZZIENT C. The physical protection system for 10CFR21 Plant Hatch or a component supplied for that system contains DEFECTS or could allou an act of sabotage or terrorism to result in potential offsite exposure com-parable to those referred to in 10CFR100.11. D. The design, inspection, testing or consulting 10CFR21 services related to a BASIC C0!!PONENT ,(such
. as contract personnel provided for servicing or inspection of plant systems or equipment) contain deficiencies that could result in fail-ure of the BASIC C0lIPONENT to perform its safety function.
E. The services supplied in support of Plant 10CFR21 Hatch operational activities f ail to comply a with applicable technical requirements or contain errors that could cause a major reduction in the degree of protection a . BASIC C0:fPONENT or system provides to public
. health and safety. -
F. The QA records provided do not demonstrate 10CFR21 that BASIC C0!!PONENTS , supplied to or for Plant Hatch or a licensed activity at Plant Hatch meet the technical requirements of the l applicable procurement documents. G. The procurement documents f or any BASIC 10CFR21 1 CO:LPONENT or service important to saf ety contain defects which could result in a major reduction in protection provided for public health and safety. H. A Design Change for a BASIC C0![PONENT is 10CFR21 necessary in order to provide the required safety function. MGR-0009 Rev. O
l ATTACH!ENT _1_ l l PACE 20 0F 39 i GEORGIA POUER, C0!!PANY l ATTACH:ENT: HATCH NUCLEAR PLANT l PAGE 3 0F 13 I DOCU! INT TYPE: l DOCUMEUT nut 1BER: ADt!INISTRATIVE CONTROL PROCEDURE l 10AC-MGR04-0 1 DOCU: INT TITLE: l REVISION: l DEFICIE!!CY Col! TROL SYSTEM l, O l . ATTACHIENT TITLE: - - l SIGNIFICANT CONDITI0liS ADVERSE TO QUALITY CONDITION REQUIRDE!!T I. .A condition or circumstances has been 10CFR21 identified which involves a BASIC Col!PONENT and could contribute to exceeding a Safety Limit as defined in Technical Specifications. J. Plant Hatch, or any licensed activity at Plant 10CFR21 Hatch, or a BASIC COMPONENT suppled to or for Plant Hatch or its operations failed to have l the capability to prevent or mitigate the
]
consequences of accidents which'could result ! in potential offsite exposure comparable to l those referred to in 10CFR100.11. K. Plant Hatch, or any licensed activity at the 10CFR21 Plant Hatch, or a BASIC COMPONEUT supplied to I or for Plant Hatch or its operation contains j DEFECTS which could lead to a failure to j maintain the integrity of the Reactor Coolant ; Pressure Boundary. I L. Plant Hatch, or any licensed activity at 10CFR21 Plant Hatch, or a BASIC C0!IPONENT supplied to or for Plant Hatch or its operation contains DEFECTS which could cause a major degrada' tion of essential safety related equipcent necessary to assure the capability to shut down the reactor and maintain it in a safe shutdown condition. M. DEFECTS are present which could lead to a 10CFR21 single fault failure of a BASIC COMPONENT supplied to or for Plant Hatch or its opera-tions and its redundant component at the same time and could cause a Safety Limit to be exceeded or could lead to a moderate exposure to or release of licensed material. MGR-0009 Rev. O
ATTACKtENT __1__ l l PAGE 21 0F 39 I GEORGIA POUER COMPANY l ATTACH!ENT: HATCl! NUCLEAR, PLANT l PAGE 4 0F 13 1 __ DOCUMENT TYPE: l DOCU!E!!T NUIEER: ADMI!!ISTRATIVE CONTROL PROCEDURE l 10AC-HGR04-0 l DOCUMEllT TITLE: l REVISIOU: DEFICIENCY C0t; TROL SYSTEM l 0 1 ATTACHMENT TITLE: . .
. SIGNIFICANT CONDITIO!!S ADVERSE TO QUALITY - -
CONDITIO!! REQUIREMENT N. Major deficiencies involving design. 10CFR21 construction, inspection, testing or use of Plant Hatch or any licensed material under its control or possession could cause a SUBSTANTIAL SAFETY HAZARD.
- 8. Detected leak of a sealed radiographic source. 10CFR34.25(d)
- 9. Immediate notification requirements for 10CFR50.72 operating nuclear power reactors.
9.1 The declaration of any of the Energency 10CFR50.72(a)(1)(1)(i) Classes with initiation of the Emergency l Implementing Procedures. 9.2 The initiation of any nuclear plant 10CFR50.71(b)(1)(i)(A) shutdoun required by plant's Technical Specifications. 9.3 Any deviation from the plant's Technical 10CFR50.72(b)(1)(i)(B) Specifications authorized pursuant to 10CFR50.54(X). This states that a licensee may take reasonable action that departs from a license condition or technical specification in an emergency when the action is innediately needed to protect the public health and safety and no action consistent with the license condition and technical specifications that can provide adequate or equivalent protection is immediately apparent. 9.4 Any event or condition during operation that 10CFR50.72(b)(1)(ii) that results in the condition of the nuclear power plant, including its principal safety barriers, being seriously degraded; or results in the nuclear pouer plant being:
- A. In an unanalyzed condition that significantly compromises safety; HGR-0009 Rev. O
i i ATTACHIENT __ l_ l l l PAGE 22 0F 39 { l \' GEORGIA POWER C0llPAtlY l ATTACHIENT: HATCH NUCLEAR. PLANT l PAGE 5 0F 13 I l DOCUMENT TYPE: l DOCUIENT NUllBER: ] ADtIINISTRATIVE CONTROL PROCEDURE I 10AC-MGR04-0 I DOCUMENT TITLE: l REVISIO:!: DEFICIENCY CONTROL SYSTEM l 0 , I l ATTACH!ENT TITLE: . . SIGNIFICANT CONDITIONS ADVERSE TO QUALITY
- - l CONDITION REQUIREMENT B. In a condition that is outside the design ,
basis of the plant; or C. In a condition not covered by the plant's operating and emergency procedures. l 9.5 Any natural phenomenon or other external 10CFR50.72(b)(1)(iii) l condition that poses an actual threat to I the safety of the nuclear power plant or significantly hampers site personnel in the performance of duties necessary for the safe operation of the plant. 9.6 Any event that results or should have 10CFR50.72(b)(1)(iv) resulted in Emergency Core Cooling System (ECCS) discharge into the reactor coolant system as a result of a valid signal. 9.7 Any event that results in a major loss of 10CFR50.72(b)(1)(v) energency assessment capability, offsite response capability (e.g., significant portion of Control Room indication. Emergency Notification System or offsite notification system). 9.8 Any event that poses an actual threat to 10CFR50.72(b)(1)(vi) the safety of the nuclear power plant or , significantly hampers site personnel in the performance of duties necessary for the safe operation of the nuclear power plant including fires. toxic gas releases, or radioactive releases. 9.9 Any event. found while the reactor is shut 10CFR50.72(b)(2)(i) down, that, had it been found while the re-actor was in operation, would have resulted in the nuclear power plant, including its principal safety barriers, being seriously degraded or being in an unanalyzed condition that significantly compromises plant safety. MGR-0009 Rev. O
t ? I
- ATTACHIZHT -,1 -. l l PAGE 23 0F 39 i
GEORGIA PO'JER CO lPANY l ATTACHMENT: HATCH NUCLEAR PLANT l PAGE 6 0F 13 i I DOCUFINT TYPE: l DOCUlIENT NUMBER: i ADt!INISTRATIVE CONTROL PROCEDURE l 10AC-11GR04-0 I l I DOCUMENT TITLE: l REVISION: ) DEFICIENCY CONTROL SYSTEM l 0 l 1- 1 ATTACEMENT TITLE: . . I SIGNIFICANT CONDITIONS ADVERSE TO QUALITY - l NOTE l , I l I l Actuation of an ESF. including the RPS. that results l i i from and is part of the preplanned sequence during l 1 l testing or reactor operation need not be reported. l e 9.10 Any event or condition that results in 10CFR50.72(b)(2)(ii) 4 manual or automatic actuation of-any l Engineered Safety Feature (ESF). including the Reactor Protection System (RPS) that are needed to: A. Shut down the reactor and maintain it in a safe shutdown. condition. B. Remove the residual heat. - l l C. Control the release of radioactive material, or D. Mitigate the consequence of an accident. 1 9.11 Any event or condition that alone could have 10CFR50.72(b)(2)(iii) prevented the fulfillment of the saf ety function of structures or systens that are needed to:
~
A. Shut down the reactor and maintain it in a safe shutdown condition. B. Remove the residual heat. ; v f C. Control the release of radioactive material or D. Mitigate the consequences of an accident. FER-0009 Rev. 0
ATTACil:!E;.T __.1___ l l PAGE 24 UF 39 I GEORGIA POWER C0;;PAUY l /sTT/.Cli:2..T:
;iATCll JUCLEAR PLANT l PACC 7 UF 13 i
DOCU!IENT TYPE: I DOCU:5.;.T ob.:Jud: AD:!INISTRATI.VE COUTROL PROCEDUaE I 10AC-!.G a04-0 l DOCU!IliT TITLE: l REVISIOU: DEFICIEi!CY COUTROL SYSTEi! l. O I - ATTAChi:iEh1 TITLE: -
~
SIG:11 FICA 1:T Cot!DITIOUS ADVddSE TO QUALITY f COUDITI0d 2EQUIhEdEi!T- I 1 9.12 Radioactive caterial releases 10CFL50.7 2( o )( 2)( iv ) A. Any airoorne radioactive release that exceeus two tiaes tne applicaule concentra- I tions of the limits specified in Appenoix B. . j Table II of Part 20 of 10CFR20 in un- q restricted areas, when averaged over a time periou of one nour.
- d. Any liquid erfluent release.taat exceeds two tices t:ie Ituitin; coubined ::axiuun Permissivie Concentration (.':PC) (see Jote 1 of Appendix B l co Part 20) at cae point of entry tuto tne receivia:; fator (i.e. unrestrictea area) for all racionuclices c:: cept critiuu anc tissolvec noole gases, when averaged over a tiae period or ene .icur. (Iu.ewtate t.ottrications ande under tais paragraph also satisry cae require-
..ents or Ice.; 4 of tais attacament). .
i i
~
v.13 Any event requiring the transport of a 10Cb R50. 72(b )( 2 )(v ) radioactive contaminated person to an offsice uedical facility for treataent. 9.14 Any event or situation. related to tne health and safety of the public or on-site personnel, or protection of tue environuent. for which a news release is planned or notifi-cation to other governuent agencies nas been or will be mace. Such an event uay include an on-site fatality or inadvertent release of racioactive contaminated Laterials. I!Ga-0009 Rev. 0
. 1 ATTACHIENT 1_ l l PAGE 25 0F 39 l
GEORGIA POWER COMPANY l ATTACH:ENT: IIATC11 NUCLEAR' PLANT l PAGE 8 0F 13 i DOCUMENT TYPE: l DOCUIEUT MUtBER: ADMINI,STRATIVE CONTROL PROCEDURE I 10AC-!!CR04-0 l DOCUi!ENT TITLE: 1 REVISION: DEFICIENCY CONTROL SYSTEM l 0 l' ATTACHMENT TITLE: . , SIGUIFICANT CONDITIONS ADVERSE TO QUALITY . CONDITIO!! REQJIL.hENT
- 10. Licensee Event Reportable Plant Hatch shall report an event regard- 10CFR50.73(a)(1) less of the plant mode or power level, and regardless of the significance of the struc-ture, system. or component that initiated the event for the balov listed items. -
10.1 The completion of any nuclear plant 10CFR50.73(a)(2)(i)(A) shutdown required by the plant's Technical (See Item 9.2) Specifications; or 10.2 Any operation or condition prohibited by 10CFR50.73(a)(2)(i)(B) the plant's Technical Specifications; or 10.3 Any deviation from the plant'.s Technical 10CFR50.73(a)(2)(i)(c) Specifications authorized pursuant to (See Item 9.3) 50.54(x). This states that a licensee may take reasonable action that departs from , a license condition or technical specification in an energency when the ac' tion is immediately i needed to protect the public health and safety and no action consistent with the license condition and technical specifications that can provide adequate or equivalent protection is inmediately apparent. 10.4 Any event or condition that resulted in 10CFR50.73(a)(2)(ii) the condition of the nuclear power plant (See Item 9.4) including its principal safety barriers, being seriously degraded, or that resulted in the nuclear pouer plant being: A. In an unanalyzed condition that significantly compromised plant safety; HGR-0009 Rev. O
1 8 ATTACHIENT ,_1 l l PAGE 26 0F 39 i GEORGIA POUER C0!!PAliY l ATTACH!EIIT: t HATCH NUCLEAR PLANT l PAGE 9 0F 13 ! I DOCUIENT TYPE: l DOCU:ENT NULBER: ADt!INISTRATIVE CONTROL PROCEDURE I 10AC-l!CR04-0 l DOCU ENT TITLE: l REVISIO!: DEFICIENCY C0!! TROL SYSTEM i 0 l 1-ATTACHtENT TITLE: -
- SIGIIIFICANT C0tIDITI0 TIS ADVERSE TO QUALITY . 1 l
j CONDITIO!i REQUIREZENT B. In a condition that was outside the design basis of the plant; or C. In a condition not covered by the plant's ) operating and energency procedures 10.5 . Any natural phenomenon or other external 10CFR50.73(a)(2)(iii) j condition that posed an actual threat to (See Item 9.5) l the saf ety of the nuclear power plant or significantly haupered site personnel in the performance of duties necessary for the safe operation of the nuclear pouer plant. l l NOTE l i I I Actuatiot of an ESF. including the RPS. that resulted l l from and uas part of the preplanned sequence during i i testing or reactor operation need not be reported. l
. 10.6 Any event or condition that resulted in 10CFR50.7 3(a)(2)(iv )
manual or automatic actuation of any (See Item 9.10) Engineered Safety Feature (ESF). including the Reactor Protection System (RPS). A. Shut down the reactor and maintain it in a safe shutdown condition. B. Remove the residual heat. l C. Control the release of radioactive material. or i D. Mitigate the consequence of an accident. MGR-0009 Rev. O i l l l l j
ATTAC 112HT 1 l l PAGE 27 0F 39 i CEORGIA POWER C0!!PANY l ATTACUtENT: HATCH NUCLEAR PLANT l PACE 10 0F 13 I DOCUIENT TYPE: 1 DOCU;2NT MUllBER: ADMINIETRATIVE CONTROL PROCEDURE i 10AC-l!GR04-0 1 DOCUl;EliT TITLE: 1 REVISION: DEFICIENCY COMTROL SYSTEll 1 O I - ATTACHMENT TITLE.
- SIGUIFICANT CONDITIONS ADVERSE TO QUALITY l NOTE l l l
! Events covered in paragraph 10.7 of this listing may l l include one or more procedural errors, equipment fail- .1 i ures, and/or discovery of. design, analysis, fabrication, i I construction, and/or procedural inadequacies. However. l
+
l individual component f ailures need not be reported pur- l l suant to this paragraph if redundant equipment in the l l .same system was operable and available to perf orm the l
;l required safety function. I i
10.7 Any event or condition that alone could 10CFR50.73(a)(2)(v) have prevented the fulfillmentaof the -(See Item 9.11) safety function of structures or systems that are needed to: A. Shut doun the reactor and maintain it in a safe shutdoun condition; i B. Remove residual heat;
^
C. Control the release of radioactive material; or D. Mitigate the consequences of an accident. 10.8 Any event where a single cause of condition 10CFR50.73(a)(2)(vii) caused at least one independent train or channel to become inoperable in multiple systems or two independent trains or channels to become inoperable in a single system designed to: A. Shut down the reactor and maintain it in a safe shutdown condition; B. Remove residual heat;
!!GR-0009 Rev. O
s
\
ATTAC.E.E!?T __1__ l
)
l PAGE 26 0 F 3 ') l GEOP.GIA POUER COLPANY l ATTACli!DT: ilATCli ifUCLEAR PLANT l PAGE 11 0F 13 i DOCU!I!;T TYPE: l DOCU:21:T NU::BC%: ADMINISTRATIVE C0llTROL P.'.0C;DU.<C i 10AC-i. gnu 4-0 l DOCUMENT TITLE: l P.EVISIOG: DEFICIEI:CY CONTROL SYST' &i 1 O I - ATTAC111214T TITLE: - SIG!lIFICA!!T COUDITIOMS ADVERSE TO QUALITY C0tIDITION REQUIRE!IllT l C. Control the release of radioactive material; or l D. !!itigate tue consequences of an accident. 10.9 Radioactive unterial releases 10CFR50.73(a)(2)(viii) (See Iten 9.12) . A. Any airborne radioactivity release tilat ; e:teeeded tuo cines the applicable concen- j trations of tne liniLs specified in Appendix l L. Table II of Part 20 of this chapter in j unrestrictec areas, uhen averaged over a true 1 period of one hour. j i D. Any liquia effluent release tant exceedeu tuo-tines , the liuttia; couoined .:a::inua Fernissiole Concentra-tration (:!PC)(See Hote 1 of Appendix U to Part 20 of this c~aapter) c cae point of entry into tue receiving unter (i.e., unrestricted area) for all racionucituos e: cept tritiuu anu aiscolveu couie ucca, when averaged ] over a time period of one hour. ! 1 10.10 Any event taat poseu an actual tarest 10CFu50.73(a)(2)(x) l to tne safety of tne nuclear pouer plant (See Iten 9.0) I or significantly haupered site personnel in j the perforuance of duties necessary for the safe operation of the nuclear pouer plant incluain; fires, toxic jas releases, or radioactive releases.
- 11. Disability of an URC Licensed Operator 10CFR50.41
- 12. Accidental Criticality or Loss of Special 10CFR70.52(a) i lluclear Material (SN11)
- 13. Thef t or Unlawful Diversion of SUlt or 10CFR70.52(b)
Atteupted Theft or Unlauful Diversion 10CFR73.71(b) of Sil!!
- 14. SUI! exceeding the required limits specified 10CFR70.53(b) tor the annual inventory report 1GR-0009 Rev. 0 1 -
ATTAC11!:E!!T __,,l_ l l PAGE 29 0F 39 ,
; r GEORGIA POWER COMPANY l ATTACHIENT:
HATCH UUCLEAR PLA!!T l PAGE 12 0F 13 l DOCUMENT TYPE: l DOCUIENT NUllBEP: ADMI!!ISTRATIVE CONTROL PROCEDURE l 10 AC-1tG R04-0
~ . ,
l DOCU!!EUT TITLE: l REVISION: I DEFICIEUCY C0!! TROL SYSTE!! l 0 l* ATTACHIIENT TITLE: * *
' ~
SIGNIFICAi!T CONDITIONS ADVERSE TO QUALITY . CONDITION REQUIREHENT !
- 15. Radioactive Material Package effectiveness 10CFR71.95 reduction during the transportation of radioactive material i
- 16. Failure to receive periodic calls during 10CFR73.26 shipment of SUM by road or rail -
- 17. Failure of a shipment of SUM to arrive at 10CFR73.17 (b )
its destination
- 18. Explicit tnreat involving SNM 10CFR73.71(c)
- 19. Major loss of physical security effective-- 10CFR73.71(c )
ness
- 20. Potential threat involvin; SInt 10CFR73.71(c)
- 21. toderate loss of physical security 10CFR73.71(c) effectiveness
- 22. Bodily injury or property damage from 10CFR140.6(a) possession of radioactive material or use of radioactive material that results in an idenity claim
- 23. Discharge of oil or oth'er pollutant materials 33CFR153 into navigable waterways 40CFR110
- 24. Violation of hazardous vaste management 40CFR260 and 265
- 25. Incidents involving hazardous materials 40CFR171.15 ETS 5.7.2a
- 26. Actuation and injection by HPCI, LPCI Unit 2 TECH. SPEC. 3.5.1; or core spray 3.5.3 HGR-0009 Rev. 0
t .. a m . ATTACEIINT. l l
, 1 PAGE 30 0F 39 i
GEORGIA POUER C0!!PA!!Y l ATTACH 12NT: HATCH NUCLEAR- PLANT l PAGE 13 0F 13 ! I DOCUlINT TYPE: 1 DOCUt2NT NUI3ER: ADt!INISTRATIVE CONTROL PROCEDURE l 10AC-!!GR04-0 l DOCUME!!T TITLE: 1 REVISION: DEFICIEl:CY COIITROL SYSTE!! l 0 1- - ATTACEMENT TITLE: * - SIGl!IFICANT CONDITIONS ADVERSE TO QUALITY , C0!!DITION REQUIREIENT
- 27. Loss of fire protection redundancy Unit 2 TECH. SPEC. 3.7.6.1
- 28. Seismic event Unit 2 TECH. SPEC.
4.3.6.2.2
- 29. Reportable Occurrences TECH. SPEC. 6.6 - -
(See Item 9 and 10)
- 30. Safety Limit violation TECH. SPEC. 6.7
- 31. Release of radioactive noble gas ETS 2.1.3.F and 5.7.2
- 32. Unusual environmental events ETS 4.2 and 5.7
- 33. Hazardous waste spills GEPD
- 34. Noncompliance with NPDES daily mar.inum NPDES peruit releases
- 35. Injury or Occupation disease OSHA-
- 36. Repetitive problems indicating General Manager ;
administrative controls are inadequate ' or insufficient
- 37. Negligence or disregard of management General llanager policy defined in administrative controls or procedural requirements
- 38. Follovup of review of corrective action General !!anager in responge to NRC required action has not been taken or has been improperly-accomplished.
/
!!GR-0009 Rev. 0
1 I l l ATTACHMENT 2 l [ PAGE 31 0F 29 l 1 i CEORGIA POWER COMPA!!Y ! ATTACHMENT: ) HATCH NUCLEAR PLANT l PAGE 1 0F 3 1 DOCUMENT TYPE: l DOCUMEllT NUMBER: ADMINISTRATIVE CONTROL PROCEDURE l 10AC-MGR04-0
- . I DOCUMENT TITLE: l REVISION:
DEFICIE!!CY CONTROL SYSTEM l 0
.I ATTACHMENT TITLE: . .
l DEFICIENCY REPORT - von-applicable blocks must be marked "N/A"** Fage 1 of DEftCIEricT REPORT AFFECTE, tr r .*(3 ): ( ) coit. ( ) T*.to. ( ) ONE AND Tuo 3 REPORT nut 3ER s ,, 1 TTFE OF DEFICICJCT ! ( ) 0FEllAT10t!AL 3 ( ) IIATERIALS (111 SECTt0N 8.3) g
......................................................................................... l 2 ITCt DESC11FTt0N : . 3 ITCt LOC,\Troti 4 I:FL UUIT,ER($) '
S ~Q~ CLAS$ . 6 P.O./ SPEC. No. t . 7 CokTRACTOR / SUFFLt!E s . 8 MIR NO. I j g . . . t
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13 Evtt!T DATC s J., J ,, TUE . DISCOVERY DATE : ,, / ,_/ TE2 ]
......................................................................................... 1 14 REFORTED BY AND DATE : . 15 $MIFT suPERvis0R :30TtFIED 6 DATE: fn2 i JJ. J J--. !
......................................................................................... 1 16 DetEDIATE UOTIFICAft0N E! QUIRED ( ) NO 1
( ) TES : ,,,,EOUR REPORT !!Ut3ER (l
. . . . . . . . . . . . . . . . . . . . . . .'A DE A3 FEE 4 17 REACTOR FASAMETERS : Milt t FStG s .F THERl;AL F0VER FRE35URE TE.*.FEIATU2E 18 HOCE SWITCH FOSITI0lf ( ) Rtit! . ( ) STARTUF A:ID it0T STAED8Y (
( ) 5HUTDOWN . ( ) REFUEL 19 CORRECTIVE ACTIDH(s) TAEEN I A. TECH SPECS. RIQUIRED ACTtot:(8) TALE!rt ( ) TES 3( ) !;0 g( ) 1;/A ,
- 1. IF TEs. List ATFLtCAsLE Tmt. srtCs. stCT10t'(s) Atro sc::rAttzt Tut ACTt0:1 l 1Auctn I
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- 2. IF :0 OR N/A. ExF1.A1;I ,
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- s. LCO IntTIATED t ( ) YES 3 LCO tfU 3EP.: 3( ) :.0 i C. w0 n:tTIATED t ( ) TEs . :nm :u:me.n .: ( ) :o !
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1 1 ATTAChKENT _2 , l I PAGE 32 0F 39 1 1 ! GEORGIA POWER C0!!PA!'Y l ATTAClitiE!"1: l HATCH NUCLEAR PLAllT . I PAGE 2 0F 3 l l DOCUl!EliT TYPE: 1 DOCU!T.hY hunbER: j ADMI'NISTRATIVE C011 TROL PROCEDURE i 10AC -IIGF.04-0 )
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DOCUMENT TITLE: . l EEVISI0li: DEFICIE!;CY CollTROL SYSTE11 1 0 . , l' ATTACEMENT TITLE 1 .-
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DEFICIEllCY REPORT
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DEFICIEilCY REPOCT D 1 21 FOR MATERIAL des ONLYs . 15 Tl!!S DR POTUTIALLY 10CTR21 REPott!A2LET ( ) TES 3 ( )M . t
. 15 THE ITCl Q LISTED A!!D D157051T10;;ED *REPA!E" 02 "D5E.A313"? ( ) YES 3 ( )W . j 3
IF Berit AAZ AHS;IEEED "m0". TKE RD4A!!rDEA 0F Tlit$ FOR t 18 TO RC4Alli BLA;3E. A!;D T1LE . ' SURE!!!TE:IDDT of QC WILL vtR1FY COR2ECTIVE ACT10h A.r0 CLOSEDUT Tel! D1. .
. 1F EIT11C IS A :SWE*ED "YES". TEE SUPERINTE:DD:t OF QC VILL FORWARD TEL F02;l Fod .
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............................................................................................ {
22 FURT11C CORRICTIVE ACT10tl LEQUIRED ( ) YES 3 ( ) ND . IF TES : I!"DIVIDUI.L RESP 0h813LE FOR CORRICT!YE ACT103s LATE 3Y UHICE CORRICT!W ACTICII !!UST SE C0::PLET D s I I l
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. 1 1 ATTAC31EN T ,,,,2__,,, l l PAGE 33 0F 39 I GEORGIA POWER C0 !PANY l ATTACHMENT: HATCH NUCLEAR- PLANT l PAGE 3 0F 3 l ) DOCUIENT TYPE: l DOCUMENT nut!BER: AD!IINISTRATIVE C0tlTROL PROCEDURE l 10AC-HCR04-0 i l DOCUMEUT TITLE: l REVISI0ti: DEFICIEtiCY CONTROL SYSTEM l 0 l'
- ATTACHtENT TITLE: , ,
DEFICIENCY REPORT - Pn. ee _,, DEFICIENCY REPORT CONTINUATION SHEET TYPE OF DR : ( ) OPERATI0t!AL 3 ( ) alATERIAL 3 LEPORT NtDISEE _* _
- _
TO USE THIS PACE: (1) INDICATE Tilt SLOCK frU"BER TP UH1Cil TOU WISH TO ADO A00!T101:AL If! TOR:WT!DH ; (2) ADD Tl!E DESIRED !!!FOR;WTION & A!!D (3) SIGN Aff 0 DATE T1115 FACE i .. 1
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. . l ATTACIIIENT _,3_. l . l PAGE B4 0F 39 l
GEORGIA POWER COIEA!!Y l ATTACHIENT: HATCH NUCLEAR PLANT l PACE 1 0F 1 l DOCUtENT TYPE: 1 DOCUllEI!T nut 1SER: ADMINISTRATIVE CONTROL PROCEDURE l 10 AC-!!GR04-0 DOCU!ENT TITLE: l REVISION: DEFICIEllCY CONT *l0L SYSTE1 1 0 l'
- ATTACHIENT TITLE: , ,
SUPPLDENTAL REPORT - Pa;e of - SUFFLCEllTAL REFORT TYPE OF DR : ( ) OPERATIONAL g ( ) MTERIAL 3 REPORT NU 18ER: *
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GEORGIA POUER COMPANY l ATTACHIENT: ) ' HATCH NUCLEAR- PLANT l PAGE 1 0F 1 I , DOCUMENT TYPE: l DOCU! INT NU13ER: ADMI:11STRATIVE CONTROL PROCEDURE l 10AC-HGR04-0 DOCUIENT TITLE: l REVISION: DEFICIENCY CONTROL SYSTEM l 0 ) I ATTACHMENT TITLE: " ~ DEFICIENCY REPORT CHANGE FORI! . OEFICICICT REP 07.T Cua:!CE For.:t TTFE OF DR ( ) OPERATIONAL 3 ( ,)flATERIAL 3 REPORT NU'3ER ,,. ,,,,,.=_ j 1 REA$0T. FOR C11A;;C'4s DESIKID CA:CE : ) I I l ll,
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GEORGIA POWER,COIIPANY l ATTAC111ENT: HATCH NUCLEAR PLANT l PAGE 1 0F 1 I I l DOCU! INT TYPE: l DOCUMEtlT NU".BER: l ADt1INISTRATI4E CONTROL PROCEDURE l 10AC-MCR04-0 l DOCUIE!!T TITLE: l REVISION: DEFICIENCY CONTROL SYSTEtt 1 O I . ATTACHMENT TITLE. DEFICIENCY REPORT LOG GEDRG L) POUCE COHFANY j RATCH WCLEAR FLA!!T l PACE 1 0F 1 t F01:1 IITLE: . DETICIE!!CT REFORT LOG UNIT W:SERI ( ) ONE 3 ( ) t*,?O Da i DE 1 DATE i TITLs CA DESCRIPTION lHOLD TACI C0 ERECTIVE ACTIQ!! 1 EClMK3 W)2ER I CRA:CE I LOCC ED 1 0F THE DETICIE;tCT l T53/ :0t i e
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Interoffice Correspondence Georgia Power d I . Date: June 18, 1985 j GM-85-532 Re: Plant E. I. Hatch Update Response to SOER 85-1 l l From: H. C. Nix , j
. l To: J. T. Beckham l l
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- 1. This is an update for the response to SOER 85-1; " Reactor Cavity ..
Seal Failure." In our response (GM 85-323) we committed to the ; following actions: - l l
- a. Consider providing separate air supplies to redundant seals !
and consider using check values and accumulators in these lines. l l Status: Separate air supplies were provided to the redundant seals. It will not be necessary to I provide check values and accumulators for these lines since separate air supplies were provided. . l; No further actions are necessary for this ( recommendation. (Recomq[,endation Sa) . ' fM i b. An investigation by Engineering is being performed to determine tMe inspection criteria and procedural I requirements. An initial visual inspection of the Reactor Cavity Seals will be performed during the Unit 2 refueling outage as part of the Engineering investigation. Status: An inspection of the refueling bellows for Unit 2 has been performed, and no problems were found. Procedure HNP-1/2-6702, " Reactor Pressure Vessel Disassembly" will be revised during the Procedure Upgrade Program, to include a step for visually inspecting the Refueling Bellows to ensure no leakage and seal integrity. This procedure revision will be completed by June 1, 1986. During the interim, Engineering will issue a Maintenance Work Order (MWO) to have the Refueling Bellows inspected prior to moving irradiated components . (b)
- c. Determine actions to be taken when'the main steam line plugs are being utilized and an inboard MSIV is to be repaired or removed.
, Status: No further actions are necessary for the following reacons:
F<a n-V7-76 D//6,
Y 4 - ..O Update Response to SOER 85-1 Page 2 l
- 1) Maintenance activities are not usually performed on MSIVs when the main steam line plugs are installed.
- 2) If maintenance is performed on the MSIV's with the main steam line plugs, it should be noted that the main steam l line plugs have two seals. One is a pneumatic seal and the other is an 0-ring seal; therefore they are single failure proof. Misalignment can be checked by opening drains in the main steam lines prior to performing work on the inboard MSIVs or safety relief value.s
- 2. An update report giving the status of item 1.b. above will . be submitted by June 10, 1986. .
Please contact C. R. Goodman at extension 2909 if you have.any further questions. M M H.-C. pp GeneraF Manager . I bdJ g HCN/SBT/C G/ulz f xc: C. T. Jones L. T. Gucwa
, P. E. Fornel T. A. Seitz -
C. R. Goodman Document Control (SOER 85-1) l File '
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v. f i interoffice Correspondence GeorgiaPower d
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S Date: February 3rd, 1986 LR-0PS-002-0286 Re: PLANT E. 1. HATCH
+
Hose Station Valves ! a' ) g Fmm: H. L. Sumner i To: Department Managers { k i
, Positioning of hose station valves shall be performed by Operations personnel only except when performing normal surveill-ance and instrument calibration procedures that require.the use of a hose station. ?
(. If a hose is to be connected to a system such as Service
- s. Air, Demin Water, PSW, etc., the person who wants to use the hose
( station must make the connection including installation of his y own isolation valve that he will control. He will then notify the Shift Supervisor.
- The Shift Supervisor will have the valve tagged open on a cl ea ra nc e .- When the connection is no longer needed, the Shift Supervisor will be notified to release the clearance and close the valve. The connection will then be removed.
. If the hose connection is to be used for a short period of 1 time, an Operator may be sent to open it and stay with it until he recloses it.
9 i
. Please call me if you have any questions. ..,,
l I' l "A C f 46vV) Y l/ M , I
. L. Sumner Manager of Operations HLS:jb1 c xc: T. V. Greene J. C. Lewis gcgg . y 7- 76 Dj,y mma ,
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. GERGIA POWER, COMPANY l _ 'g - PIANT E.I. ELT S l
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inocuumr mounza: Imisim.m: MAMCEMENT MEMD- MMUER'S BnrJN IM-MGR-002-0686 l N/A
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[ M T ISSUE: 6/10/86 To: ALL PERSONNEL i g Memo: Procedural compliance must be ass'u d in the ! day to day operation of Plant Hatch;and cannot be over emphasized.- However, complying j with th'e procedQf<e does not release you fromlusing good judgement, 1 common sense, &nd careful attention to detail. In particular, notes l
.i and cautions in procedures contain flags and' reminders of interface with other systems, potentiil difficulties and consequences.
Remember, only people.make mistakes, procedures take no action by J themselves. 1
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i THIS MEMO WILL TERMINATE ON JULY 10, 1986. _a j : t generalManagey / l () MGR-0001 i Fe2 4 - S ? -76
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,-' MPL NO: 2 9M*M d O
RTTP5: Gl k O&* 4 lla* W .-_
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' PREQUENCY: - _ _ _ As Reesired COMPLETED BY: d r,.' ,
[detI4 , Ad-Id DATE COMPLETED: I BAYS REVIEWED TEIS DATA PACKAGE FOR COMPLETENESS AMD AGAIRST ACCEPTANCE CRITERIA IN ACCORDANCE WITE 10AC-MGR-903-0, 30AC-OPS-001-0, 30AC-OPS-003-0. UNACCEPTABLE ACCEPTABLE DATE - IEw3D r"/4/I4 y
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TIME IN _
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^p.....,.......................................~......._m REMOVAL FROM SERVICE DESCRIPTION COMPLETED sr STEP ......
Notify Shift Supervisor that g-P.1 . - . .the . . .in.strument . - is to be remov
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Open link _ ~ h[g
" _ at panel Open link _ t 'g 9 Lift wire _ f~
_ at pane 1 #ltf 6 /instrumen....
... ...... ..... . ._ at pane
. _ . 139UWinstrument
........... p/f Lift wire. . . . . . . . . . . . --
Place jusper across terminals A and C._ - . . . 9 __ g - 4, 0t' y P.3 ... ............ _Close isolation valve 7At-A3ntf' g - -
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.. _ . _ VV1 F.4 Open vent valvs
. . . . . . . . . . . . . . .M . . 7Y9 . . . -_ DV1 g -
Open drain valve .. _ .
; ... ............... . ...... LEVEL INPUT A8 L3FT AS FOUND (STEP G.10) --
(STEP G.5) y EXPECTED
-~......-.......-
-.........q.........- sw 62
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sw #1 sw 92 SY8 TEM sw pl .......... SW 62 ... . .... RESPONEE 8w #1 klg f... .
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N/A - Page 2 of 3 57CP. CAL-094 2 RSS
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DATA PACIAGE 1 (CON'T)- ROBERTSEAM LEVEL SWITCE CALIBRATION PLACING ______..____.INTO SERVICE COMPLETED VERIFIED STEP DESCRIPTION EY* SY NO _ _ _ _ _ . . _ _ _ _ .___...__.
. ______ ___________.____.__.______- ....._~_______.
Level SW. Roset, All Associated Alarms & I.1 Trips Roset ______.._ .________--__ _ _ _ _ - - _ - _ ..__ . ___ k _ _ _ _ _ _ _ _ __ _ _ __ __ _ _ _ _C u _ "J W . yy1 I.2 Close vent valve - - _ . - _ _..... ... __________________.... ......._________.-__ g O Close drain valve CF- 7Y9 - DVI _ g_ _ _ __ _ -_______ Open isolation valve. ______ ______ ..__ g I.3 ______________________24Gf M '_- . . IV1 _Open _-___ _isolation ___ __ ____ valve_ ____ 2 ___h2-Jht1/ - IV 2 .._ g______ .g%___ __-___ __-_ _______________ ..__________ ____..__ j I.4 Remove jumper from terminal A and C # __ . g Q
..Replace wire 4 _at
_ __ _ __ __ ____l 2M-Attf5 pane _________--____---________.________.... ___ g
^
Replace wire - at panel .34!lbMtif ___ g____._ _. - __..__ __.___.----__ _-____.._____._____. A Close link - on panel __-----__[r,/__ . . Close link - on panel -
,4rfQ O
On panel - return switch - to
# f /,/
- position. _.-_-____
Shift Supervisor notified that instrument I.5 is ready for service. --_____--__________ M N/A TEST RESULTS:
- ( d ACCEPTABLE, ( ) NON. ACCEPTABLE . 'SEIFT SUPERVISOR NOTIFIED REASON FOR NON-ACCEPTANCE /CONNENTS
- INDEPENDENT VERIFICATION REQUIRED ON SAPITY RELATED INSTRUMENTS.
. ** MARK TECSE STEPS WEICE DO NOT APPLY TO TEE SPECIFIC INSTRUMENT BEING CALIBRATED (e.g. MON. SAFETY RELATED INSTRUNSNTS) AS N/A.
e 8 . I COMPLau D BY DATE b Y ': N~$ DATE VERIFIED 4Y* ' hh 76 % Page 3 of 3 57CP-CAL-094-2 Res
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// " !W _
/
I BAVE REVIEWED TEIS DATA PACIAGE FOR COMPLETENE AND AGAINST 30AC-OPS-001-0, 10AC-MGR-003-0, ACCEPTANCE30AC-OPS-003-0.CRITERIA IN ACCORDANCE W
. UNACCEPTABLE ACCEPTABLE REVIEWED BY: .7 M
DATE REVIEWED:
/ /-3-/N' I
- T REMARES:_ _
I J l J ................................................ \
~
k
'. DAT A P ACK AGE 1 ROBERTSHAW LEVEL SWITC5 CALIBRATION '
..t
/ .
. ' C _' -
TEST EQUIP. NOS._ '
/ [. r x u '
f (
. MPL $_ _ Service' w /A -
MODEL NUMBER _
. i _
TIME IN _ ~ TIME OUT _ ) TIME LIMIT - 7 Days (WBERE APPLICABLE _ 4- ' ,L( ) OTHER REASON FOR TEST ) MWO 9___ ' ai T ) SURVEILLANCE ( .. ...- COMPLETED REMOVAL FROM SERVICE .. . 8Y 2.: DESCRIPTION - STEP .. d
-. _ ........ ..the in. 'g/,
C - F.1 Notify Shift Supervisor thatstrument is to be/removed from se
. . w. /,4-. . _. turn. . .switch
. . . .A//. #. .. _. _. . . . . .$. . ~ . . . ~ . . .
~
F.2** On panel .......... . . - - a /A T_ position. ............ . _ at panel _ A///. .. to ,
. a............... - . . .
Open link _ A /r
- .... ....i....... _ at.......
panel _..... __. ff/.:. -
.h-Open link _..........g......................._'s t / instrument -- -..
at panel Lift wire /CJ
..~................;..,........-at panel s
- _/ instrument
_ . .u
'i[ . _.-
's r, . . . .
Lift wire ........ .... .c w Place jumper across terminals A and C. .
/ ,#
~. . - . . . . . . ~ . . . . . . .NIS1_ . _ . .-.IV1 . . _- . . . -.-
Close isolation valve. . vL i F.3 . . _~ f , Close isolation valve __ td 13 I _ - IV2 // ' - - f - _ lA90FN _ VV1 ... _ Open vent valve _ F.4 .- /3 -_J Open drain valve _.... .._ ...LeuJ d DV1-.__
._L L.._....._......_.___;
. ~ . . _ . _
-.y
,............-............... _. . LEVEL INPUT y AS LEFT AS FOUND (STEP G.10)
(STEP G.5) . ----... EXPECTED -. --...-- SW 62 SYSTEM
-..---- ..--...-.. SW #1 SW #2 SW #1 SW #1 RESPONSE ......... ......... ...
SW #2 . . - - .
" gJ I
j.,
. ............. f.,
4 I p, ! 3 .... ...
.7\ b TRIP .
......... ... l
.... ........ . )/ 2. $~ l: s.
)
~<
y..wM. /< I RESET
! .............].21. Page 2 of 3 R00 57CP-CAL 094 2
DATA PACKAGE 1 (CON'T) ROBERTsaAW LEVEL SWITCE CALIBRATION PL&CING INTO SERVICE -- ......_. ' VERIFIE COMPLETED
. DESCRIPTION BY BY*
STEP , NO . I.1 Level SW. Reset, All Associated Alarms & Trips Reset ()/fE d - VV1 //
.. C . -
]
I.2 Close vent valve- .. LosdCk_ - DV1 g Close drain valve Open isolation valve NIN
~ - IV1 3
p - . ...-
%)
I.3 , Open isolation valve _ A)(3 l
- IV2 . y y -
A and C ,,, M A//A I4 Remove jumper from terminal
...... 3......_....
45 at 4/c . Replace wire Replace wire at / m th
//A on panel #/# ,,[ Nh ,
Close link .. ....s ... ... _ _ - .. 4.........
,/4 pl j I A Close link ///A on panel _ ///#
/, T return switch 4//*
to On panel A//r !
# 1h A/ik..................
position. ....._....... . . . . . . _ _ ____ i I.5 Shift Supervisor notified that instrument N/A is ready for service. TEST RESULTS_:
) ACCEPTABLE, (
( NON-ACC**"W - SRIFT SUPERVISOR NOTIFIED 0D S ONb uNf6H _ REASON FOR NON-ACCEPTANCE / COMMENTS _
- INDEPENDENT VERIFICATION REQUIRED TRUNENT ON SAFETY
** BEING MARK TBOSE STEPS WEICE DO NOT APPLT TO THE SPEC CALIBRATED (e.g. NON-SAFETY RELATED INSTRUMENTS) AS W/A.
COMPLETED By i DATE
// lY
/w DATE VERIPIED BY'
} c g % J .a d w ulos/rr U U Page 3 of 3 5 7CP-CAL-094-2 R00 1
N --. l
1 i --
,a .-
4 4 PROCEDURE DATA PACKAGE 1 DOCUMENT NO: 57CP. CAL-094 2 o SENIAL NO: R00-C NPL NO: f& ys - g .T/ 3 N. RTYPE: Gl.5 Ge-(.,.//o. qf '
- XREP: fyfgpY p_yf. ppgg TOTAL SHEETS: 3 FREQUENCY As Required l COMPLETED BY: [ mies _t DATE COMPLETED: /-#-P4 i
* \
I HAVE REVIEWED THIS DATA PACKAGE POR COMPLETENESS , l AND AGAINST ACCEPTANCE CRITERIA IN ACCORDANCE WITH 10AC-MGR-003-0, 30AC-OPS-001-0, 30AC-OPS-003-0.
, 1 ACCEPTABLE j UNACCEPTABLE l
l REVIEWED BY: / s DATE REVIEWED: /- [ REMARKS: i O .--.................... ------#....eg.g.... ,g,gg , Page 1 of 3 57CP-CAL-094-2 R00
- - _ - _ -~~-'- ----_ _
1 ) t .. .. , 4 4 4 DATA PACKAGE 1 ROBERTSHAW LEVEL SWITCH CALIBRATION w/9 _ TEST EQUIP. HOS. MPt.8 W y/- w p f vo- f. .< w
,ue:s.2
_ Service MODEL NUMBER O r/> d //r a TIME IN _ M/# TIME OUT C) TIME LIMIT . 7 Days (WHERE APPLICA8LE) 0066 _ ( ) OTHER_ REASON ) FOR TESTSURVEILLANCE ( [MWO $_ ,t -f /
- T
' COMPLETED REMOVAL FROM SERVICE _.
DESCRIPTION
..y.................................. BY STEP ' ............. ............
. .... ...................................... 7Pg5oy F.1 Notify Shift Supervisor that..._ the.........
in-strument .......... is to be On panel turn switch e
......f./'/v ..----
F.2** __ position. to _ at panel _ _. . s/,/ja Open link _ s/j/j, _ at panel _ _. . ............
............................j3y,..................
Open link _ 9 Lift wire 7 at panel gs,3 _/ instrument sC32.,,...... atpanel$"J?_/ instrument .. l Lift wire -- Place jumper across terminals A and C. .. .._....
,j fjp
.... .. .......................... .................... - IV1 .....
,g /
.l.,p .....
,* ,F.3 Close isolation valve
...... ...............................................:$d1....
Close isolation valve
- IV2 .
l
...-_. ................................................. _ Yvl sd6".... .
Open vent valve F.4 Open drain valve
- Dv1 ( ._..J_/.?..... I g......i..................................................
LEVEL INPUT AS LEFT
............. .................. AS FOUND (STEP G.10)
(STEP G.5) .---...... ... ...- EXPECTED SW $2 SW fl SW 92 SYSTEM SW $2 SW $1 ....... ... .......... SW $1 '
......... ........... g s en . ..g}...'.
RESPONSE ' *
.rsep j 3.. .' _ .
4 s g', ......_... .... g',"
......... ......... ........... g ' g
O .... TRIP RESET syf ,y /y/ .vjs,r
....................u. ................... ........................
Page 2 of 3
f -- 4 e DATA PACKAGE 1 (CON'T) ROBERTSHAW LEVEL SWITCH CALIBRATION PLACING INTO SERVICE
,...... -_..........-- .......... ....--.....--- r----------<---------
ISTEP DESCRIPTION COMPLETED VERIFIED NO BY BY* I.1 l Level SW. Reset, All Associated Alarms & l Trips Reset
, pfgj
- vvl ,a /f,7 I.2 Close vent valve
................................................../.
Close drain valve - DV1 ,0 / f,f
.................................-- ...................... d I.3 lOpenisolationvalve - IV1
....--...A.,.p y /
Open isolation valve - IV2 t / / /
.......-- ........-- ...-- ..............- ...... ........A.f, .........
I.4 Remove jumper from terminal A and C #s .,.y /,
---.....-----................--. 7 , ,..... ........2 Replace wire f- ,at panel me y gg ,gg, Replace wire - at panel gan er, _T
. . . E_ ,.g Close link on panel ,g /p on panel ,/ /
D close link On panel return switch to
..-- ... 2 ..ff ......--
.d /
position.
........4. .,4 ........
I.5 Shift Supervisor notified that instrument
...........--...............................--...g--................
is ready for service, g N/A
- TEST RESULTS:
( ) ACCEPTABLE, ( d N-ACCEPTABLE SHIFT SUPERVISOR NOTIFIED 7-t'#1 REASON FOR NON-ACCEPTANCE / COMMENTS Ars 2 h rrw fe u ,% a'eh
..% a u m rn .- 2 2:: _ r m. i n w ,. / i m ,
- INDEPENDENT VERIPICATION REQUIRED ON SAFETY RELATED INSTRUMENTS.
** HARK THOSE STEPS WHICH DO NOT APPLY TO THE SPECIJIC INSTRUMENT BEING CALIBRATED (e.g. NON-SAFETY RELATED INSTRUMENTS) AS N/A.
I COMPLETED BY DATE N //$ 2 /~ 2 -h < DATE - C VEMFIED BY' 1 \ && _ ,1 /.; Af* Page 3 of 3 5 7CP-CAL-094-2 R00 l -
~~
~-- .
~'*
. ~
p, < ; ~ ~' - .
- _ s . .p. :
gennummer 3E31 PgCEASE 1 57CF-CAL-4_94-2 p,
~.4,COMEur.' WO: _
I k ' .'t s o SERIALN0s_*Ak - ' in IEPL Nos) #22.-LS- M 40 /4 _ ErrFB: etwee-/'.//..Gf 1
/ _
i, .~' 7 ar, . q> I *- EREF: %f- CbL - A .. 3
' TOTAL SERETS:
O As Eequired ._ FEEQORNCY: C COMPLETED BY: S V0dfif !2 bM e DATE CONFLETED:~ 7
/
M _ TEllB85 l CE WITE j I EAVE REVIEWED TEIS DATA FACKAGE FOR CON l AND AGAINST ACCBFTANCE CEITERIA IN ACf , UIRACCEPTABLE __ ACCEPTABLE JJks E - B.B. E,
. - B - B B.:
%n rt -
ERMAEES__ - __________________ Page 1 of 3 l. .
$709-Chic
. . . 494-2 . .. .
- . . s.
g.,
- s. .
. f. a g .
Tas? 80017. NOS. N[A service _ [...... TIME IN _ Notp. WWIssa g . 7 Days (WNERS APPLICABLE) Tins CUT
) NWO 9
( ) OTERR COMPLETED E( . . . . . . . . _ . _....__.7.. BY ossCRIPTION _ . _....._. j[
/
sfhnOWA.L~FROM:SERVIC=R _.....the in.
.. .. visor that service.. . _ . .
... ved from be ......... ... . -
Notify shift Super remo L.. _ is to switch
- y.1 strument. ... ... . turn s
On panel ~~~js~sTETon. F.2** to
.................at panel _...._. ... . .
.Open. =..... = -...= . _. .,,_,
link . . . at . ....
.panel. . . . __,,,,,,.,._.,.,,,,..
.. ..... . .. . . . . . ..trument .
Open link ,,,,,__,,__, ........ .at panel __,___._/ ins..... trument....
. Lift....wire ......... ..
.p
_ . _ ... . ....at panel .../ ins._....... . . . Lift wire
. ... _ .. . nd C. v..,
/
.. .... . _ .... across terminals . IV1A. .... a. ...... . . . . .J g. . . . . . _ . s Place jumper.. ... ... ..... IV2 valve v alv_e.....,_,,.,,,,.,.,,,,.,, . . . . . .. . . ..
Close isolation F.3 VV1
. j Close isolation...
vent valve .. DV1 . . . . _....................... F,4 Open...... valve _. . _.................... ... . .. _ _ .. Open drain ..... ... ...... *
....... . .......... . . . . . (ST37 LEVELINPUT
. L8FTG.18)
AS
....... ........ . . . . . .FOUND .. .-
..... AS G.5) SW $2
._ ~......... ... .... ... .... .
(STEF SW il
..... ~ SW #2 p ni ;
EXPECTED~ ..~. SW #1 . .. ..
.. ... SW 92 .... ... ..
..f.3.
j SYSTEM SW fl ...... g.y$.... . ..
........ ..m..... . ... ..
G it
..RE570W85 A8fl rmIP
.................. 57CP. CAL 994 2
'~~I
. *-,, -c, .
. MTk PacEASB 1 ( W T1 d ION _
im0Gaumr"** L375L SWITCN 'm-;W
- - _ _ VMIPasii COMPLBTSD P!LM*ING =-...- INTO_ - SERVICE _
. ._ ., .Te -
== DRSCRIPTION 7
STSP 50 _ Alarms & - -
.. -Level sN. Roset, All Associated..... _
_kd g .. 21 Trips Roset ............ I
. VV1
[1~ Close vent valve _ Y' _) I.2 . DV1 -- _
...................;... ..:.. .-IV1 __ .. . (I( Q - ..
valve . a.. D Close drain .
..... valve u
..........M h I.3 ....................;... _
Open isolation ...
. IV2 .. ...... .
s Open isolation valve j
,- ..... ...Remove
......... jumper .......=...
from terminal ....A and _. C . . [~ I.4 ..... ........_ ............._ at panel ; -- _ C ee Replace wire
..............;... ............._ 4t panel _ _
/
c~ Replace wire _ _ on panel _ Close link _ on panel _
/ ,
Close link _ 4 On panel _ _ return switch _ position. _ to F W/A I shift supervisor notified that instrument...... L. .d _. J. I.5 is ready for service. L.....L.................................. TEST RESULTE: ( ) NON-ACCEPTA8 ( N ACCEPTABLE, _ SHIFT SUPERVISOR NOTIFIED TS_ _d/
~/
REASON FOR NON-ACCEPTANCE /CONNEN , ED ON SAPETY RELATED INSTR
- INDEPENPENT VERIFICATION REQUIR PPLY TO TER SPECIFIC As II/A. IN3 S UN
** BEING NARE 75035 STEPS NEICE DO WQTD&TsAMON-SAF CALIBRATBD (e.g. l T
l SY F 5:* Law " sama e Mg,Y < Y. i
? 1h
/
RS/l Page 3 of 3 5 7CP-CAL-994-2
~ _
. err. g et. 4 u a
,_.jA-Y" _
9
. p 3ATA PACKAGE 1
( DOCURENT NO: 57CP '"*'494-2
- l SERIAL NO: 30b 3
MPL WO:_ O lI/ O 2 RTYPE: GM /d b-
. ., H L XREP:
A
\
r,* TOTAL SHEETS: 3 v , O pagQUENCY: As Required - COMPLETED BY: IIIA A' '
./
DATE COMPLETED: fd ^ I RAVE REVIEWED THIS DATA PACKAGE FOR COMPLETENESS AND AGAINST ACCEPTANCE CRITERIA IN ACCORDANCE WITH 10AC-MGR-003-0, 30AC-OPS-001-0, 30AC-OPS-003-0.- ACCEPTABLE REVIEWED BY: O=
~
~
DATE REVIEWED: REMARES: 1.5 4/73 0 ,.................----------------------~~~~~~~~~~~~~~~~~~~~~~~~~~~ Page 1 of 3 57CP-CAL-094-2 R0[l
wn
- ..m 4
~
DATA Pad *m* 1_ IBRATION 20SERTSEAM LEVEL rf-V22 SWITCE CAL glY _ TsST sooIP. mos._ . RFL#JA m . m &&d# - ServicefA&" Aw 2kl $O6d"R TIME IN 4/4 DEL RQREER_ _
/IM ggIMEOUT HERE APPLICABLE)
RIME LIMIT . 7 Days (W / _ _ (tr> oTEsm_ BM REASON FOR TSST ) nWo #_
..m T- ) sonvz1LLaicE ( . .
COMPLETED
........................... ST
- ~ .
g CVAL PRON SERVICE,,......, .......... DESCRIPTION .._ N STEF ........................... the in. 9 .. .... _ .................. service. .. - F.1 Notify Shift Supervisor thatstrument is to be removed O
.................. _ turn switch _
c'. F.2** On panel _ position. to _ _ at panel - _. y" 4 Open link ._ _. .. 5 _ at panel _. . . . . . . . . . . . . . . . . . . , Open link _.............................. _/ instrument 9 _ at panel _. . . . . . . . . . . . . . . . . . . . Lift wire _..........................._ at _/ .............. instrument panel _ . . Lift wire _ Place jumper across terminals. . . . . .
...A and C.
gg 0 IV1
..... ...........Close isolation yAC.~
4- IV2valveJAm2-4/3 A-F.3 Close isolation valve. . _Sp M.htt.........~......... pg3 -- V1 ....-
.. ............ .......Open vent valve 24 h A m ?S .VZ1j8._
...... ..... l F.4
.. .....open drain valve ha.l.N9tos _ DV1...................
q u............................... ............... LEVEL IMPUT
......q AS LEFT 7........................
AS FOUND (STEP G.10)
. ............. (STSP
........-.yG.5).......
<1-....
SW $1 SW 82 RKPRCTED .. /
.....-..,.. ...... SW $1 SW #2 ........... ... ..
SW 92 . .... . .
~ ll SYSTsn SW 91 i
RESPONSE ......... ... ...
.... ....... y .. ... 17 . .
. t
//Llu."...- l} b ;
. fI.L .. .
b ff .. . , O ....TnIP E )4
. ......... . Page 2 of 3 5?ce.CAle=994
. ... 2 shi
~~_
~
(Nut'T1
. _ DATA FA'"' ACE 1I*** TION _
, !K* s r= w LseEL SWITCE CAL VERIFIRE COMPLETED D J!L*d"f5G INTO SERVICE _ SY SY* -
rs DESCRIPTION - . . . _ _
~ _ ._
C STEP NO -..........
.............. [lO [g l Associated Alarms & ..... .
y,_ Level SW. Roset, Al y
"__ .......... ...................-. . . . . . . . . .[/.[..
A I.1 . Trips Roset VV1 _..
; Close vent valve
................... JAM-4604 -
_........... g.. . ... .-11# .... I 2 . Close drain valveJpJa N M R - DV1........... IV1
....... g .
y.M.~.
.......................Open isolation valve.h g og[en d gp-....
N I.3 valve qA.;Lt.otdp .....-- IV2 . Open isolation
........................ ......A and C .
y Remove jumper from terminal ._ at panel...... .... ........... o .4 I
- c. Replace wire............; .............._ at panel _ _
Replace wire _ _ on panel _ Close link _ _ . .. .. _ on panel ; ........ G ..... close .....;....... link ....... .... _ to _ return switch ~ ; On panel ' _ position. N/A j l YIO .. I shift Supervisor notified that instrument L..... I.5 is ready for service. L .L....... l TEST RESULTS: ACCEPTA8LE, (
) NON-ACCEPTA8LE _
( FT SUPERVISOR NOTIFIED TS_ _ _ R1*RON FOR WON-ACCEPTANCE /CONREN S NT T AFFLY TO TER AS N/A. SPECI
**REING MARK CALIBRATED (e.g.
TBOSE STEPS WRICE DO NO* HO4-SAFETY RELATED INSTRUMENTS f DATE L cC#iPLETED 87 Wie$6
, fema,rI nu 9 Wast R$[I Page 3 of 3 57CP-CAL-994 2
'hm._
~~
~~ _
~ N *TP g p .. ,
=
_ . .. ......... ... a. .....
~- PROCEDURE DATA PACKAGE 1 l
DOCUMENT NO:_57CP. CAL.094 2 SERIAL NO: R00 y MPL NO: Old-N3b7b _ o Gl%46" /k /l: .W RTYPE: R pas #
~
900 $h XREF: MD - EL- 1017 3 TOTAL SHEETS:_
. As Required _
4 FREQUENCY: 0 L SUlne / G Kr,nkr lig COMPLETED BY: f 3[El _ DATE COMPLETED:_ . WITE I EAVE REVIEWED THIS DATA PACKAGE FOR AND AGAINST ACCEPTANCE CRITERIA IN AC UNACCEPTABLE _ ACCEPTABLE 8u > RRVIEWED BY:
,w ..
. y ,
DATS REVIEWED: 7/31 - 1 -
't N 4f //M ;
,,)
REMARES: '~ [f -- O . . . . . . . . . . . . . . . . . . . . . . . . . . ~...............\ ............ l l Page 1 of 3 57CP. CAL.094 2 ROO l
D 3, , , DATA PACEACE 1
. TION ROBERTSIAW LEVIL SWITCE CALIBRA M/_A _
Om n TM
. )AJM- Al.%7 8 _ TEST EQUIP. nos.__ Service MPL 9_
MODEL NUMBER 91-En TIME IN - O.*( 7 l *. l C ) s, TIME OUT - CASLE) TIME LIMIT - 7 Days (WHERE APPLI _ e ) OTERR O REASON FOR TEST /) MWO $_ Q-%- / OTL ( T ) SURVEILLANCE ( ................... COMPLETED .........
;.....q.................................
REMOVAL FROM SERVICE DESCRIPTION l BY
- , STEP ......................J...
...... ........................... i . . OLS .......-
P.1 Notify Shift Supervisor that the in.strument _ I is to be a
....... .. ......................_ turn switch _ .. ... .
On panel _ . . . F.2** _ position. to _ at panel _ _. Open link _ _. ....... .... _ at panel _ .............. open link _..................................jinstrument _ at panel _ G Lift wire _ _ at panel _ jinstrument ........... Lift wire _ Place jumper across terminals ................. A an d C. .... ... ( 1 .... .Y. Close isolation valve wrn-use. IV ......0.6_ F.3 ........................................ m- At%5 IV2 Close isolation valve m...... .................... m e
-PJ %36 VV1.................W.W..
F.4 open vent valve p W. S
................ ..................open d' rain valve ghjT1- AL%
,7 L..........................................................................
.............y..............
LEVEL INPUT
~.
7......................... .................. .......AS FOUND AS LEFT (STEP G.10) -- (STEP G.51----~~~ EXPECTED
--~~~~ q--SW 62 ----~SW ~41--9 SW-- - $ 2
- -- ---W 41---
SYSTEM SW $1-~~~--SW $2 S
...........e.........
80'H" M RESPONSE ......... ..... ... M 1 1 M ........ TRIP I Q' ll " .... ...hl.....C 6 .., R ...L.... A LJ.L3 .'...J. f
. . . . . . . . . . . . . . . . kL. . . p . . .
O RESET FJi,..u. ./. .\l
. . . . . . . . . . . . L . .: . R00 Page 2 of 3 57CP CAL.094-2 l
hw_.
-_ ~_ ~'~~%,-_ _ - - ' -
i
*-.o,....,,
f
+
DATA PACEAGE 1 (CON'Tl h0BERTSHAW LEVEL SWITCE CALIBRATIO
.... 7...........,......... VERIFIE G
COMPLETED BY* PLACING INTO DESCRIPTION j SERVICE...................................... i BY l STEP NO ;
...................... ............All Associated OLS Alarms g le j
' Level SW. Re' set, I 1
. Trips Reset .................. . ...........b........-f
. . .O. .L .i. ... . . .
Jr........ _I.2........................ Close vent valve waa NMB- VV1. o($ . ..g..... c r
.................. valve ............
4376 - DVI
@ M t .......... ..... y" Jy
;Close drain .............
...................... .' Open isolation .........
valvemn-Nt.O gg< g-. IV1 I.3 ,....................................--- --... IV2 ......4.... Open isolation valve:ha-NOM-............................... A and C
.. . Remove jumper from terminal .. .......
I.4 ..............................._ at panel ..... .. ..........
.. wire
; Replace... .... .. ;.................
at panel _ .. _ Replace wire _ _ on panel _ l Close link _ on panel Iclose link ............. _ return switch - _ to 9 On panel ~ position. OL5 N/A j shift Supervisor notified that instrument . 3
...... ...L I.5 ,is ready for service. .. ....
L.....L... ........... ..... TEST RESULTS:_ ( ,) NON-ACCEPTABLE OLS ( ) ACCEPTABLE, 4e b 4c, be _ Fe.,, ~ 4 % SHIFT SUPF.RVISOR NOTIFIED NTs_ _ REASON FOR LNON ACCEPTANCE hns been o dl<. V/ COMME W T4 dch 3.w oc l m ble RED LY ON TO THESAFETY SPECIFIC RELATED N/A.INSTRI
- INDEPENDENT VERIFICATION REQUI
**BEING MARE THOSE STEPS WHICH DO NOT[ A CALIBRATED (e.g. I DATE
{ COMPLETED BY 7/3 ft j _Od ME, DATU VERIFIED SY*
. 1
'l S-tL l
R00 Page 3 of 3 5 7CP. CAL-094 2 _. - '"M..
r
~ ~ ~ '~~~~~~~~~~-~ ~~-- ... _ _______
PROCEDURE DATA PACKAGE 1 i DOCUMENT NO:_57CP-CAL-094-2 SERIAL NO:_R00-MPL NO:j76 f/ ,93g 2
- G/4, ss-RTYPE:-C ; g XREF:.9-J'$'- 3f ff TOTAL SERETS:__ 3 FREQUENCY:_ As Required COMPLETED BY:_// $:r b i / // [ //,- _
/ /
DATE COMPLETED: M-//- TI AND liGAINST ACCEPTANCE CRITERI 10AC-MGR-003-0, 30AC-OPS-001-0, 30AC-OPS-003-0. i ACCEPTABLE UNACCEPTABLE _, REVIEWED BY //<. s .,e DATE REVIgwgn /g -// yq-REMARES:
*--~~~---~ ...
Page,1 of 3
DATA PACKAGE 1 ROBERTSRAW LEVEL SWITCE CALIBRATION
/V/8
-- TEST EQUIP. NOS. A , l. e nrL 0 2 C 47 V M J __ Service fm.s tb %,w 4ee
. MODEL MUMBER Tl ~
TIME IN _ A/p // TIME OUT __ k# _ TIME LIMIT . 7 Days (WHERE APPLICABLE)
~~ .
( ) OTRER umASOg ) FOR TESTSURVEILLMCE ( 5 fMWO $ 7-W-3 6f4 T COMPLETED REMOVAL FROM SERVICE-.......... DESCRIPTION
.... ................ SY STEP .~.......
. _ .. .... .. ..... .. the in.
.W
. 7 F.1 Notify Shift Supervisor thatstrument... is to be. .removed from service.
On panel N/4 turn switch....... ... A</ 4
~
F.2** o, A 1 pesition. .. --
~
to ...................-...
..................._ . . at
. panel h/h _. ...._. p4 --
h,A . Open link _.............. .... ............N i k _. u,A _ mt panel ... _....... pg - Open link
......s
... _...........s......... _
_ at panelp w w ma/......... instrument . , 4= Lift wire _ t' -._
....................at panel;a., . ......... mu/instrum_en1 A
Lift wire _ -... ............... ...... U. . Place jumper across terminals A and C............... Close isolation valve Ar. 4 . IV1 . . . . . . . ... w d.._. . F.3 . . . . . . .
. . . . . . . . . . . . . . . . . = . An n . IV2 Close isolation valve ....s._ ...._ _.........
. . M .. .
.......... .. M ..
_. ........~. .. ..... . N /# _ VV1 . F.4 Open vent valve ........ 4........... Open drain valve N/# _ DV1 .... ...M$ _ . I
..............................s.................... .............. .
..... ........................................ LEVEL ..........
INPUT .... ... . _ .
... .. AS LEPT
._.... ..... .............. . AS FOUND (STEP G.10)
EXPECTED (STEP G.5) . . . . - . . . - - -
-.~.... ..-~ ~.-
-....~~--..~~.. SW 61 SW 42 SYSTEM SW #1 SW 92 .. ..
SW fl ......... SW 42 ......... . .......
RESPONSE
y a f. y ,. p ad. t
...g ' ...
TRIP .a. ).
... .h .2h., .2%.. .... ... I 21i1k w ut2LiLb:.tL .l.6's.E.....
3?0/ . ... hE... Page 2 of 3 57CP. CAL-094 2 R00 nn - m
o, _ r- N DATA PACRAGE 1 (CON'T1 WITCE CALIBRATIO_N _ROBERTSEAM LEVEL S ..... .. 7,... VERIPIED PLACING INTO SERVIC_ E . ................. COMPLETED BY*
) -
...7.................. DESCRIPTION RY ..........
_ . . . . . d.Alarms . . . &. . .j. . . . . hl.T.... ............ STEP WO
................. Level SW. Reset, ..... ......
. . All
. . . Associate I.1 ...... ........ 1
} Trips Reset
....................A/#
VV1..............
..._.af at...
l close vent valve..................; I.2 valve 6........N/A : - DV1. ....... . _. hA Close drain... .............;. .... ....N /C - IV1 f & tt....f...b/ ... Open isolation valve ........ .... .. I.3
................. ...=.........
Open isolation ....... valve _ h/ ...... A _ . IV2 g-2._..
.. ................ ... ... ....... ......... A and C . . . ,
I4 fRemovejumperfromterminal#/#
... _........ ..a.......
.. _ at panel _ XW/ _
wire _ g... .
/ Replace.... ...........s....... ~...v/# _ at .a......
panel _ A,/A _ : ,
...a...........
wire f. l Replace N //7 ..... . .
....... .. /WA on panel 5....Z......
Close link w/# _ w/B _ on panel.....;... ....... 1
. Lyig Close link w/L to p
.............;..... ....N/A return switch ~~ 46 .
lOn panel ~ < position. N/# N/A ; Shitt Supervisor nottfied that...... instrument j....g.......... j .. 1.5 .
;is ready for service,.... .
- e. ..._..... .... ..
TEST RESULTS:_ ( ) NON-ACCEPTABLE Q l IN e# ( ) ACCEPTABLE, SHIFT SUPERVISOR NOTIFIED MENTS /e 6 e1 5w,4 K v4 . _
.m , < , I s ,
REASON FOR NON-ACCEPTANCE d o , <.
/COM is st w t'a kh/ nri w s. t
( / MENTS. lit cI % .
- c\s EQUIRED ON SAFETY NSTRUMENT
) AS N/A. RELATED I
-* INDEPENDENT VERIFICATION DO NOT APPLY NON-SAFETY R RELATED TO THE SPECIFIC INSTRUMENTS I
I
** MARK THOSE STEPS WBICE BEING CALIBRATED (e.g. l DATE ]
{ COMPLETED BY /i'/'/ ' S h bsk i DATE _
~ VERIFIED BY*
O %e R00 Page 3 of 3 5 7 CP. CAL.094-2
9e A *>.k ~~ 3EM m e1 .. . SOCIM3n Was'i % ""** b 2 ' ' I
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. .=:-..-
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- . .. . . : . 49. narrM. WO: 500 -
~
2... SIFL SD: -2 EJ/ - /MAA
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W . -....? :C . _ 'g TonL suns: 3 .
- - FRBQUENCT: As E m ired 5#:-
~~
COMPLutD M: fig. Tl ku . L.,4L
- p. .
- DATE COMPLETED: . 9 - ."M -f C
/
, ,y I R&YE E29IEstED TEIS D5blTACEACE FOR COMPI.M ,
AltD AGAINIT ACCDTANCE CRITERIL IN ACCORDANCE WITES ID&C-BGR 003-0, 3GAC-OFYr-CD1-0, 30&C-OPE-DD3-0. ta
.. 5,-
ACCEFnBLE _ v _ DELCCEPTAB &' - REVIEWED M: ~ (/ qv
~
DATE REVIEWED: /M II i REn&REs: v f
.- .. --_ = :
Page 1 of 3 _=_ ) 57CP-CAL-094-2 100 l
~ ..-
s .. ;. ,, 2 m. , vacuum s b smsc--,,cs ~,-- mos b .. -
.m- - . . . . .
.==== 4.sanze7 mos..'.;;;L,pr 4:,2;; xm.
_ i
. =:. < .
.. w gN w' L' '2O .w .
4~ TIM 3 ,m
-T e
- - ~ , . -
.y, ,
. Tns 1,2 WIT _- 7 3ays (MEERE APPL 3 -
~
o-r..w. - pluAlMG .. 3 dD.a #. ;;v'iii s . 5e ; I.g mume-Pe= 21 0 3 WWO 4 1 oraEr g ym ~" . 4,z -_2%. .
. E-M FROM SERVICE . -
i ,,- COMPLETED g.-w- .;
~ 323p ; . DF. SCRIPT 208 ' ,,
- F.1 '_ , ' Notify shift supervisor that the in - yfpf.
~
strument is ,to be removec 2ron service. turn switch
~
F.2** e' On panel to ~ position. k , at panel .
"@1 Open link
/
~b Open link at panel .
/
9.j -
- w. .
Lift wire at panel /instrazment j/ Lift wire _ at panelg, / instrument [ [ . . Place ')umper across terisinals A and C. _/nW Close isolation valve OI(/-NMO- 271 7g i F.3
~
.' glose inclation vs.1ve '2E(/-nMAO- 2V2 g F.4 Open vent valve 2 E f/-MM4h vv1 gg **'
Open drain valve 2ES/-/M60 Dv1 % jg-
- ---~ ~ ... .__
=. __
.. M L. INPUT i
AS LEFT AS POUND EXPECTED (STEP G.5) (STEP G.10) SYSTEM SW #2 SW $1 l SM $2 SW #1 RESPONSI SW 41 l SW 12 , N - 1W1Y
$ub.N..$ ...l b l A
=
//1 -
O ag.y ..... A . u w .i.u f l ncsc= Page 2 ot 3 57CP-CAL-094-2 100
Wa
. ,, m at 1. .d i E2* . .-mm
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. - . . ~ .
, M
~
1s h' YI"1 *M suC"3hneet. All Associated l'inema a gy F g*.2ripo meset 4 . j g .: 9 , gj p j g,) '
~
2'2 close went eelee. "1FC /-nmo - vv2 I j .; pi
-:092 close ermin' valve' O Ett-rr@ .g , , 9' 2;SE cpen 1-e3=tice weave JM/.nNo - 2W2 *
'1
'U $' 1i n4L -s.
l'r=ff1-e3= tion um19e , ME/-tmm - Tv3 * - 1 and C g Remove $naper from ter=4=1 2.4, Replace wire at;==7 y [ ~.., _ at panel [ 1,$if. - Replace wire on :~-a
/
C1one ya
.M ce panel _
[. . i l Close link
~
' on panel return switch '
W ition. _ to Shift Supervisor notified' t. hat M L# Nfa 1.5*
"" is ready for sw . ice. -
M ST RESULTS:
) MC#4CCEPTARLE __
. .i d Eti.r.unBLE, (IrTsUmvIsoR mInEn- l l
anam POR you. ACCEPTANCE /CC00ENTS -
- DID3 PENDENT VERIPICATION R300ZRED ON S
*** BEING MARE TROSE STEPS NE' ICE DO NOT APPLY T CALIRRATED (e.g. NON-SAFETT RELATED INSTRUMENTS) A
' COMPLE"'ED BY i DATI
' d[ d: t VERIF lb BP 3 3e.gg i DATE l 9.w.es h /AM l Page 3 of 3 5 7 CP-CAL-094-2 R00 ;
o l j
. . . . . . . ~.. PROCEDURE . . . . . DATA . . .PACKAGE
. . . .1 . . . . . . . . . . . l 6
i l 57CP-CA*-094 2 DOCUMENT NO: SERIAL NO:_R00 f AM I - C '/ bY MPL NO:__ RTYPE:- GMP N// 55 __ s XREF: _ SA 3 TOTAL SHEETS:_ As Required FREQUENCY:_ l M//4, ,/)//4,4// DIE t l COMPLETED BY:' f Y - / Z- #t l DATE COMPLETED: f iNESS l E WITH IAND HAVE REVIEWED AGAINST ACCEPTANCE THISCRITERIA DATA PACKAGEIN ACCORDANC6, FOR30AC-OPS.00 COMPLE! 10AC-MGR.003-0, 30AC. OPS.O l UNACCEPTABLE
- ACCEPTABL'E _ _
,-N' e A __
REVIEWED BY: DATE REVIEWED: _ d---$l-db _ l
\
/
REMARKS:_ A/ v f
~
D ............................. ! w ....................................... R00
$7CP. CAL.094 2 }
l I
_ ~ O o I DATA PACKAGE 1
. ROBERTSHAW LEVEL SWITCH CALIBRA* ION h
_ TEST EQUIP. NOS. G MPL 8 4 65/- N #M
/ '9
__ Service
,r, #
MODEL NUMBER _ TIME IU /d' _ 4 /N TIME OUT 7 Days (WHERE APPLICABLE)
*:ME
- IMI* _
_( ) QTHER_
~~ REASON FOR TEST ) MWO #_
SURVEILLANCE ( T K) ............ REMOVAL FROM SERVICE i COMPLETED BY DESCRIPTION l......]................................. STEP
.................................................w....
l *
...... the in-l Notify Shift Supervisor thatstrument is to............ be removed fro F.1 '
M( ;d 7 j C) turn switch On panel ......., F . 2*
- et position.
to l 7....;...a.....................................y..... Open link c T s _ at panel ............. l r..............g................................. Open link _ ) _ at panel _. I .................
........q l
O,", ............... _ at panel _/ instr. ment . j Lift wire
#1 at panel 4iA.....................
/ instr. ment .... .........
Lift wire k Place jumper across terminals A and C.
..........g.........
Close isolation valve gES/-M%r4 . IV1 i J.. 4.j .... .... F.3
.................................................... ......... ...s. 1 I ,
Close isolation valve #W-NM . Iv2 i
.....t. 1......
......J.....................................
Open vent valve peft MM . vv1 F.4 . Open
. . . drain
. . .valve . . .JEST-oWp
. . . . . ._ DV1 . . . . . .( . . /n
. . . . ...............c.........I '
L......'....................................... ............ .........................
;............................... .............LEVE* INPUT
........................Q AS LEFT
.................. AS FOUND
............. (STEP G.10) ;
' (STEP G.5) L ..-----.
EXPECTED - - - . . - - - - - - - v2 -------... - - .SW - -92. . - l SYS:EM SW #1 SW # 2 SW #1
'..SW ....... .........'........
lSW#1 , I
RESPONSE
............. g................ ..........l l
...n......>%..tl......u....
gy..k....I l
....TR;P 65tA...
%W.. ... ....
y . lS.vg;Agg 3., ^).' . . . . . . . . . f O .........
. . . . . . .a'tutont
. . . . Sc4M
. . i.l/%s#.A.C.M. 4 N
[M 6 A
...L . . . . . . . . . g A. . . . . . . . . . . . . . . . . .
Page 2 of 3 $7CP-CAL-094-2 R00 1 1
l
- I DATA PACKAGE 1 (CON'T)-
ROBERTSHAW LEVEL SWITCH CALIBRATION , j PLACING INTO SERVICE DESCRIPTION COMP.ETED BY VER:F:ED BY'
' STEP ...._......
NO L.._ ..................-----.------......-................. Level SW. Reset, All Associated Alarms b I.1 /Bt Trips Reset ' l.............................. ................. - VV1 - , , . . valve 2E'-*JW J .... I.2 'Close vent
, Close drain valve.45s C@4 - DV1 [ .........
, , j pf
.....,z....
...--....... ........--.......... ............-- _ - IV1 i , .........
j,. . y{..... , I.3 Open isolation valve qe5K**....................... ( j j Open isolation valve g5e-upe9_ - IV2
..... ......................................... A and C fgj.............;f. l g S ;
I.4 l Remove Jumper from terminal............. # ....._ .. .................. l _ ......__........... at paael l
' Replace wire _ /d [
Replace wire at panel / _l j on panel l .. . Close link ... ......... l
' Close link _ . on panel ........
l ... . . . . . . . ... 9,,, .,o............. n panel return switch & :o )
/
/gposition .
8 [4 Shift Supervisor notified that instrumer.- T I.5 ,
. g, N/A L.._..>..isreadyforservice............................__.............................
TEST RESULTS:
) ACCEPTABLE, ( ) NON. ACCEPTABLE
! ( f S 1FT SUPERVISOR NOTIFIED __ N REASON FOR NON.ACC4PTANCE OMMENTSr M 2eMGMO ERM N 'dJ't.TL2AMD N SE2da- Pst G T J iE S l' @t.3 **BEINGMARK THOSE CALIBRATED (e.g. STEPS NON-SAFETY RELATED WHICt! INSTRUMEN*S) AS N/A. DO NOT A i DATE i i COMPLETED BY , I
. . . t MM ss / 7.SY \
,, /. . E ine i DATE VERIFIED BY' O Nkb W 4.f 7- M Page 3 of 3 57CP-CAL.094-2 R00 I
l l \,* .s GEOP.GU. POWER COttPANY l
. HATCH NUCLEAR PLANT l PAGE 1 0F 1 l
FOfL't TITLE: r S BUILT NOTICE FOR SCR PACKAGE
- l.
Dat e 7-Id 'N' As Built Notice No. Tb ~ H (p l l Unit No. 2 Sheet / of /s 3gg rg; The work required by DCR ~U 9 Rev. D r, ehn omp eted.
~
I
,g .3 :w( "
Deviation from the DCR response package drihIhgi?hiWOE '/M- NY'I.O l~Without . fc v.c n. r a,$:: i . . . - - - - - - - - l _With Deviation from the DCR response package drawin,gsy pppy,gg St. ige i I (See attached sketch and FCR/FDR (if applicablel) .
,;. ,9 4 0Md i' !F E ii'l 6-C.-8Z- 089- l , I O DiSIRICUIION J i 1 1. Sketch No.6h4.Ied 3 Rev. A. ApplicaS e S h,. I'b26(a N ~~Rev._4 N 2. Sketch No.6hd. 2 o 3 Rev. A. Applicable Dvg. M-7 %% - Rev. 4 ,
N 3. Sketch No.60. 3 cE 3 Rev. k. Applicable Dwg. 4-2%54 ---gey.1 S.c-82.ct9 -2 Sa-2!al t h / Re.v 4 c- I D f, j 1 N 4. Sketch No.Sht. I oE 6 Rev. b. Applicable Dwg. N-2.6(o64 --- Rev . 4 5%- 25113 - - ReV. V<'/6 1 5. . Sketch No.6h%. 2 af 3 Rev. k . Applicable Dwg. H-2.StoS4 - Rev. 4 5%-25-~1 l 3 --- tZef, -K'- M '
- 6. Sketch No.5M. S of 3 Rev. A . Applicable Dwg. N-26/o64 - RevM@ gi 6-C 82-CIC)-3 S% 'lS~l14 /Er,v.4t-% g!
I 7. Sketch No.6hf. I ed 1 Rev. b Applicable Dwg. N-16b64 % Rev. 4 q.
$%- 2.67 L 4 - Er.v. M/' bT N 8. Sketch No.6hk. '2 ok'2- Rev. b . Applicable Dvg. 'tev. 4 6-C-82.-otc1-4 N3o 6- - 26 h i n/o 6 4~ R / ed. .J*/--
1 9. Sketch No.%t. I of I S c- 82 ota-I, Rev. k. Applicable Dwg.3-76(,64 - Rev. 4 sv . 4 - F 5- So stt I 10. Sketch No.6hh I ed I Rev. k . Applicable Dwg.3- 26'.o64 - Rev.A FDR 82-ol'l-3 .5%-2.5113 EEN, .At 1 D N 11. Sketch No. 6h+, 2 af 4 Rev.. ,, Applicable D.rg. N-ZDiebb -:;-Rev. 4
* ')
N 12 Sketch No. 6hh ~) cE 4 Rev. _. Applicable Dvg. N-2 N b.4. - Rev. 4
$_13. Sketch No. 6hk,4 ed 4 R ev. .
Applicable Dwg. 4-25 6 5 4 - Rey. 4
- 14. Circuit Schedule 7- M-&-
SW _ ttAA k / RM , / flN [/ ible Engineer Date Engineering Supervisor Date l
. Fe 2. A 7(s l D/a l ENG-0016 Rev.0 42EN-ENG02-0 J
i e GEORGIA POWER COMPANY l HATCH NUCLEAR PLANT l PAGE 1 0F 1 l 9M TITLE: S BUILT NOTICE FOR DCR PACKAGE Date l-I4 b As Built Notice No. Unit No. 2 S he et 2 o f' /_d_ I
.The work required by DCR B2-o/ 9 Rev. 6 has been completed.
W ithout Deviation from the DCR response package drawing' ' . I 3 l ___ W ith Deviation from the DCR response package drawings. l l (See attached sketch and FCR/FDR (if applicable)) l 1 . . FDR-BZ-o19- 3
$ 1. Sketch No.& t. 4 d 4 Rev. . Applicable Dwg. N-7 % b k 4 !
% 7.5714 Rev. T I 2. Sketch.NSF N !A Rev. . Applicable Dwg. H-2%54 Rev.
5%-Z.Sll4
- 13. Sketch No. N!A Rev. . Applicable Dwg. H ~2 64 64 Rev._4 ,
- 4. Sketch No. Rev. . Applicable Dwg. Rev.
- 5. Sketch No. ~ Rev. . Applicable..Dwg. Rev.
. ___ 6 . Sketch No. Rev. . Applicable Dwg. Rev._ ,
- 7. Sketch No. Rev. . Applicable Dwg. Rev.
- 8. Sketch No. Rev. . Appli :mble Dwg. Rev.
- 9. Sketch No. Rev. . Applicable Dwg. Rev.
-)
- 10. Sketch No. Rev. Applicable Dwg._ Rev. .__.
'j .
- 11. Sketch No. Rev. . Stpplicable Dwg._. Fev.
- 12. Sketch No. Rev. . "ipplicable Dwg. Rev.
- 13. Sketch No. Rev. _. Applicable Dwg. Rev.
- 14. Circuit Schedule l
1 d//m /M,//am 7/ /4 / E, / / I
/(dp ible Engineer Date Engineering Supervisor Date I 1
ENG 0016 Rev.0 42EN-ENC 02-0
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SERIAL NO: R0di
- HPL NO: __ ?.Wl ~ A/OlQ CD RTYPE: GM N//o.5(
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- y. XREF: BOP C C TOTAL SHEETS: 3
, c-PREQUENCY: As Required j COMPLETED BY: k yT Rrtg [h/W l. , f
,4 DATE COMPLETED: [h~ /d -[h s .
I HAVE REVIEWED THIS DATA PACKAGE FOR COMPLETENESS t AND AGAINST ACCEPTANCE CRITERIA IN ACCORDANCE WITH
,_ 10AC-MGR-003-0, 30AC-OPS-001-0, 30AC-OPS-003-0.
. , ACCEPTABLE UNACCEPTABLE
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REVIEWED BY: AfMM' f
. 'D' ATE REVIEWED: /h fff 4 -
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1 1 rif ' REMARKS:
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ROBERTSHAW SVEL' SWITCH CALIBRATION vMPL i 2 GN - No/9 CEST EQUIP. NOS. * [A - OgODEL NUMBER $ (_ ) 2.2.- 8 2 Y ServiceN.tpre CMAL BEAK b TIME OUT 3!.00 Aim TIME IN CTIME LIMIT - 7 Days (WHERE APPLICABLE) ' REASON FOR TEST y ) SURVEILLANCE ( ) MWO f ( OTHER OCP C.4L, g EMOVAL PROM SERVICE CC' STEP DESCRIPTION COMPLETED T ---__--
-___-_--------_--_------------__--------_--------- ---- B Y-------
C' F.1 Notify Shift Supervisor that the in-j strument is to be removed from service. A l C -------
-------------------------~~~--~------------
F.2** On panel y tur.n switch to position. Open link at panel Open link at panel
---------[ . . . ,
4 Lift wire at
---_.._--_-_--_--_-_-- g"? L Aro l9 (ins t r umen) '
Lift wire ~ f # - _----__-- -___ at
---------_--_---_--_---_-----_---__4- /v6 $ _
l Place jumper across terminals A and C d F.3 Close isolation valve F'2.% - IV1 Close isogi n 3, valve 9 2.34
------- ------__-- - Iv2 Q
F.4 Open vent valve VV1 /
- - - - - - _ - - - - - - - _ - - - - - - - - - - - - - - - - - - - - - _ - - - - - - _ - - _ - - - .---- Z. .,-_-
Open drain valve
--------- q
------_------_-_-_----__,._-- DV1
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-- _---------- _ . _ - - - - _ - -- _ _._ - _.._. . . LEVEL < INPUT '
4 AS FOUND. '
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AS LEFT' ' EXPECTED (STEP G YSTEM ~ ~ - - - - - - - - - - - - - - --------- . . 5. )'
'--a,,-----
. ... ... . . ( S T.E
. .P. ----
G..._10 -- ) %
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RESPONSE- SW #1' SW #2 SW #1 SW (2 SW #1 SW (2
> TRIP RESET
--$yd ----------
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. ..l:TA PACKAGE 1 (CON'T) . .
ROBERTSFAW LEVEL SWITCH CALIBRATION . s ~ PLACING INTO SERVICE . m-------------------------------------------------------:------------- STEP DESCRIPTION COMPLETED VERIFIED
.9 NO BY BY*.
=- --------------------------------------------- - - - - - - - -- - - - - - - -
T I.1 Level SW. Reset, All Associated Alarms & g Trips Reset I
---_--- _ - - - - - - - - - - - - - - - - - - _ - - - - - - - - - - - - - - - - - - _ - - - -./---------- - - - - - - - - -
l I.2 Close vent valve - VV1
-- g----
to Close drain valve - DV1 N I.3 Open isolation valve @ 7_3 8
- IV1
( Q- ----. - - - - - Open isolation valve 1: 2M - IV2 g ------
------------------------------------------+ - ---- .-- -----
I.4 Remove jumper from terminal A and C d o ** -----------_-------------------------_----- -- 8------.--- -- c-Replace wire h at --
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Replach wire C_ C Q' 8 0 N
,a t p-.m NO 19
( Close link on panel Close link on panel
---p-----
------------------------------------------- --------- N -------- .
l On panel return switch to position.
- - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - -------------- - - - - - - - ~
I.5 < Shift Supervisor notified that instrument ,,,, is ready for service. N/A l l TEST.RESULTS: ( CEPTABLE, ( ) NON-ACCEPTABLE SHIFT SUPERVISOR NOTIFIED REASON FOR N'ON'-ACCEPTANCE Ybe kca:#~[~ hmb L')ete. (hed % to
+k bAm # A Aod ckdc. /, $",s ce&JA of ASad Chde.
- INDEPENDENT VERIFICATION REQUIRED ON SAFETY RELATED kNSTRUNENTS.
00 MARK THOSE STEPS WHICH DO NOT APPLY TO THE SPECIFIC . INSTRUMENT BEING CALIBRATED (e.g. HON-SAFETY RELATED INSTRUMENTS) AS N/A. I - 2.
- - ../ m ., ., COMPLETED BY DATE ,
N bO~b W WERIFIEI1/'BY* -/7' DATE ,
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- - s' y' e F1/cc 3%z l RELEASE FROY SPEXT FUE1 POOL at PLANT HATCH December 3,1986 .
l l i F. S. CANTRELL
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1 i i l SAFETY SIGNIFICANCE I ANALYZED ACCIDENT (14' WATER StilELD REMAIN)
- I EVENT OCCURRED INSPITE OF PRECURSORS ANALYZED' ACCIDENT CAUSED BY NONSAFETY SYSTEMS (AIR SUPPLY, TRANSFER CANAL SEAL, SEAL LEAK ALARM) - POOR DESIGN
- i PROCEDUE VIOLATIONS CONTINUE TO CONTRIBUTE TO EVENTS WITH POTENTIAL SAFETY SIGNIFICANCE <
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GPC PROPERT/ ) IhTAKE PUMPING STATION NITROGEN STORAGE AREA l i YARD DRAIN 1 OlffEALL TO SWAMP SWAMP FLOW TO RIVER 1 l u,,. %
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3 FLOW PATH OF ACTIVITY RELEASED 0.4 CI RELEASED BULK OF RELEASE TO NITROGEN STORAGE TANK AREA SC E WATER DIRECTLY TO YARD DRAIN FROM N2 STORAGE AREA SOME TO RADWASTE 10% ACTIVITY TO 0lHFALL _ 1% TO SWAMP-LICENSEE BUILD DYKES AT OUlFALL AND INSTALLED Plf1PS TO COLLECT WATER FROM < YARD DRAIN INSTALLED INFLATABLE BLOCKS IN LINES LEADING TO OUTFALL, PLMPED CLEAN WATER TO COOLING TOWERS AND CONTAMINATED WATER TO TANK TRUCKS FOR PROCESSING THRU RADWASTE { ALL CONTAMINATED WATER RETAINED ON GPC PROPERTY CONTAMINATION IN SWAMP 4.0,5 MR/HR - MOSTLY IN ROOT SYSTBi 0F PLANTS ALONG . FLOW PATH, COLLECTED "RDT" VEGETATION AND PLACED GRAVEL OVER FLOW AREA STATE DID NOT WANT SWAMP DESTROYED INSTALLED AUTO SAPLERS AT EFFLUENT FROM SWAP AND AT EFFLUENT TO RIVER, SET UP PROGRAM TO COLLECT SAWLES AND ANALYZE, NO IWACT ON SWAMP ESSENilALLY NO RELEASES ;
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I i' REFUELING FLOOR PLAN VIEW BUILDING JOINT - 3" GAP l SPENT FUEL POOLS TRANSFER CANAL TRANSFER CANAL SEALING STRUCTURE i G i l i 1 1
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5 FUEL POOL ELEVATION BUILDING J0lKf SPENT FUEL STORAGE RACK i IF WATER DRAINS TO BOTTOM 0F TRANSFER CANAL, WOULD STILL HAVE li FEET WATER SHIELDING ABOVE ACTIVE FUEL ANALYZED ACCIDENT IN FSAR MINIfiJM WATER LEVEL WAS 221' GPC CALCULATED THAT WIDI BOTH MAKEUP PtNPS IN OPERATION WATER LEVEL WOULD EQUALIZE AT ABOUT 211' ( 61 FEET ABOVE BOTTOM OF TRANSFER-CANAL) ! A NUMBER OF -IRRADIATED CONTROL BLADES WITH COBALT ROLLER WERE STORED ON SHORT HANGERS. THESE WOULD START UNCOVERING AT: 219' ELEVATION RADIATION LEVELS TERE CALCULATED TO BE N 10,000 R/HR AT CONTACT. THE EQUIVALENT T0 es100 R/HR DIRECTLY ABOVE CONTROL BLADES AT REFUELING FLOOR LEVEL , AND ml R/HR REFUELING FLOOR LEVEL 6 FEET FROM die EDGE OF THE POOL j L
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6 TRANSFER CANAL SEAL ASSEMBLY U SHAPED REMOVABLE
- REPLACE SEALS APPROXIMATELY 5 YEAR INTERVALS 010 TECH, SPEC. REQUIREMENTS)
- SEALS ARE NOT CONSIDEPED SAFETY RELATED BY GPC BUT HANDLED AS"Q" MATERIAL )
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l i AIR SUPPLY COWIGURATION I I NDTE EDUNDANT SEALS l AIR SUPPLIED FRm U-2 TO ALL SEALS COULD BE MANUALLY TRANSFERRED TO U-1 BUT 112' NO PROCEDURE BASED FUEL POOL LEVEL l NOTE SEAL LEAK DETECTION INSTRlfENTATION NOT OPERABLE BECAUSE DRAIN VALVE LEFT OPEN FOLLOWING CALIBRATION. PROBABLY WOULD NOT WORK ON. CATASTROPHIC FAILURE ADDING MAKE UP WATER TO POOL APPROXIMATELY 1 PER SHIFT TO COMPENSATE FOR . EVAPORATION AND LEAKAGE IN FUEL POOL CLEAN UP/ COOLING SYSTEM l U-2 RECOVERING FROM REFUELING OUTAGE HAD PROBLEMS WITH EXCESSIVE USE OF AIR ) 1 MANAGEENT LETTER REQUIRED CLEARANCE TAG ON EACH " DROP" Alml0RIZED TO USE
~ AIR OTHERWISE VALVE BE CLOSED UNKNOWN TIN: REGULATOR FAILED AND DOWNSTREAM VALVE THROTTLE TO SUPPLY AIR T0. SEALS ON 12/02, 4-12 OPERATORS REMOVING CLEARANCE NOTED LEVER VALVE CRACKED AND CLOSED-NOT REPORTED AT TIE 1 1
SEALS DEFLATED SLOWLY NECESSARY~TO MAKEUP WATER TO FUEL POOL K)RE FREQUENT BUT NOT DOCliefiED, ON SHIFT OPERATING SUPERVISOR NOT INFORED AND ONCmlNG SHIFT NOT INFORED LEAKAGE NOTED IN TURBINE BUILDING AND REACTOR BUILDING AT PEIETRATION, FIPST SAFPLES NOT CONTAMINATED, SEARCH BEGAN TO DETERMINE SOURCE OF LEAKAGE (CORRELATION BETWEEN SFP LEAK AND LEAK IN TURBINE AND REACTOR BUILDING NOT RECOGNIZED) WHEN FUEL P0OL COOLING Plf1PS TRIPPED ON LOW LOW SKIMER SURGE TANK LEVEL, THE ON SHIFT OPERATING SUPERVISOR RECALLED PEVIOUS EVENT IN WHICH THE FUEL POOL / REACTOR CAVITY GATES WERE LEAKING, BECAE ALARED AND WENT TO REFUELING FLOOR WITH OPERATOR TO INVESTIGATE, i CHECKED GATE SEAL PRESSURE AND TRANSFER CANAL SEAL PRESSURE - NO AIR PRESSURE ON TRANSFER CANAL SEALS AND WATER LEVEL DROPPING (LATER DETERMINE TO BE ABOUT 51 FEET LOW) ; RESTORED AIR PRESSURE AND LEAKAGE STOPPED , NO RADIATION ALARM ON REFUEL FLOOR : g g g } A Q g g g ANT AIR SUPPLY TO SEALS EVEN THROUGH IT I
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mDIFIED AIR SUPPLIES U-1 SUPPLIES AIR TO ONE SEAL ON 0-1 SIDE AND OfE SEAL ON U-2 SIDE U-2 SUPPLIES ARE TO THE OTHER SEAL ON U-2 SIDE AND OTHER SEAL ON 0-1 SIDE BOTH UNITS SUPPLY AIR TO SEALS IN THE BUILDING GAP j i 4 f l 1 I i
c ,A 7 9 CONCLUSION GPC RESPONSE TO EVENT WAS EXCELLENT AFTER LEAK IDENTIFIED ! LITTLE OR NO PAD 10 ACTIVE RELEASE OFF SITE DESIGN OF SEAL ASSENLY QUESTIONABLE (GPC C0KIENDS THAT SYSTEM ET ALL l EGULATORY REDUIREENTS) SEALS DID NOT HAVE REDUNDANCY SINCE ALL WERE SUPPLIED FROM SAT AIR h0SE (GPC C0KIENDS REDUNDANT AIR WAS AVAILABLE MANUALLY BUT NOT SINGLE FAILUE PROOF) LEAK DETECTION SYSTEM WAS INADEQUATE AND MAY NOT HAVE WORKED EVEN IF i PROPERLY VALVED i LEAK DETECTION / COLLECTION SYSTEM NOT TIED IKf0 SPENT FUEL POOL LEAK DETECTION SYSTEM AS 1RIED IN FSAR (GPC CONSIDERS FUEL POOL LEVEL ALARM AS THE PRIMARY LEAK DETECTION SYSTEM) NIE ROUS PRECURSORS TO HAVE AVOIDED: INCREASED FREQUENCY OF SPENT FUEL POOL LOW LEVEL ALARMS - NOT DOCLENTED OR TURNED OVER WORK ORDER NOT WRITTEN WHEN REGULATOR FOUND FAILED, AIR VALVE WAS' THR0 TILED AIR VALVE CLOSED C0WLEIELY - NO PROCEDURE NOT PASSED ON PROCEDURE INADEQUATE FOR CALIBRATING LEAK DETECTION ALARM SYSTEM: NO PROCEDURE FOR RETURNING TO SERVICE NO PROCEDURE TO ROUTINELY CHECK AIR PRESSURE ON SEALS i
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4 , SEQUENCE OF EVENTS ,
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RELATING TO LOSS OF FUEL POOL INVENTORY (
. The following summary -describes the sequence of events relating to the loss of approximately five and one-half feet of water from the Unit I and Unit II Spent Fuel - -Storage Pools, which occurred at ,
approximately 2200 EST on December 3rd, 1986.'- At approximately 2200 on December 2nd, 1986, a plant Equipment Operator closed a service air hose-station valve .which he found cracked open while restoring clearances unrelated to this valve. The j operator was unaware that this . valve was the supply ; isolation valve to the transfer canal inflatable seal pressure regulator. The regulator had failed at some unknown previous time and its supply isolation valve had been throttled almost closed to control seal pressure. With the air valve isolated, seal air pressure would have started decreasing at a rate dependent upon seal leakage. At approximately'1130 EST, on December 3rd, 1986, the Unit 1 operators received the second low fuel pool' level alarm for their shift. As ~ refilling of the fuel pools is normally only required once per shift, an t investigation , was started. The investigation discovered a 'high level dump valve open, which was'
.a closed at that time.
'%t approximately 1400, a Plant Equipment Operator discovered water leaking from around- the Reactor Building penetration 2T43-HO12A where it entered the Turbine Building on the 112' elevation. An investigation determined that the water was entering the sealing material between the Unit II Reactor Building and the Turbine Building and leaking out through the penetration.
At approximately 1430, the fuel pool alarm occurred again. This time, a licensed, operator,also took part in the system valve lineup review in the plant. No discrepancies were noted, and the problem was turned ovwr to the next' shaft. The evening shift continced the search for the cause of the loss of fuel pool water- by closing additional isolation valves in discharge flow paths off the fuel pool cooling system. P e3: /4 - Y7 - 74 O/44 L
,, , SEDUENCE OF EVENTS RELATING TO " # ~C '
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, LDSS OF FUEL POOL INVENTORY I (Arge Two)
At .approximately 2137, a Shift Supervisor noted that both fuel low fuel pool pool cooling pumps had tripped on low, surge tank level. { <I All normal low pool i Invol alarms functioned normally. At this time, water level in the fuel pools was reported to be approximate 1y' 'one foot below the pool skimmers. When - investigating the problem, the Unit I operators left in the Control Room reviewed technical specifications and found that minimum pool level was 8.5 ft, above top of active fuel. At approximately 2200 on December 3rd, 1986, I several reports to the Control Room occurreds
- 1) A Bechtel employee reported water coming i into the 112' elevation of the Turbine Building from "the Hp office", at the '
condenser bay. This report was inconsistent as the Hp office is on the 130' elevation.
- 2) The Health physics Department reported water pouring down out of the cable trays in the Turbine Building hallway.
- 3) A plant Equipment Operator attempting to j check the Unit II Nitrogen storage tank was '
una bl e to open the door to the area due to water behind the door. ^ { By approximately 2230, fuel pool level
, decreased approximately fi ve feet'below normal level. had. {
At this time, the air pressure on the transfer canal inflatable seals was observed at O psig. The closed air isolation valve was openwd and then throttled to re-establish normal seal pressure. The depth in the fuel pool remained greater than 30 feet of water at all l times. Q gM M m/ % M h g,g dw % 7 y W ~$ &b-- Y \ Y'0 @ l While the refueling floor investigation was occurring, a second Shift Supervisor forced open the door to the Unit II nitrogen storage tank area. Inspection j of the area revealed water flowing from the 4 seal' between the. two Reactor buildings up to an I elevation six feet above the existing water level. At ( this stora'ge time, there was two to three feat of water in the tank area. Water was observed flowing out of ' this area through a storm drain. Efforts were undertaken to prevent ~ the. escape of the water that entered the Hot Machine Shop from the nitrogen storage tank I area. Relatively little water was observed ! actually leaking through the outside doors of the Hot Machine Shop. , I l
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SEDUENCE OF EVENT 3-RELATING TO*' LOSS OF FUEL POOL INVENTORY v i (pago Throo) , At "this time, efforts were undertaken to contain the water leaving the. storm drain system as there'was i no doubt that the fuel pools were the source of the ~ water entering the nitrogen storage tank area storm drain. ' ~ At '2245,.the Georgia power plant Hatch Manager of Operations was notified and immediately responded to the site. At 2255, fuel pool level had been returned to normal. By 2315, the Georgia power Vice president for plant Hatch had arrived on site. At 2330, Georgia power Manager of Health physics and Chemistry was notified and immediately responded to the site. -
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At 0128 EST, December 4th, 1986, the NRC.was informed of the situation. ADDITIONAL FOLLOWUP ITEMS: o The- fuel pool cooling and cleanup system was returned to service at 2400 EST on December 3rd, 1986, o Health physics was instructed to. begin i taking surveys and samples to confirm that the contaminated water'had not left the site boundaries and to contain and cleanup the contaminated areas in and around the, plant site, o An investigation of the existing alarm equipment related to the transfer . canal inflatable seal was performed. The alarm is controlled by level switch G41-NO19. and annunciates on panel 2H11-p654. 'There is no indication. that snas alarm occurred'during this problem and an investigation is in progress into equipment. the functional. status of this s
,, htWULNCE OF EVENTS RELATING TO ^
LDSS OF FUEL POOL INVENTORY ?, (Page Four) i . o Equipment clearance 2-86-1949 was issued on' "the service air supply valve to the transfer ( i canal inflatable seals, tagging the valve open. q, ** o A review of. Unit II Technical Specifications 4' ' determined that Unit II Technical 3,\ Speci fi cat ion required 23 feet of water v fabove the top of irradiated fuel when it is y
) stored in the fuel
, pool racks, Detailed calculations have revealed that the. minimum 3
j water level reached above the active portion [
'\
of the fuel was approximately 18.4 ft, of water, The period of time level was below
\ the technical speci fi ca t ion limit was less
) than 1-1/2 hours (period of time from fuel
,' pool cooling system tripu until level was
,7 restored to normal).
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L ^ - S- S. o' / s 'I. cF # " r ,~.- r," u u 's t, - 's 0 os 't. - ; - ~ ..... . j s = 5i4 8 - .~ . -r' . d'o o. . '45 . 42s f. r; *s.$. - ,i _ - 4 . , u. u ,,, _s,s . a ' 3 d- 4o * -~ - - $ .n ., "- r. s ' 2 . ~ ,eeem*~ ss s , r. c r r '- o r. 3 t. 0 o 9 *' - u. .- . i - n .. . i . u u - 4 ,eeee" scmu' .e @ . h.6@.c'" v - @@ - ua 8 f; - . han . m ; -;? '8 A %. R //wo-9 e~,, n, - o - J/c n Axcan ama G G . pezp . S 1 - 7G D/3'1 L f i DES OF EVENT 1 UPDATE: Water loss from the Unit-1 & Unit-2 spent fuel pools was recalulated t.o be about 141,000 gal. Instead of the 50,000 that was reported earlier . This updated number includes all water added to the pools since 12/2/86 as determined from the log reviews. The drop in fuel pool level was about +ive and one half feet which is below the unit 2 Technical speci t icati ons required level of 23 feet above the top of stored fuel (Unit-1 T.S. required level is 8.5 feet above stored fuel) The action required by U-2 T.S. was to suspend fuel movement and crane operations with loads in the spent fuel storage pool area. No vi ol at i ons have been identified resulting f rom level loss. Of the 141,000, 17,000 gallons was captured in the rad waste holding tanks, estimated 40,000 gallons may still be in the joint between the reactor buildings below the 112 foot elevation and the remainder, about 84,000 gallons
- drained to the swanp area.
During late afternoon and night of 12/4/86 the sources of non-contaminated water were diverted from draining into the swamp. Al so the flow from the j i i l \ ,e contaminated drain has essentialy stopped. Therefore addition at water to t h *= swamp is from clean ground water sespage. Overnight, efforts to verify containment of swamp water disclosed a flow p4th from the north portion of the swamp to the river. Samples taken by licensee and State personnel verified no contamination in this tiow path. The or19tno' this flow path is out side the contaminated portion of the swamp. This flow path was filled with dirt and the flow halted. No migration of contamination occurred overnight. The river level increased about 1.25 feet from 12/4 to 12/5/86. The bank height is currently about 2.5 +eet. The licensee is considering raising the 4 bank height between the river and the swamp. Also efforts to determine the I expected crest height as a result of recient rains is underway. Although no emergence condition has been declared the Technical Support Center 1 has been maned and recovery etfort is beening coordinated from there. The President of Georgia Power Company and members of his staff are on site monitoring the recovery effort. The source of the leak was from loss of air to the inflatable seals (6) on the seal between reactor buildings one and two. The gap between the buildings is about three and one half inches. As an immediated corrective action the licensee divided the single air supply to this seal such that the outboard seals are supplied from a different source than the inboard seals. This results in redundent seals. Upon descovery of the leaks, planned fuel movement was stopped and the transfer canal gates were installed. Also plant l '.m7magement placed a hold on Unit -2 startup pending discussion wtth NFC Geg;or e iI. Water removal from t'he swamp area hot spots has continued overnight -in d s r. ! 1 i continuing. This water is beening pumped to tank trucks and processed bv recirculation through demineralizers prior to being transfared to thw plant j i ) rad waste system. On truck load has been processed and another in beinn ) l processed. This water removal appears to be reducing the rad levels in t h r-i swamp from the maximum of 1.6 milirem per hour seen in one local aroa yesterday. l I 1 1 4 l l j1ll a v a 3 ) b - l e.r l y o *e g t a a n a . l t e o p o s e i t n e .av rM i r i t n n d e n h c s a l t v c e e a a fe t w t r g m e e a t e h g t a d o n i u 0 i j a h t n i a m e 3 d k e i x f 0 l d w t a t i i s ' A,,1_ t a f d o 0, e a o s c t a u e s l r t b e d t o e n s e - h l n i p n 5 a h e t v u e l _ s a u p e e e t r r n n e _ a r b a p h e r e i e i n s r F _ d l d t r d s i c s n a i n t n a d u s a i e Riu Em l o e r e o n e h e y p a e f i n t r : a h c e c n e v h t t c a m t f w i l m a t n o s a o s l a n e e i t o i d, w YOMs BT AN o e n o s e i 2 c s m o r r l r a i l h e w s c o 'i r l o a c s n e t c e r a s e p DNti I V GTn I e a h t i d f 2 a t e o o T a t t e a r e i c d e d e t o OI Ca v R REa g i t J n s r o t r e a t i U n t d o 3 f e l p e r o . t d o e k n e a d a w b y f s n a l h e k a e l z y a i o s POSr P A h t w e u f t e d r T l n g t a d l o f n t e t a n b i r l n i t d i g a s e i e o e n u e T w a a t a n . h s w . 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F Q 8 N 1 f l e t l d n e r l h w m s , 9 O e b c s s e a b a a t r e 7 1 I T t r a e n e n t e e e a m 3 P a a t o r o n t e p s e v l i 1 a g e e l e l u n e p v l a t - 4 I 6 n r d l w l o a .s a e l a S ) R 8 g i a a a c l n l a v o 9 C d r C / n s k g r g c p e k b v t 4 ' e S 3 i u n a e a c a a 'e . t b E / w a a e 0 t 0 n e i e t y h d 2 4 n m D 2 o c l 0 a 0 u h l l a l t e 3 o e 1 l o 0, w 0, t l p l t 1 c c l s t e e e e f p y i a - ( e n o a n h 0 f 0 h o h h n u h a h 5 D O f w i T 5 o 1 t t T T i s w f t 0 E ) T N A /E l D TR a C( c E i _ J . g _ BO o UN l . S o /T i YN r d . BE e a e V c r s NE i a J ' O f t e 1 9 I E f n l 9 TL O e e 0 0 AB y t r 7 7 CA t r e 0 0 I T d FR u v i ) I O D d u : L TP a in M A-OE ) f n t i E N NR H I l R I - G I R O ( Y T I R L O I T C A-R A T F S / 2 I E t N E i _ I S n - M) N U : DS E 6 NAR C 6 O D I L h 3 I L(h c - TA 2 F O t a 0 5 UNNW BOO I I S E H * ! / . R GSn V UAILI bl Alub Ntt'llHI HNP-Si MWTH //u, /,,u//6 MWE ' PRESS p,spj MODE SWITCH: R/F S/D S/U RUN gg77 p/g g/g ~ AVG o- EQP OR FL DR CST - l TEMP / F LKG GPM LKG i GPM LVL F T. I C HW // CONO OFF GAS PRE TREAT RAD K - LVL VACh 271N.HG F LOW J SCFM ((j Me FACTOR C' ; HEAT RATE 7h h f BTU /KWH CORE FLOW ] 06tb/hr CONO i[ 7 Mho I
- [ l STATUS OF THE FOLLOWING ITEMS NEEDED RIVER LVL (OAILY, u J EACH MONDAY AS OF 7:00 a.m.: ,
{gg p, FUEL EXPOSURE M "' ^ ' //' MWo/T. ACTIVITY (Copper) /Vf ppb t ACTIVE LCO'S f NUMBER EQUIPMENT
- NUMBER EQUIPMENT l
l- bh"~ N b Ri^t Ocur Sw&f6;, < . 1 / POWER CHANGES Notify Lab of any power changes of >15% in one hour when made. - ' ( FROM TO T!NiE FROM TO TIME FROM TO TIME- l* t l U N lT N A R R AT IV E R E PO R T: ,7*dacy,,*,,*,g'g*,',a' =l',Qf;,j;*,';;,y;*,ygga'=='f',7,~d'" , , , ='""" ~ l'Oii?f6//.*/r2) / G d $ $ is s Y f 7 3 ,$ ,l M & M N cf ? b f//P A'iup D Osetc J. // 7p r:- f3I .0!?n, 5.?C' ,$// ^Edij' fi,/ri,; ~ hit,w./y 7/' J he(:,'/.se h.m/ i '/ , , b~ f 4 f3'I Y' f/c /> WX ,*rth' ' 3 $c~n /$ /$t,/ h, f llQ/' jL , ,^ ,l,,:,9 (hi /7- [ k r>/,' i t k rps , / ' ' / ~ I Hatch Duty Officer /- _ [_ p - l9 7~~r - .* l' k (^/ - / </ C l PREPARED BY, M'h " 4 '76 ! OPS-0048 Rev.0 31G0-0FS-007-05^ , _ _ l I . l 1 . l . DAILY STATUS REPORT liNPGT~ /)pc2,//f6 MWTH MWE - PRES MODE SWITCH: S/D S/U RUN [ O AVG o EOP OR FL DR CST /gj p pf , /g TEMP F LKG GPM LKG G P'.t LVL F T. U/ , HW OFF GAS PRE TREAi 11AD K - . COf30 ,. LVL /[ // VACE IN.HG FLOW h SCFM [ p:i/sec FACTOR HEAT RATE BTU /KWH CORE FLOW 106 lb/br D j { Smho I . STATUS OF THE FOLLOWING ITEMS NEEDED RI,VER LVL (DAILY) ' EACH MONDAY AS OF 7:00 a.m.: e fggO p/ RX' COO LANT (lodine) I eI p/mi ' MWD /T. ACTIVITY (Copper) /VM ppb ACTIVE LCO'S l NUMBER EQUIPMENT
- NUMBER EQUIPMENT l
; POWER CHANGES / Notify Lab of any power changes of >15% in one hour when made. - , FROM TO TIME FROM TO TIME FROM TO TIME- . *l l l i i } i UNIT N A R R ATIV E R EPO RT: [*45,'",;;,'",*jyg*;a',fa',*4"y;;,g,';'gy;*,yg;;*l,,'ylg',* gaa*as **"=** k'1//'d/^/ /'&' h(/~://n > [ yh', // ,h'h .-l3, );6ij'si /} ifi,e s/-)%,p ll (bb/~rf-fR (fp .frik /o/ff, f. j7//t th,/-f!, t, j's , .. /p/g,, ;, .. J',n&, ., hi,,f ' 2// fi, ih - 6?/r (/t k if, sf.i ,p/i ks! iTi,,,, i, ;V; ),! . :/, sy ()/E, i s L /$iic.'* > r <'cl.Sbf't/ tri /}oe /',iimy) [A /, :, -g l 's f, 4.'I],.4, /,'., .Y Yf c' ~~~ . 1 / ist Il'N'.Ik N.:, )h k,, Jr /r Il /ftp,, s- t's, '/ /. r , /r- f,(, . < /// 1/b /' 4, /?m,b, ' a ffftb;I'hIOfft?l'c)i1 /N S 5 / Z, S-!v;-ts <, V .) / .5 Ac,,llr:i S/)JT S S i7.* i i />1 [$oIcibirar / c> <t/'l 1 ,$'s-hv.v.y.' f_5/{/)? f.f...,,,//,7i,, hr /0c l k// l lhr ~/m nr &' (c'/,6 oib ti /! n !'& . np, a.-M,ribiha,,. ./dr w se &p/Ti /I, d !D l $/~/rfi), r") _ /}fJ.L h ( /}<Se.s'/ ,6i, ,, /,, . v / /S,'f,t flh/se asul :f/In ~ h H l' 3%//i>r Sr' P/'uk //k 0'r/ftny,: /Y///? $/gr k., >,h 02 Pro),//k$ W 'YbJ2, h^h' -r / >, i rn []Nf/ /he-l.. cii,. :il/wy/t &, /b ,,R* , /< .Nc /N N$ i . Hatch Obty Officer , , f,. . (l.4-tcil -- PREPARED BY, / ~ 0P5-0048 Rev.'O 31GO-0'PS-007-OS ; a 'h 7 , T.17 9 j J _. Decem b er /, / 9 S'le Shc H ' s 0.5DS-Co kvta-w tJ/1s Ty ec 7newlabs&' lh eVoNnacL-rc a wr _ .ncecanig100% of HP w/K08mwe. , \ .) )
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- . _.$0 . _ , , , , , . _ _._.__.]_. . . . . . _ . _ _..d . . _ , _ _ _ DO# f hm . Eh _ .*4 ... .T_W- Z -% . Mb E _ ..Mbe _ .. _ ,%= _w hp. _ . .. A % .-.% % _SO S _ . _ ,_, 910.5 h%%- CHz.'Z- ._S M7 2y %'A b 6M Dh @ ,535\/.i'56:Qot _t ? _L k .6 ca k t.oA._. % 4 C h _ k e lW q Sih? _OM-oo) r_. mnV ks46.w4 hel .- ~@_e .. \ % {l w a %t,.o m-t_ %dAL_ = A4&L Lg 4_SA . . . - .. _. -_._ . $_9dMwas:ou-M 'k..k C A _ __.bg. 4 .M - _ _. _ _ _ D**[S 49-S W..c4 __k h h _1 .th '= b _. % 39 w - . . e.5 ajanso,_smoos-2 Akk_.ww W sea -L.q +bk. __ % % w w . . w w m m :. - - w w .2. %.u6A$ Q : % ~a. .z n M R. % ... a = 3 g . . . . _ ._ dsa! Lut1.._ng. 4 sak_.%. _. % % 4250l MW-Mh.ooa-1 _344. %ko@Mg . Coq Ahi. .DP t + ~2. . . ._ ".coc 34%u-W N oott. C.\ L .b. 7e.sb Ce q % unsd- ,1%Go-DN C'$b 2. T-U.S Nb M Coq + Tk . Ccho eM de 3 q o.4 e sm . w. _ um er% m ,e ons 5 \5c .'Pn-w. r. Coq * %A. M O. h w -t 0 C C 4-L .. M h g %uNb g b4- M moc , sw m. oot.2. h o (y,q Gq A %$ L e, Its 5 z9 h _ .D \ t3 hg . , v ,ye l \ i i ! Radioactive Leak l Tied to Faulty Seal i. l i, Power BAXLEY (AP) - A Georgia Co. spokesman ing from the pool. 'Ihe system wa.s said cleanup h efforts are essentially completed af- designed to use a pressum regulator s <; oflow-level radioactive water toatkeep was delivered closed. nu-ter the seal the leak of about 10 IIclear Plant Hatch. < . l The regulator at Hatch had ! 'Ihe spill occurred when a rubber l seal lost air pressure and collapsed, failed, however "and we were get- l
- allowing water to leak from a large ting a new one,", Beckham said. He
; pool used to store spent nuclear fuel, said he did not know how long the .' p said 'Ihomas Beckham, Georgia regulater had been defective. i , Power's vice president in charge of A new pressure regulator was in-
- Hatch operations. stalled shortly after the water loss in l the storage pool was discovered
" Cleanup efforts are essentially about 10:30 p.m. Wednesday, Beck- ' complete after the spi!!," company ham said. - spokesman David Altman said Fri. day. "We are going to continue to Workers had regulated pressure . morutor the ares behind Plant to the seal by partially closing an air . Hatch, in conjunctlan with the state pressure valve that is normally kept 'DepartmentofNaturalResources. open. A plant worker who saw the "All of the levels of contamina- valve partially opened closed it, ) ' tion were well below permissible shutting off all pressure to the seal ' limits " he said" and allowingit to collapse. The leak at the plant 11 miles guy ght mayk some- ; northwest of Baxley was blamed on 7,,had just accidentally left it ,~regator mat was "ftman ~ A 14 000 gallons of the Spent nuclear fuel is kept in a water W sW, Me aW im ' storage pool separated from the r me drainage ama wtside
- plant's nuclear reactors. 'Ihe water [ *
. used in the pool as a shield from ra- - ; dioactivity, however, is slightly ra- "It was a mistake," Altman said. , a dioactive, said Georgia Power "We found the mistake, we tdok s l' spokesman Gordon Van Mol. prompt and decisive action to deal ~ ' I , with it, and we'll make whatever ; sealAir thatpressure inflates. a rubber , changes are necessary to make sure j prevents water from leak- ** I it doesn't happen again." Fo2. A - V J ~ ~7 6 O/3o s \ s GE(RGIA POWER COMPANY l - l FIANT E.I. BATS I l PAgg i og i DOCUMMT TITLE: - IDOCUMENT IWMBER: IEETS ION NO: MANAGEMENT MEMD- MANAGER BULLETIN l MM-MGR-001-1286 'l N/A ~ * , DATE OF ISSUE: 12/4/86 TO: All Personnel , _ , , MEMO: Cleanup and Recovery Organization [ I Water from the spent fuel pools leaked through the transfer j canal last night into a building seau. Some of this water l found its way to storm drains. 1 Since the water has.very small (but detectable) amounts of l radio isotopes in it,a cleanup and recovery organization has been established and is currently working to recover the drainage. This is not an emergency but efforts to completely eradicate - any problems and recover the water are underway. For updates call Answer Phone at ext. 2319. k l l g e a W THIS MEMD WILL TERMINATE ON 12/15/86. / FPLANT MANAGER / MGR-0001 Fore - 2 7- 76 4 31 Displa/tng Directory (5 tccmr : f M8 # \,llh Ext (#) 203-A l200 Orive: B Aval% le: 36 %/ Directory: ID NAME EXT SIZE DATE TIME a 552-1 7XT 3072 09-02-86 13:07:58 b 552-101 TXT 3072 01-01-80 00:09: 12 e 552-201 TXT 88576 09-04-86 11:19:12 d 552-202 TXT 3072 09-04-86 10:56: 48 e 552-301 TXT 49152 01-01-80 00:42:34 f 552-302 TXT 3072 09-04-86 14: 10:44 g 552-401 TXT 39424 09-08-86 08:25:10 h 552- n' TXT 3072 01-01-80 00:05:08 0 1 25600 12-06-86 16: 44: Och 4 'T j TVA86-38 SUM 6144 09-12-86 15:57:08 k IR-86-36 NOV 5632 11-25-86 12: 26 : 42<f---- h ! END OF DIRECTORY , , I Press PG DN key to see more. Press HOME to return to top. Type ID letter to choose new default document namet press ENTER: fsfA J T~% 3 y as.J M 4<~.M n ? u. wafaw G ""- Upl^ /d ,. LL~ 4 no/bg ) #*M g w A ^ *.4- l 7 1 1t 3, & W-3- # ' M.d- &Q " U n-g x - 7* 3 vb. fz w/'m A %' f' N
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l DEFICIEt:CY REPORT l 1 AFFECTED U: (S): ( ) OtIE. b ) TWO. ( ) OilE AND TUO ; REP 0itT NU !BER .1.16_ . 8N t TYPE OF DEFICIENCY : h ) 0FERATIO!!AL ; ( ) ttATERIALS (SEE SECTI0ii 8.3) 2 ITEi! DESCRIPTION : . 3 ITDI LUCATION : vun 3. r u s . ,~ . a.+. . 4 MPL NUIIDER(S) ;;;m=. ..p! em. vu, r,. . . . .. . s uua n. i.. - .> a .a w , .. . . m 5 "Q" CLASS . 6 P.O./ SPEC.10. : . 7 C0t! TRACTOR / SUPPLIER : . 8 MIR NO. : , 'dv. 9/A V/A .......... ... A//A 9 PROCEDURE NO. & REV .10 ACTIVITY INSP: . 11 LD TAG AFFIXED? ( ) YES ; ( ) N0; I 1 g . . . ) !!/A ; TAG 10. : 12 DEFICIENCY : *Tae - Ameve tarea sucan cEt is en2ws Apesa To Not emn a mn an . L/AtaA. bAM 6m. Aun Aas 1/. 2 . a d aA ruu sv aas nt sit e S Aatists . *nnens cagon , T'aA w s. pass h e.aew4 TusJ Pametmatww zm. wsno m ve h s ua . 13 EVENT DATE : 11/_,.2_/ 1!. TII{E =.21s* . DISCOVERY D/(TE ': it./ 4 /,gg, TI)lg esse car, svr / 14 PERSO11 REPORTIHG. DEPT.. AND DATE . I dI f ERVISO NOTIFIED & DATE: TIME h -,e Cos**r , , . 1 1 Guats. ja2, ] $I /L //00 , . l3 I s / ft., , 16 IIDtEDIATE IOTIFICATION REQUIRED : ( d NO ( ) YES : HOUR REPORT NU!IBDt (!!ADE AS PER 40AC-RECO2-0) , q REAC'IDR PA! AMETERS : O ....-. HWt ; d PSIG ; Md 4F , ! THERilAL POUER P!!ES SURE TE!PERATU2E , 18 Il0DE SUITCll POSITIOli : ( ) UN , ( ) STARTUP AND HOT STANDSY , ( SHUTD0vT.i . . ( ) REFUEL ' 19 CORRECTIVE ACTION (s) TA!;DI: A. TECH SPECS. REQUIRED ACTIO!!(S) TAKEN? ( YES ; ( ) to ;( ) N/A $ 1. IF YES. LIST APPLICABLE TECl!. SPECS. SECIIOil(S) AND SUICtARIZE THE ACTIO TAKEu: . e= M h n e s w.t . Cno & M rs's?%3A ) A4*AldC }~ /AJ AfrA . ~ 17$, klf 4)AffGl S70/k/S#C/_) ,
- 2. IF 10 OR II/A. EXPLAlli : 4 B. LCO IllITIATED ? ( YES ; LCO ITUllBER: -N '"'" ;( ) NO C. !!UO IHITIATED ? ( YES ;EIO !!U!!BER: *
* ;( ) NO , ( ) A10 NOT t!EDUIRED a 1 ( ) NOT AT THIS TIME < 30 CO:!PLEnn BY: 4AMMM/tL ' ~l) / Y /MMOS AM/FM , FT SUPERVISOR'S SICilATURE DATE REP 0itT TIliE , AF KNOWN ** FOR !!ATERIAL DJs. BLOC:'S 15 THRU 201:AY REZIAI;! BLAllit. . ncP-0031 Rev. 0 10AC-MGR-004-0 D/37 s t Hon-appli.cai>1c., blocks uust be rurked 'll/A"** V.T Pte 1 of _ DEFICIEt:CY REPORT .f.FFECTED UllIT(S): (A ) O!!E. (j) ) TWO. (y() O!!E AllD T1JO ; REPORT NU!!BER . ' ] TYPE OF DEFICIENCY : (jr) OPERATIut!AL ; ( ) !!ATERIALS (SEE SECTI0i; 8.3) 2 ITEll DESCRIPTION : Jgy/.fg . 3 ITZli LOCATIOli : /hf.' 4 HPL IfU:lDER(S) 46f/-ff3f 2/4/- f.?3f Jg JYo/Yf AW)kl hSNrLl Atx/M,/u An-~ 5 'Q~ CLASS . 6 P.O./ SPEC.10. :
- 7 COUTRACTOR / SUPPLIER : . 8111R 10. :
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