ML20009D061
| ML20009D061 | |
| Person / Time | |
|---|---|
| Site: | Midland |
| Issue date: | 07/06/1981 |
| From: | Jackie Cook CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.) |
| To: | Harold Denton Office of Nuclear Reactor Regulation |
| References | |
| RTR-NUREG-0737, RTR-NUREG-737 IEB-80-08, IEB-80-8, NUDOCS 8107230077 | |
| Download: ML20009D061 (2) | |
Text
{{#Wiki_filter:go-34 m Consumem power James W Cook C pY Vice President - Projects, Engineering and Construction General Offices: 1945 West Parnell Ro4E Jacksoe, MI 49201 e eI7) 78&O453 ,r 7/ /, July 6, 1981 t-k S @y Harold R Denton 97 Office of Nuclear Reactor Regulation S Nuclear Regulatory Commission k' Washington, DC 20555 V / ,,v A MIDLAND PROJECT 4/ .s bCN1I-DISTRIBUTION OF GENERIC NRC LETTERS FILE: 0505.2 SERIAL: 12808
REFERENCES:
A. LETTER FROM J W COOK TO R L TEDESCO DATED 6/5/80 B. LETTER FROM J W COOK 20 H R DENTON DATED 2/3/81 C. 42TTER FROM R L TEDESCO TO J W COOK DATED 3/18/81 ENCLOSURE: LIST OF 1980 GENERIC LETTERS NOT ADDRESSED TO MIDLAND DOCKET We have reviewed the subject references and found that several of the generic letters for 1980 were not received on the Midland Docket. Attached is a list of these generic letters. As mentioned in my earlier letters to you dated June 5, 1980 and February 3, 1981, we cannot guarantee response to generic requests relating to the Midland Docket unless the request is sent to James W Cook, Vice President, Projects, Engineering and Construction, Consumers Power Company, 1945 W Parnall Road, Jackson, MI 49201. The absence of the generic letters is a continuing problem. We would like to request once again that any future generic requests that apply to the Midlano Docket be addressed as indicated above. Thank you for your continuing attention to this problem. d.- JWC/DMB/cr CC JEBrunner RJCook J / ['j DPHoffman GSKeeley / KRKline DBililler (3) oc0781-0352a100 8107230077 810706 ' PDR ADOCK 05000329 A PDR
7, c .4:- ..n- .2 -p c -. ~ ~ b i 1980 GENERIC LETTERS NOT SENT TO MIDLAND DOCKET ~ f M.4 'Date Subject- '3/10'/85 Enhanced Fission Gas Release I. 4/7/80.L 7 IEB 80-08, Examination of Containment Liner Penetration Welds s .~ 9/5/8U1 Preliminary Clarification of TMI Action .;,W-Plan Requirements y -
- 10/31/80-
-Post-THI Requirements, NUREG-0737 i. 11/26/80 Orders on Environmental-Qualification of Safety-Related Electrical-Equipment ir J (. 8 i ~ >. z, . s J:., u - a 9' ;. ~ _4 -*'P', ? .r. ,s-m - ,;/f loc 0781-0352a100
f ~ il Ja 6'80 x N CCDSuii1013 !"N'%)190':!CT %:- W ) . r-Jame, n cook - -I k $ 1 Vice l>tsident, Atulland everjecs General of feces: 1945 West Pernail had Jackson, Michigan 49201 * ($17) 788-0G40 June 5, 1980 DMB 8-80 Mr Robert L Tedesco Assistant Director for Licensing US Nuclear Regulatory Cc= mission Washington, DC 20555 I DOCKET U0S.: 50-329/330 ' ADDRESSEE CHNIGE FILE: 0505 'UFI: 70* fCRIAL: 9038 Due to 'a recent organization change aM in. order to expedite receipt of correspon- . dence on the above docket numbers vo'are requesting that future correspondence on Docket Numbers 50-329/330 be addressed to James W Cook instead of S H Howell. Will you also please change the address for r.aterial being mailed to Mr Howell and myself to read 19h5 West Parnall Road, Jackscn, MI h9201. Mr Howell's and my phone numbers remain unchanged. Thank you for your prompt attention to this matter. h& i JWC/jn -CC: TS H 'Howell, P-2d-336B l,7 'D B Miller, Midland v i D UfE: FSzi4Q LPP73
z f,232 /.cmN CODSUH10fS I. (%d -gh /i N i P01,'18T e Ja.nes W Cack L] 000kf Vice hesident - hojects, lingineering esJ Construction General (artices: 1945 Weet Pernail Road, Jackscn, fJa 4)201 + (517) 783 04% February 3, 1981 DMB 9-81 Harold R Denton Office of Nuclear Reactor ReEulation Nuclear Regulatory Commission LWashington, DC 20555 MIDLAND PROJECT DISTRIBUTION OF GENERIC NRC LETTERS ' FILE: 0505.2 UFI: 70*01 SERIAL: 11215 .We have received a letter dated 1/6/81 from Frank J Miraglia responding to our inquiry regarding the NRC policy of a single mailing per Company of generic 1etters and documents that apply to nuclear reactor facilities. After reviewing this response, we request that this policy be revised since we cannot guarantee response to generic. requests relating to the Midland docket unless the request is sent to James W Cook, Vice President, Projects, Engineering and Construction, Consumers Power Company, 1945 W Parnall Rd, Jackson, MI 49201. The reason is that separate areas of the Company are responsible for the different NRC dockets depending on whether the plant is under construction or operating. Furthermore, our internal system automatically sorts and' distributes the mail to the indicated addressee. The single mailing at best introduces unnecessary delays in reaching the Midland Project personnel and in addition introduces uncertainty in the determination of whether the specific correspondence applies only to the operating plants or s to all our dockets. We therefore request that in the future, any generic requests that apply to the Midland docket be addressed as indicated above. Thank you for your attention to this problem. J paw ( sta-- JWC/DMB/pg CC JEBrunner, P-24-513 RJCook, Resident Inspector DPHoffman, P-24-116 GSKeeley, P-14-113B KRKline, P-14-312A DBMiller, Midland I miO181-0204a100 bufE:8 L$ tJ.tY 333
v-e ' go nog . c ' 2711 [f h UNITED STATES o Y') 4. r. i NUCLEAR REGULATORY COMMISSION ,3 " .E WASHINGTON, D. C. 20555 \\;~..f 4.. MAR 1 8 1981 Docket Nos.: 50-329/330 -11r. J. W. Cook Vice President Consumers Power Company - 1945 tiest Parnall Road . Jackson, Michigan 49201
Dear Mr. Cook:
SUBJECT:
CliECKLIST OF GENERIC LETTERS A!!D BULLETIMS FOR 1980 Attached for your information is a listing of generic letters and bulletins issued 1to Poer Reactor Licensees and Applicants in 1980. The listing is in two parts: (a) those items sent to Power Reactor Licensees and applicants, and (b) those items sent to applicants only. The listing identifies the addressee generically, by PWR type and licensing status. Should you have questions reg-trding this list with. respect to Midland Plant, Units.1 and 2, contact cur licensing project manager. Si ncerely, 3 ,=.- s. Robert L. Tedesco, Assistant Director for Licensing Division of Licensing
Enclosure:
As stated cc: See next page. l l DUfE: 7.L43M$ L2-/
Mr. J. W. Cook .Vice President Consumers Power Company. 1945 West Parnall Road- ' Jackson, Michigan 49201 l-cc: Michael. I. Miller, Esq. Mr. Don van Farowe, Chief Ronald G. Zamarin, Esq. Division of Radiological Health
- Alan S. Farnell, Esq.
Department of Public "ealth ,r. -Isham, Lincoln & Beale P.O. Box 33035 Suite 4200 1 First National Plaza Lansing, Michigan 48509 Chicago,-Illinois 60603 James E. Brunner,'Esq. William J. Scanlon, Esq. Consumers. Power. Company 2034 Pauline Boulevard 212 West-Michigan Avenue Jackson, Michigan. 49201 . Ann Arbor, Michigan 48103 c . Myron'M. Cherry, Esq. U. S. Nuclear Regulatory Commission ~ 1 : IBM Plaza Resident. Inspectors Office Route 7 Chicago, Illinois' 60611-Midland, Michigan 48640 s
- Ms. Mary.Sinclair Ms. Barbara Stamiris 5711 Summerset Drive 5795 N. River Midland, Michigan 48640 Freeland, flichigan. 48623 Frank J. Kelley, Esq.
Attorney General -State of Michigan Environmental Protection Division. 1720 Law Building Lansing, Michigan 48913 Mr. Wendell Marshall Route.10-
- Midland, Michigan c8640 lir. Steve Gadler 2120 Carter Avenue t
St. Paul, Minnesota 55108
i LETTERS Atl0 SULLETI!!S TO PCWER REACTCR LICENSEES, f APPLICANTS FOR OPERATING LICENSES Att0 HCLCERS OF CCNSTRUCTION PERMITS' L L + k I:- d' t. h. ?. t (-y ri l' J 4 13 hlf. 4 ?
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-.- 2 -' RESP 0tGE DAlf 10 1 SUBJECT = PURPOSE-DATE All BUR Licensees with a . Illi. tuj.02 Inadequate Quality Requesting -Information on _ '90 Days b@ 1/21/2 CP or OL Assurance for Nuclear. Supplied feedwater spargers and EE ilitment thennal sleeves from Harvin P Engineering I I 1/29/30 All Power Reactor iicensees low Level Radioactive Waste- ' Infonning of revised require-lie fore - lg% Disposal nients on waste foruts; sulanit Ope ra t ic..- (. revised Process Control-no spect fic Program (if required) date g. >v a,;,.. 2/6/80 All llolders of Power IEll 110-03 Loss of Charcoal froni Requiring inspectiori-and 45 Days } Reactor OLs and CI's Standard Type-II, 2 Inch, Tray, evaluation of charcoal adsor-Adscrber Cells ber cells ~2/11/PA All IHR Reactor Itil 80-04 Analysis of a PUR Main Review accident analysis fo.r 90 Days facilities llolding Ols Steasii L ine lireal with Continued containinent overpressure and and to those tiedring feedwater Addition the reactivity increase front Licensing cooldoun 'i.j ' Q\\'V ' 2/23/110 All luk Licensees t uh Pripury Coolant System Pressere Requires 1) description of valve 14 Days ( Isolation Valves configuration 2) description of testing and 3) description of unit fications i t' necessary I
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E s E ? s ~* + 3-_.- RESP 0i4SE 'DAlf 10 SUR)ECTl .. PURPOSE DALE -(\\~h/2d/80: \\ .All Pcwer Reactor facilities. lEB 79-018 - Enviro'nmental' Quali fi-Transmits supplemental None with an,0L ' cation of Class 'IE Equipment information in the form, required of questions and answers mf/ D'3/6/80 All.0perating B&ll Reactor Crystal-River 3 Reactor Trip from Requires infonnation on ~ 60 Days Licensees. Approxinutely 100% full Power Hill /ICS, corrective actions and 'and expanded review of.
- 11 Days IED 79-27 h~3/10/80 All LLIRs Enhanced fission Gas Release Inforniation that the Problem lione has been resolved required I
3/10/80 All PilR Power Reactor IEB 80-0S Vacuina Condition Requires review of all systems 90 Days l'acilities holding OLs Resulting in Damage to Chemical that ccatain lou pressure or and to those with a CP Voltme Control System (CVCS) holdup tants and description of lloldup Tanks corrective action.if necessary . ~,... /10/80 All Power Reactor Emergency Planning 1:anstaltting flVI;EG.06S4 flone Licensees and Applicants Criteria for Preparation and required for a License to Operate Evaluation of Radiological a fluclear l'over Reactor Emergency Response Plar.ts and I (iSAR Dacketed) Prepastdness in Support of I fluclear Pouer Plants (for interim Use ami Coument). = 0
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b s ' S- 'DAIE .TO SUUJECT. RESPONSE-PURPOSE DAlf h- {f/7/80 .All BUR Licensees Hodifications to lloiling Water. Infonnation concerning the .None Reactor Control Rod Crive Systems NRC staf f's conclusioris on Required CRD systent nodifications to eliminate cracking in. the return line' nozzle 4/10/80 All Power Reactor Licensees - Operability of Systems Clarify ucaning of tenn 30 Days Operable as it applies to single failure criterion for safety systems -required l tech spec.submittals 4/I//80 All Power Iteactor Operating IEll 80-09 Ilydranotor Actuator fleport veri ficalions - tha L 60 Days facilities and llolders of De ficiencies ample uurgin exists for Power Reactor Construction actuation with in. proper Permits springs installed i 4/25/8u All Power Iteactor Licensees Clarification of flRC Requircuients Infonnation on facilities lione for Emergency Response facilities Required d at Each Site 4/25/80 Individual Iicensees E f f ec t o f a DC Power Supply Confirm that the GE eference 30 llays l'ailur e on ECCS Perfoniunce ' study regarding mininen LCCS equipnent availability with a DC power supply failure is appropriate for plant specitic applica tion
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._7_ RESP 0tiSE DALE .10 SUBJECT. PURPOSE-DAIE r 1/ W 5/9/80 Each PWR with an OL IEB 80-12 Decay lleat Renoval. Repor on adequacy of 30 Days System Operability decay,.2. cat 'renoval capabili ty during all modes of operation ak 5/12/80 All'BWR's with an OL' IEB 80-13 Cracking in Core ~ spray spragers and related Inspect and report on core 30-Days Spray Spargers. piping-5/19/80 All Licensees with iteactor Fire Protection Rule Enclosing proposed rule flone Operating Licenses Issued " fire Protection Program Required Prior to January 1,1979 for Nuclear Power Plants Operating Prior to Jan. 1, 1979 S/19/80 All Power Iteactor Licensees Generic Technical Activity A-12 Requesting coiunents~ on Potential 60 Days fracture Toughness for Low fracture Tonghness and Lamellar Tearing on PUR Steam Generator -and Reactor Coolant Puii;p Supports tillREG-05/7 S/22/80 All 1.icensees with Reactor fire Protection Rule Enclosuing revised pages to flone Operating iicenses issued S/19/80 letter on Iire lequired Prior ti, January 1, 1979 Protection
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^ RESPONSE-DATE' - T0_ . SUBJECT-PORHISE DATE. h6/3/80' individual Licensees Nuclear S feguards Problenis:- Participation'in a study of None -people-related problemas.In. Required nuclear. sa feguards
- p. c t-6/5/uo All BilR Licensees Generic Activity A BilR.
TransitalLLing huREG-0619
- 4) Days.
' Cracks' "[IllR Feedwater Nozzle and ~ Control Rod Drive Return Line Nozzle Cracking. requesting cousnents. A: [l06/9/80 All 0 grating Reactor Five' additional THI-2 related Transmitting errata sheets to - Hone Licenser 2s requirements May 7 letter on five Required additional 1MI-2 related requirenents. i, ' 6/11/80 All Operatinq Pressurized Decay lleat Removal Capability Requesting anendaent to IS,re 120 Days llater Reactors reactor decay heat reinoval capability \\'n 6/12/80 All UtlR's with an OL IEtt 80-14 Degradation of Scram Report on review of SDV level 45 Days Discharge Volume Capability switches and associated piping
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TO SUBJECT _' N.RfE:
- D.A.I.E
'- [(6/18/80 All Nuclear facilities 108 80-15' Possible Loss of Ilot-Report' titat'all ENS facilities 60 09yg ^ iloiding OLs ' line with' Loss of Of f-Site Power would resiain operational with- ~ ' a loss of offsite power- '6/25/80 All flower Reactor Applicants Consitinion Menoranduin and Order 1ransmitting Heporandtan and' None alid Licensees (EQ) Order dated May 27, 1980 re Required fire protection for electrical cables, and environmental qualification of electrical couponen ts 6/27/80 All Power Reactor IEB 80-16' Potential Hisapplication Report on review and corrective 30 Days facilities with an OL of Rosenount Inc., Models 1151 and actions for iniproper Rosenount or a CP 1152 Pressure Transultters with Travisnil tters Either "A" or "D" Output _ Codes / 6/30/80 All Applicants for Meetings on EQ Transmitting federal Register None 4 Con:cruction Permits, Power Notice' re Regional llectings to Requiri Heat. tor Licensees discuss environmental Architect / Engineers ants qualification of electrical Reactor Vesidors equipinesit t G 1 4
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- RESPONSE '.
.DATE 10 SUBJECT. ' PURPOSE DATE . f\\'., 7/2/80 All Pressurized Water Reactor TMI-2 Lessons Learned Enclosing K) del Techical 60 pqq Licensees SuecifIcations for UUREG-0578 THi-2 Lessons Learned Category A Items, requires . sulmui ttal '\\< 'Y/2/80 All Bolling Water Reactor IMI-2 Lessons' learned - Enclosing flodel Technical 60 Days Licensees Specifications for NUREG-0578 1MI-2 Lessons Learned Categor, A Items Requires submittal 7/3/t10 All'illlR Power Reactor . II:ll 80-17 l' allure of Control Report on review of energency 14 Days 4 facilities llolding OLs Rods to Insert During a Scram operating precedures, on one at a BWR nunual and one automatic scram test 7/7/80 All lloiling Water Reactors Scram Discharge Volume Designs Requesting amenduent to technica190 Days specifications with respect to control rod drive scram discharge voluric capability 4 1 7/11/80 lo All Applicants for Licensing Schedule !<equests Comnent 30 1:ays Operating i icenses and Construction Permit iloidars
- I' l - l _g RESI ' WISE DAff -TO SullJECT PURPOSE' DATE: [ 7/18/1!0 All-bWR Power Reactor. IEB180-17 Supplenient'l ' Report on SDV systems, 45 Day? facilities llolding OLs Fcilure of: Control Rods to install water level Insert During a Scram at a .. nonitoring system ll!JR - 5,. 3< h/22/80 All lloiling Hater Reactors Scram Discharge Volume Referencing 7/7/80 letter Hone -and stating that 15 change Require. request is a Class III license fee sulunittal gh 7/22/80 All BWR Power Reactors, IED 80-17 Supplement 2 Report on review of SOV 7 Days failures Revealed by Testing vent systen: Subsequent to failure of Control Rods to insert During A Scram at a tillR / 7/21/110 All l'ilR Power Reactor ILD 80-18 Maintenance of Report on calculations of tio Day + facilities llolding OLs Adequate flinisuum Flow Thru minimum cooling flow for and to those PilRs Centrifugal Charging Pannps centrifugal charging pumps nearling 1.icensing following Secondary Side liigh and corrective actions if Energy Line Rupture necessary / / 3 1 / 110 All fluclear Power IEB 80-19 failures of ikrcury-Report on use and surveillance 90 ikays f acilities llaving Either Wetted Matrix Relays in Reactor of mercury-wetted matrix an OL or a CP Protective Systems of Operating relays fluclear Power Plants Designed by Combustion Engineering
7 ( '.12;. Y'Te .r 4 . RESP 0ftSE D 10 10 SUBJECT PURPOSE. DATE 7/31/80 To Each Nuclear Power facility..IEB fl0-20 failures of. llestinghouse. Report on~use,L lesting' 90 Days in your Region having an OL or Type.ll-2 Spring. Return to Neutral-s and corrective' actiosis -a CP CGntrol Switches for 18-2 spring return switches / 7 / 3 1 /150 All Licensees of Operating Interim Criteria for Shift Staffing Requires the' development and flane Planits~ and Applicants.for innlementation of adinints-Requ;re. Operating Licenses and llolders trative procedures by of Construction Pennits 10/31/80 8/1/80 All Applicants for Con- " functional Criteria for fuergency for infonaation and concent. 30 Days ~ struction Penalts. Licensees Response facilities
- flVREG.0696 of Plasits Under Coastru-ction and All Operating fluclear Power Plants c.
ti n t1/ 7/110 All Operating Power Lessons learned Tech Specs Referencing Letters of flone Reactor Licensees 7/2/80 and requesting Requirt Anendment fee Classificattori C \\\\\\ 11/15/U0 All llestinghouse Pressur-Refueling llater Level Transmitting Standard 30 Days ized llater Reactor lechnical Specifications to Licensees require at least 23 feed of water over the top of the reactor pressure vessel flange
jy r o 8 ~ -.+ RESP 0t4SE. DALE' '10 SilBJECT PURPOSE DATE N/20/80 All' BWRs with Nrk' 1 Nrk I f.ontainnentL Lo.ig-Term - . Enclosing Cy of-NUREG- .None Containnen t Prograr:- 0661 "Nrk I Contalement - Required Long-Term Program Safety s Evaluation Report, Re-solution of Generic ' Technical Activity A-7" r ,\\f 8/22/E0 All BUR Power Reactor IEB 80-17 Suppleur;.. 3 Report on procedures requicing 14 DdYs facilities llolding Ots failures Revealed by Testing inanediate nianual scram on Subsequent to failure.of various conditions Contral Rods to insert During a Scram at a BWR b9/5/H0 All Lic' <sces of Prelisuinary Clarification of Requests conenents, discusses flo specific Operat s y silants and ' 1HI Action Plan Requirenents Regional Meetings date '- Applic 3ts for Approx. Operat.9 Licenses and 30 DdYS llolders of Construction Permits $/19/80 All Iitensees of Preliminary cle i.*1 cation of Addendum to 9/5 letter fione Operati.ig 1(eactor Plants l!!! Act ion Plan itequirements Required and Applicants for i Operating iicenses and flulders of Construct ion Permits
8 _ j4._ ~ . RESPONSE' DAIL . TO - SullJECT PURPOSE DA1E .E, b i 9/ 30/80 All Power Reactor. facilities. 118 79-01B Supplenent ~2 Infonnation in the form' None with n OL Environnental Qualification of of questions and answers Required Class IE Equigment /. J
- 10/1/80 All Licensees of.Operat.ing Environnental Qualification of Requests voluntary
~30 U3YS Planits and Applicants for - Safety-Rclated Equipment' assistance in ari LQ testing Operating Licenses - audit program and llulders of Construction Penni ts Tlir '10/1/80 All iluR Licensees BUR Scram Systeni Submit plans for partici-30 Days pation in long tenu program to upcrade scram systems 9 I 10/6/80 All Power Reactor linpleuentation of Guidance from Inforuation and sunuury of th)ne required Licensees and Applicants unresolved Safety Issue A-12 sta f f's prograin' " Potential for Lou fracture loughness and lanellar Tearing i on Component Supports" i 10/21/80 All Operating Pressurized Seismic Qualification of fonvards preliminary 19 ne 2 llater Reactor I icensees Auxiliary feed. vater Systenis probabilistic assessinent of hequired j seismically induced loss of decay heat renoval systems, discusses long tenu progs am i r
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SUBJECT
- PURPOSE' DATE
[1'0/24/80- ' All Power Reactor facilities. ~IEB 79-018 Suppleutrat 3 ~ Clari fication. of submii ttal None with an OL Environunental Qualffication of requireinents Required IE Equipnent 0: W 10/31/80 All Licensees of Operating Post 1MI Requirenents forwarded requirements and 30 Days - Plants and Applicants for NtlREG-0737 implenentation dates. Operating Licenses and requested conent tments llolders of Construction - Penni ts 5 %b 11/04/80 All llolders of Constr uction ODYli Code Calculation Infonnation on staf f's use ilone Penui'.s and Operating of 00Yli Code in analyse:> of itequired ' Licenses for tillRs-pressurization transients g/ 11/6/80 All Light Water I:eactor ILB 80-21 ' Valve yotes Report on inspection and 39 Days facilities llolding OLs or supplied by fialcolm foundry corrective actions concernIng Cps Company, Inc. Italcom valve yotes 7 11/13/80 All Licensees of Oper-Energency Plan Describes subniittal schedules lione ating Reactor Plants, of new rule llequired lloiders of Construction Penaits and Applicants for Construction Penuits
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s,,. ~~ ~ g. - 17'-- ItESPONSE DALE 10-Stn! JECT ... PURPOSE DME ' c. )-{'N11/25/Is0 Operating Reactors with. Inservice Inspection Programs Requests voluntary infor-None Prestressed Concrete Contain-seiation on coittalssaiseilt. Required ment Structure; tendon tests 11/26/80 To All Power Reactor Fire Proetction' forwards revised dine ' Licensees willi Plants federal Register Notice Requires' l.icensed Prior to Jasiary 1, 1979 0 11/26/80 All Licensees of Operating Orders on Environmental Provides clarification on Nune Plants and Applicants for. Qualif cation of Safety record requireu:ents itequired Operating Licenses and Related Electrical lloiders of Construction Equilment Permits 12/9/80 To All LtWR Licensees illlR Scraiti Discliarge System Iransmits staft's Generic none Safety EvaluationiItepart Itequi s e,' for Info.anation
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SUBJECT:
PURPOSE. - DATE ,1 ' 1 2 / 9 /110 - All Licensees of. Operating Einergency Planning Revision 1" Criteria for . None fo: wards 1) NUREG-0654 Reactor Plants,.lloiders of Required-Construction Penuits and Preparatiosi.and Evaluation ; ~Applicaits:for Construction' - of Radiological Einergency: Penni ts - Response Plans and Preparedness in Support- - of Nuclear Power Plants" and.2) sunanary ratisig sheets for evacuation tinne estistnies ,; \\ o ' 12/15/80 All Operating Reactor Periodic Updating ~ of fSARs fonsards new ' rule and flone Licensea guidance in the fonn of - Required questions and answers 7-12/18/110 All BilR 1.icensees 'IED 80-17 Supplenent 4 Requires testing of 45 Days failure of Control Rods to insert Continuous Manitoring During a Scram at a fillR Systeni for Scrain Discharge Volume-i it 12/19/80 All lillR Power Reactor IEli 80-25 Operating Problems Review anni testing require-90 Days f acili t ies with an 01. with Target Rock ' Sa fety Relief inents for Target Rock S/RV
- nd f einn 2, Shoreham Valves 12/22/80 All L.icensees of Operating Control of lleavy Loads Implemnt interim action 90 Days Plants and Applicants for Operating 1.icense and Review and Report 6 Months Permits Results 9 nonths.
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- RESPONSE-DATEL TO-
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Pukp0SE-DATE. AWJ \\ 1/18/80 - All BWR' Applicants Issuance of titlREG-0313,i Rev.1, for infonnation' and 60 Days " Technical Report on Material conenents. Selection and. Processing Guide-lines for BWR Coolant Pressure Boundary Piping"- / -i. 2/5/uu All Construction Pennit . lssuance of NUREG-0588, "Interiin Transmitting NilREG-0588 60 Days and Operating License Staff Position on Equipment for interim use and Applicants flualifications of %,Tety-Related consnent . (All PWR & 8tlR Electrical Equipment Applicants) } .,-T 2/21/80 All Operating License ()ualification of Safety-Related itequires review of all 45 days Applicants Electrical Equipu.ent safety related electrical I equipment quali fication documentation and description of descriptive dClion if neCessary 3/10/80 All Pending Operating Actions llequired from Operating Requires infonnation related Info. I license Applicants of 1.icense Applicants of fluclear to Auxiliary feedwater Systems be prov.oed fluelear Steam Supply Steam Supply Systems Designed by as amend-i Systems Designed by llestinghouse and Combustion Eng. ment on Westinghouse and resulting from the llRC Hnlletins opplication Coubustion Engineering and Orders Task force Review Regarding the Three liile Islarid linit 2 Accident 1
. g. .y s L - DALE ~To ' SUBJECT.
RESPONSE
PURp0SE-DAT E* / [3/10/80 LAll Power Reactor ' Licensees .lssuance of NilREG-0654/ FEMA-REP-1, " Transmitting NUREG 0654/fEHA 1/1/81
- & ' Applicants for 4 License
" Criteria for Preparation and. REP-l' for interim use in - to Operate a Nuclear Power Evaluativt of Radiological Emergency ' evaluation of emergency plans Reactor FSAR Docketed ' JResponse Plans aad Preparedness in .t.all Power Reactor Licensees) Support of-Huclear~ Power Plants / j 'J/ l l/80 ' All Applicants for Constru-Ciiange of Submittal Date for Postpones' date for submittal 45 Days cLion Pennits' arid I.icenseer Evaluation -Time - Es tima tes of evacuation time estimates of Plants under Constructnen . ending GAO review completion p k/21/80 All Construction Permits Information Request on Category I Requests response to list of None ~ and Operating Licesisee Masonry Walls Employed by Plants questions concerning Category I given Applicants. Under C? and OL Review masonry walls i 4/24/80 All Pending Operating Actions Required from Operating Requires evaluations and other Info. to License Applicants of License Applicarits of Nuclear Steaisi liiforisiatiori coricersiisig auxiliary be provided Nuclear Steam Supply Supply Systems. Designed by Babcock feedwater systems as an Systems Designed by and Wilcox Resulting frcm the NRC amendnent Babcock and Wilcox Bulletins and Orders Task force on applica-Review regarding the Three Mile Lion Island tinit.2 Accident (auxiliary feedwater systems) 11/2S/80 All Applicants for Operatiiig Cosinitission Memorandum and Order of Requests date. f r.ompletion of flone 1 i.icenses and floiders of Hay 23,1980 (referencing IE staf f review rt u ting to equip-givesi Construction Permits Bulletin 79-018-Supplement No. 2 -- ment quali ficat. xi of electrical Q.2 & 3 -' Sept. 30, 1980) equipment.
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1 %~ .3_ 8 - ~ ltESP0fjSE: DATE. TO 50BJECT. PURPOSE. - DAIC ttff2/29/80 All Power Reactor Fadilities lEB 79 01B Enviro'nmental Qualift . Transmits supplenental' flone . with an OL , cation of Class ~1E Equipment .infonnation in the form - requiredi ' of questions and answers x 3/6/80 All Operating B&ll Reactor' Crystal ~ River 3 Reactor Trip from Requires information on ' 60 Days Licensees Approxinutely 100% Full Power 'llfil/ICS. corrective actions. and 'and exparided review.of 11 Days ICB 79-27 ,/ 3/10/80 All LWRs .. Enhanced F.ission Gas Release Infornation that the Problem llond has been resolved required ? 3/10/80 All P11R Power Reactor IEB 80-05 Vacuum Condition Requires review of all systems 90 Days F4cilities holding OLs Resulting in Damage to Chemical that contain low pressure or and to those with a CP Volume Control System (CVCS) holdup tanks and description of Iloldup Tanks corrective action if necessary / 3/10/80 All Power Reactor Emergency Planning Transmitting flVREG 0654 flone Licensees and Applicants " Criteria for Preparation and rei uired l for a License to Operate Evaluation of Radiological a IldClear Power ReitClor Einergency Respohse Plants and (fSAR Docketed) Preparedness in Support of linclear Power Plants (for Interim i Use and Conment).
w g u. '%q g - . 't* e, c. 4'- RESPollSE ^ DATE TO SullJECT PURPOSE DATE 3/1i/80 All Operating fluclear Plants NRC Nuclear Data Link;(f1DL) Transmits for information - flone - ~ " Nuclear Data Link-Required' Specifications" .. 3/13/80 All Power Reactor facilities IEll 80-06 Engineered Safety Review system drawings and 90 Days with an OL feature (EST) Iteset Controls provide a schedule of testing ~ to assure that upon reset all ESF equipment remains in the emergency node 3 / 211/110 All Power Reactor Applicants Qualifications of Reactor Revised criteria fo'r reactor Various - alid Licensees Operators ' operator training and licensing: 30 Days-(1) experience, 2) training, 3) 240 Days facility certifications, 4) and increased scope of exams 5) 120 Days requali ficaLion programs t ! 4 / 4 / 11 0 All GE lillR-3 and 11HR-4 IEB 80-07 BUR Jet Pump Assembly Herpeis es visual inspections and 30 Days IdCilities with dll 01. failufe ultrasonic examinallons of jet pump structures, written report B 4/7/80 All Power Reactors with a IEll BC-Ott Examination of Requires report of non. 60 Days CP and/or OL no later than Containment Liner Penetration destructive examinations of April 7, 1980 Welds flued head design penetrations -}}