ML19347D484

Forwards List of Generic Ltrs & Bulletins Issued to Power Reactor Licensees & Applicants in 1980

ML19347D484
Person / Time
Site:	River Bend
Issue date:	03/18/1981
From:	Tedesco R Office of Nuclear Reactor Regulation
To:	Draper E GULF STATES UTILITIES CO.
References
NUDOCS 8103260110
Download: ML19347D484 (27)

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UNITED STATES

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NUCLEAR REGULATORY COMMISSION TI!$

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WASHINGTON D. C. 20555 8l*<<n's," O

'Qs I,'AR 1 8 133) s y '-

Docket Hos.:

50-458/459

• [t/,k "d 7['O Dr. E. Linn Draper, Jr.

Vice President - Technology Gulf States Utilities Company P. O. Box 2951 Beaumont, Texas 77704

SUBJECT:

CHECKLIST OF GENERIC LETTERS AND BULLETINS FOR 1980 Attached for your infonnation is a listing of generic letters and bulletins issued to Powr Reactor Licensees and Applicants in 1930.

The listing is in two parts: (a) those items sent to Power Reactor Licensees and applicants, and (b) those itens sent to applicants only.

The listing identifies the addressee generically, by PWR type and licensing status. Should you have questions regarding this list with respect to River Bend Station, Units 1 and 2, contact our licensing project manager.

Si ncerely, EEdca-cv Robert L. Tedesco, Assistant Director for Licensing Division of Licensing

Enclosure:

As stated cc: See next page.

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cc:

Troy B. Conner, Jr., Esq.

Conner, Moore & Corber 1747 Pennsylvania Avenue, N. W.

Washington, D. C.

20006 Mr. J. E. Booker, Safety & Licensing Gulf States Utilities Company P. O. Box 2951 Eeaumont, Texas 77704 Stanley Plettman, Esq.

Orgain, Bell & Tucker Beaumont Savings Building Beaumont, Texas 77701 Karin P. Sheldon, Esq.

Sheldon, Harmon & Weiss 1725 I Street, N. W.

Washington, D. C.

20006 William J. Guste, Jr., Esq.

Attorney General State.of Louisiana P. O. Box 44005 State Capitol Baton Rouge, Louisiana 70804 Richard M. Troy, Jr., Esq.

Assistant Attorney General in Charge State of Louisiana Department of Justice 234 Loyola Avenue New.0rleans, Louisiana 70112 S

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LETTERS A!i0 SULLETI:15 TO POWER REACTCR LICE:iSEES, APPLICA?iTS FOR OPERATItiG LICE?i!ES A?ID HCLCERS CF CCNSTRUCTIG:4 PE?.9IT5' 9

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RESPONSE

DATE JO SUBJECT PURPOSE DATE 1/3/80 All Power Reactor Licensees NUREG-0630 " Cladding, Swelling Extend Comnent Period 14 Dfys and Rupture - Models for LOCA Analysis" 1 / 7 / 11 0 All Power Reactor Licensees Quality Assurance Requirements Review QA Program for None (Except Arkansas Nuclear One, Regarding Diesel Generator fuel

'icsel generator fuel required Units 1 and 2)

Oil (unless exception taken) 1/10/80 All BWR Licensees BWR Control Rod failures Requesting recent experience 90 Days (except llund2oldt Bay) with control rods failing to fully insert 1/11/80 All BWR Power Reactor IEB 80-01 Operability of ADS Requires evaluation of ADS 7 Days facilities witn an OL Valve Pneumatic Supply operabili ty 1/14/80 All Power Reactor IED 79-01B Environmental Quali f t-Requesting additional infor-45 bays facilities with an OL cation of Class IE Equipment motion on Class IE electrical and equipment 90 Days e

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RESP 0tiSF DATE TO SUBJECT PURPOSE DATE j

1/21/80 All BWR Licensees with a ILB 80-02 Inadequate f)uality Requesting Information on 90 Days r

CP or OL Assurance.for fluclear Supplied feedwater spargers and Ci ulittnent thermal sleeves from Harvin l

Engineering i

i 1/29/80 All Power Reactor Licensees low Level Radioactive Waste Inforning of revised require-De fore

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Disposal ments on waste forms; submit Operation-revised Process Control no spectfic s

g Program (if required) date I

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2/6/80 All lloiders of Power IEB 80-03 Loss of Charcoal from Requiring inspection and 45 Days

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Reactor OLs and cps Standard Type II, 2 Inch, Tray evaluation of charcoal adsor-Adsorher Cells ber cells 2/8/80 All PUR Reactor IEB 80-04 Analysis of a PWR Main Review accident analysis for 90 Days facilities llolding OLs Steam Line Break with Continued containment overpressure and and to those nearing feedwater Addition the reactivity increase from Licensing cooldown

' 7.i k 2/23/80 All LUR Licensees LWR Primary Coolant System Pressure Requires 1) description of valve 14 Days Isolation Valves configuration 2) description of testing and 3) description of modi fications i f necessary I

RESP 0tlSE DATE 10 SUBJECT PURPOSE DATE l

2/29/80 All Power Reactor f acilities IEB 79-01B Enviro'nmental Quali fi-Transmits supplemental flone with an,0L cation of Class IE Equipment information in the fann required of questions and answers 3/6/80 All Operating D&W Reactor Crystal River 3 Reactor Trip from Requires information on 60 Days Licensees Approxinutely 100% full Power tital/ICS, corrective actions and

'and expalided review of 11 Days IEB 79-27 i

p 3/10/80 All Lillh, Enhanced Fission Gas Release Information that the Problem flone has heell resolyed required I

3/10/80 All PUR Power Reactor IEB 80-0S Vacuum Condition Requires review of all systems 90 Days facilities holding OLs Resulting in Damage to Chemical that contain low pressure or and to those with a CP Volume Control System (CVCS) holdup tants and descriptioi} of Holdup Ta ks corrective action if necessary m.,

I3/10/80 All Power Reactor Emergency Planning Iransmitting flul!EG.0654 hone Licensees and Applicants

" Criteria for Preparation and required for a License to Operate Evaluation of Radiological l

a thsclear Power Reactor Emergency itesponse Plants and I

(ISAR Docketed)

Preparedness in Support of i

fluclear Power Plants (for Interim use and Coinnent).

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s RESP 0tiSE DATE TO SUBJECT PURPOSE DATE

//7/80 All BWR Licensees Hodifications to Boiling Water

. Information concerning the None Reactor Control Rod Drive Systems NRC staff's conclusions on Required

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CRD system niodifications to eliminate cracking in the return line nozzle 4/10/80 All Power Reactor Licensees Operability of Systems Clarify meaning of term 30 Days Operable as it applies to single failure criterion for safety systems required tech. spec.submittals 4/17/80 All Power Reactor Operating IEB 80-09 Ilydramotor Actuator Report verifications that 60 Days facilities and lloiders of Deficiencies ample margin exists for Power Reactor Construction actuation with improper Permits springs installed 4/25/80 All Power Reactor Licensees Clarification of flRC Require nents Information on facilities flone for Emergency Response facilities Requi red at Each Site 4/25/80 Individual Licensees Ef fect of a DC Power Supply Confirm that the GE reference 30 Days failure on ECCS Performance

' study regarding mininua (CCS l

equipment availability with a l

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appropriate for plant specitic l

application

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e RESP 0tiSE DATE TO SUBJECT PultPOS't DATE S/9/80 Each PWR with an OL IEB 80-12 Decay lleat Removal Report on adequacy of 30 Days System Operability decay heat removal capability during all suodes of operation 5/12/80 All BWR's will an OL IEB 80-13 Cracking in Core Inspect and report on core 30 Days Spray Spargers spray sprogers and related piping 5/19/80 All Licensees with Reactor fire Protection Rule fuclosing proposed rule ilone Operating Licenses issued

" fire Protection Prograili Required Prior to January 1,1979 for fluclear Power Plants Operating Prior to Jan. 1, 1979 S/19/80 All Power Reactor Licensees Generic Technical Activity A-12 Requesting cnninents on Poteritial 60 Days fracture Toughness for Low I racture Toughness and Lamellar Icaring ori PWR Steam Generator and Iteactor Coolant Pump Supports fluREG-05/7 S/22/80 All Licensees with Reactor fire Protection Rule Enclosulng revised pages to fione Operatieng Licenses issued b/19/80 letter on fire Required Prior to January 1,1979 Protection

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10 SijllJECT PilltP05f 6/3/80 individual Licensees Nuclear Safeguards Profilems Participation in a study of None people-related prolalems in Required nuclear safeguards 6 / S / 11 0 All llWk Licensees Generic Activity A lluit Iransmitting HilltfG-0619 30 Days

' Cracks "llllR l'eedwater Nozzle und Control Itod Drive iteturn Iine Nozzle Cracking, requesting coima:n t s,

6/9/00 All Operating fleactor five additional IMI-2 related transmitting errata slicets to None Licensees requirements May 7 let ter on five Itequired additional lHi-2 related reqnt renamt s 6/11/110 All Operating Pressurlied Decay lleat Itemoval Capalillity itequest ing an=>ndment to IS,re 120 Days Water iteractors s'eactor sletay lical reiiioval capalellity 6/12/110 All DUH's willi an 01, litt 110-14 Degradat ton of Scram iteport on review of SOV level 46 Days Distliar9e Volume Capatillity sultthes and associated piping 4

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DATE TO SUBJECT PURPOSE DATE 7/2/B0 All Pressurized Water Reactor.THI-2 Lessons Learned Enclosing Model Techical 60 D(yg Licensees Specifications for NUREG-0578 THi-2 Lessons learned Category A Itenis, requires subnit ttal 7/2/80 All Boiling Water Reactor THI-2 Lessons Learned Enclosing flodel Technical 60 Days Licensees Speci fications for NUREG-0578 THI-2 Lessons Learned Category A Iteins, Requires sut;mittal 7/3/80 All 8tlR Power Reactor IEB 80-17 failure of Control Report on review of energency 14 Days Facilities llolding Ols Rods to Insert Durint) A Scrain operating procedures, on one at a BWR manual and one automatic scram test 7/7/80 All Bolling Water Reactors Scram Discharge Voluine Designs Requesting ainendaient to technica190 Days specifications with respect to control rod drive scram discharge volune capability 7/11/80 To All Applica:its for Licensing Schedule Requests Comnent 30 Days Operatisig Licesises avid Construction Permit iloiders l

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RESP 0llSE DATE TO SUBJECT PURP05C DATE 7/31/80 To Each Nuclear Power facility IEB 80-20 failures of Westinghouse Report on use, testing 90 Days in your Region having an OL or Type W-2 Spring Return to Neutral and corrective actions a CP Control Switches for 11-2 spring return switches 7/31/80 All Licensees of Operating Interim Criteria for Shift Staffing Requires the development and Hone Plants and Applicants for implementation of adminis-Required Operating Licenses and lloiders trative procedures by of Construction Pennits 10/31/80 8/1/80 All Applicants for Con-

" Functional Criteria for Emergency for infonnation and connent 30 Days struction Permits. Licensees Response facilities" NUREG.0696 of Plants Under Constru-ction and All Operating Nuclear Power Plants U/ 7/80 All Operating Power Lessons Learned Tech Specs Referencing Letters of Hone Reactor Licensees 7/2/80 and requesting Required Amend.nent fee Classification 8/15/80 All Westinghouse Pressur-Refueling Water Level Transmitting Standard 30 Days ized Water Reactor Technical Specifications to Licensees require at least 23 feed of water over the top of the reactor pressure vessel flange

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DATE 10 SUBJECT PURPOSE DATE 10/24/110 All Power Reactor facilities IEB 79-010 Supplement 3 Clarification of submittal None with an OL Environmental Quall'fication of requirenents Required IE Equipnent 10/31/80 All Licensees of Operating Post IMI Ret,uirements forwartled requirements and 30 I)ays Plorits arid Applicants for HilREG-0737 linplenientation dates, Operatisig Licesises and req 6ested consultments lloiders of Construction Permits 11/04/110 All lloiders of Construction ODYil Code Calculation Information on staf f's use flone Permits and Operatirig of ODYli Code in analyses of Required Licenses for 11WRs pressurization transients II/fi/110 All Light Water Reactor IEB 80-21 Valve yotes Report on inspection and 30 Days facilities llolding OLs or supplied by Malcolm foundry corrective actions concerni'ng cps Company, Inc.

Italcom valve yotes 11/13/110 All Licensees of Oper-Energency Plari Describes submittal schedules florie dting Reactor Plants, or new rule Required linlders of-Construct ion Permits orid Applicants for Construction Pe mits

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DAll 10 Sut!JfCT PURPOSE DAIL 11/2S/80 Operating Reactors with Inservice Inspection Pro.jrains Requests voluntary infor-None Prestressed Concrete Contain-unition ori cositaliiiiient Required ment Structures tendon tests 11/2S/80 To All Power Reactor fire Proetction forwards revised None Licensees with Plants federal Register Notice Required Licensed Prior to Ja:Ory I,1979 11/26/110 All Licensees of Operating Orders on Environnental Provides clarification on None Plants and Applicants for Qualification of Safety record requirenients Required Operating Licenses and Related Electrical lloiders of Construction Equipment Penni ts 12/9/80 10 All UWR l.icensees iltilt Scram Discharge systeni Iransmi ts s taf t 's Generic rione

$afety Evaluatinsi Report Required

!cr liitoimal ion

RESPONSE

DATE TO SUBJECT PURPOSE DATE 12/9/80 All Licensees of Operating Energency Planning forwards 1) NUREG-0654 None Reactor Plants, lloiders of Revision I" Criteria for Required Construction Permits and Preparation and Evaluation Applicants for Construction of Radiological Energency Perinits Response Plans and Preparedness in Support of Nuclear Power Plants" and 2) sunsnary rating sheets for evacuation Line estimates 12/15/80 All Operating Reactor Periodic Updating of FSARs forwards new rule and None Licensees guidance in the form of Required questions and answers 12/18/80 All BWR Licensees IED 80-17 Supplenent 4 Requires testing of 45 Days failure of Control Rods to insert Continuous Monitoring During a Scram at a BWR System for Scram Discharge Volune 12/19/80 All BilR Power Reactor IEB 80-25 Operating Problems Review and testing require-90 Days facilities with an OL with Target Rock Safety Relief inents for Target Rock S/RV and fermi 2, Shoreham Valves 12/22/80 All Licensees of Operating Control of lleavy Loads implement interim action 90 pays Plants and Applicants for Operating Licenses and Review and Report 6 Months Pennits Results 9 Manths

LETTERS TO OPERATING LICENSE AND CONSTRUCTICN PERMIT APPLICANTS' k

=

s RESPONSE' DATE TO SUBJECT PURPOSE DATE.

1/10/80 All llWR Applica:its Issuance of NUREG-0313, Rev.1, for infonnation and 60 Days

" Technical Report on Material consnents Selection and Processing Guide-lines for BWR Coolant Pressure Boundary Piping" 2/S/80 All Construction Pennit issuance of NUREG-05H8, " Interim Transmittisig NUREG-0588 60 Days and Operating Licen +

Staff Position on E'rdpment for interim use and Applicants Qualifications of Safety-Related consnent (All PWR & Btm Electrical Equipment Applicanis) l 2/21/80 All Operating License Qualification of Safety-Related Requires review of all 45 days Applicants Electrical Eqeipment safety related electrical equipment qualification docunientation and description of descriptive action if necessary 3/10/80 All Pending Operating Actions Required from Operating Requires infonnation related info. to License Applicants of License Applica:its of Nuclear to Auxiliary f eedviater Systems lie provided Nuclear Steam Supply Steam Supply Systems Designed by as amend-Systems Designed by Westinghouse and Combustion Eng.

ment on Westinghouse arid resultirig from the NRC Bulletins application ConJaustion Engineering and Orders Task Eorce Review Regarding the Three Mile Island Unit 2 Accident

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ltESPONSE DATE TO SUBJECT PURPOSE DAIE-3/10/80 All Power Reactor Licensees issuance of NUREG-OfaS4/ FEMA-REP-1, Transmitting NUREG-06S4/fEHA I/1/81

& Applicants for a License

" Criteria for Preparation and REP-1 for interim use in to Operate a Nuclear Power Evaluation of Radiological Eniergericy evaluationi of eniergency plans Reactor FSAR Dockettui Response Plans arid Preparedness in Call Power Reactor Licensees)

Support of Nuclear gower Plants 3/11/U0 All Applicants for Constru-Charige of Sutanittal Date for Pastpones date for sulanittal 45 Days ction Penuits and Licensees Evaluation Time Estimates of evacuationi time estimates of Plants (Jnder Construction pending GA0 review completion l

4/21/80 All Construction Permits Infonnation Request on Category I Requests response to list of None and Operating Licensee Masonry Wa'lls Employed by Plants questions concerning Category I given Applicants Under CP and OL !teview masonry walls 4/24/80 All Pending Operating Actions Required from Operatituj Requires evaluations arid other Info, to License Applicants of License Applicarits of Nuclear Steam infonnation concerning auxiliary lee provided Nuclear Steam Supply Supply Systems Designed by liabcock feedwater systems as an Systems Designed by and Wilcox Resulting from the NRC amend.nent liabcock and Wilcox Ilulletins and Orders lask force on applica-Review renarding the ihree Mile tion Islarid thilt 2 Accident (aux 11lary feedwater systems) 11/25/80 All Applicants for Operating Conmissinn Memorandum and Order of Requests date for completion of None Licenses arid lloiders of May 23,19fl0 (referencing IE staff review rel.* ting to equip-given Construction Permits llulletin 79-Olli-Supplement No. 2 -

ment qualification of electrical Q.2 & 3 - Sept. 30, 1980) equipment l

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RESP 0rj5E DATE 10 juBJECT PURPOSE DATE 2/29/80 All Power Reactor Fadi11 ties

.IEB 79-01B Enviro'nnental Qualif t-Transmits supplemental flone with an OL cation of Class 'IE Equipment information in the form reoutred of questions and answers 3/6/80 All Operating B&W Reactor Crystal River 3 Reactor Trip from Requires information on 60 Days Licensees Approximately 100% Full Power

'lifil/ICS, corrective actions and

'and expanded review of 11 Days IEB 79-27 3/10/80 All LWRs

i. Enhanced Fission Gas Release Information that the Problem tions has been resolved required

'll PWR Power Reactor IEB 80-05 Vacuum Condition Requires review of all systems 90 Days 3/16/80 A

Facilities holdirig OLs Resulting in Damage to Chemical that contain low pressure or and to those with a CP Volune Control System (CVCS) holdup tanks and description of Ilo] dup Tanks corrective action if necessary 3/10/80 All Power Reactor Energency Planning Transmitting flVREG.0654 tione Licensees and Applicants

" Criteria for Preparation and rei uired l

for a License to Operate Evaluation of Radiological a Nucicar Power Rea.clor Emergency Response Plants and (fSAR Docketed)

Preparedness in Support of thiclear Power Plants (For Interim Use and Consnent).

t RESP 0ilSE DALE TO SUBJECT PURPOSE DATE 3/12/80 All Operating Nuclear Plants NRC Nuclear Data Link (NDL)

Transmits for information ilone

" Nuclear Data Link Required Specifications" 3/13/U0 All Power Reactor Facilities IEB 80-06 Engineered Safety Review systes drawings and 90 Days willi an OL Feature (ESF) Reset Controls provide a schedule of testing to assure liiat upon reset all ESF equipment remains in the energency mode 3/28/80 al Power Reactor Applicants Qualifications of Reactor Revised criteria for reactor Various -

and Licensees Operators operator traisiing and licensing:

30 Days (1) experience, 2) training, 3) 240 Days facility certifications, 4) and increased scope of exams 5) 120 Days requali fication prograniis 4/4/80 All GE UWR-3 and BUR-4 IEB 80-07 BWR Jet Pump Assenhly Requires visual inspections arid 30 Days facilities witti an Ot.

Failure ultrasnnic examinations of jet puinp str actures, written report 4/7/80 All Power Reactors with a IEB 80-08 Examination of Requires report of non.

60 Days CP and/or OL no later than Containnent Liner Penetration destructive examinations of April 7, 1980 Welds flued head design penetrations