ML19343D126
| ML19343D126 | |
| Person / Time | |
|---|---|
| Site: | Grand Gulf  |
| Issue date: | 03/30/1981 |
| From: | Tedesco R Office of Nuclear Reactor Regulation |
| To: | Mcgaughy J MISSISSIPPI POWER & LIGHT CO. |
| References | |
| NUDOCS 8104090531 | |
| Download: ML19343D126 (24) | |
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[t\\, c [ (0,h NUCLEAR REGULATORY COMMISSION UNITED STATES 6
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.y WASHINGTON, D. C. 20555
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OJ MAR 3 0 1981 f-6
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[7 Docket Nos.: 50-416/417 64k,g 8/
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Mr. J. P. McGaughy, Jr.
Assistant Vice President - Nuclear Production
-Mississippi Power and Light Company 4
6 P. O. Box 1640 Jackson, Mississippi 39205
Dear Mr. McGaughy:
SUBJECT:
CHECKLIST OF GENERIC LETTERS AND BULLETINS FOR 1980 Attached for your information is a listing of generic letters and bulletins issued to Power Reactor Licensees and Applicants in 1980. The listing is in two parts:
(a) those itens sent to Power Reactor Licensees and applicants, and (b) those items sent to applicants only.
The listing identifies the addressee generically, by BWR type and licensing s ta tus. Should you have questions regarding this list with respect to Grand Gulf Nuclear Station, Units 1 and 2, contact our licensing project manager.
Sincerely, l
(gest c R '
I Robe L. Tedesco, Assistant Director for Licensing Division of Licensing
Enclosure:
As stated cc: See next page 810409 0 53j lh
MAR 3 01981 Mr. J. P. Mc6augby Assistant Vice President - Nuclear Production Mississippi Power & Light Company P. O. Box 1640 Jackson, Mi sissippi 39205 cc:
Robert B. McGehee, Esq.
Wise, Carter, Child, Steen & Caraway P. O. Box 651 Jackson, Mississippi 39205 Troy B. Conner, Jr., Esq.
Conner, Moore & Corber 1747 Pennsylvania Avenue, N. W.
Washington, D. C.
20006 Mr. Adrian Zaccaria, Project Engineer Grand Gulf Nuclear Station Bechtel Power Corporation Gaithersburg, Maryland 20760 Mr. Alan G. Wagner, Resident Inspector Route 2 Box 150 Port Gibson, Mississippi 39150
[
Mr. N. L. Stampley, Sr. Vice President Engineering, Production & Construction P.O. Box 1640 Jackson, Mississippi 39205 Mr. L. F. Dale Nuclear Project Manager P.O. Box 1640 c
Jackson, Mississippi 39205 Mr. John Richardson P. C. Box 1640 Jackson, Mississippi 39205
MAR 3 0 ;981 LETTERS AND Bl!Lt.ETINS TO POWER REACTOR LICfNSFES.
APPLICANTS FOR OPERATING LICENSES ANI)
HOLDERS OF CONSTRUCTION PERMITS
i i
RESPONSE
DATE
)))
SUBJECT PURPOSE DATE 1/3/80 All Power Reactor Licensees NUREG-0630 " Cladding, Swelling Extend Comnent Period 14 Days and Rupture - Models for LOCA Analysis" i
1/7/80 All Power Reactor Licensees Quality Assurance Requirements Review QA Program.for None (Except Arkansas Nuclear One, Regarding Diesel Generator Fuel diesel generator fuel required Units 1 and 2)
Oil oil (unless exception taken) 1/10/80 All BWR Licensees BWR Control Rod Failures Requesting recent experience 90 Days (except Humboldt 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 operability 1/14/ 80 All Power Reactor IEB 79-01B Environmental Qualifi-Requesting additional infor.
45 Days Facilities with an OL cation of Class IE Equipment mation on Class-IE electrical and equipment 90 Days
RESPONS.E DATE TO SUBJECT PURPOSE DATE 1/21/80 All BWR Licensees with a IEB BO-02 Inadequate Quality Requesting Information on 90 Days Cp or OL Assufynch for N' cTear~ S6pplied feedwater spargers and u
EqulMrent,
thernal sleeves from Marvin Engineering 1/29/80 All Power Reactor Licensees Low Level Radioactive Waste Informing of revised require-Before Disposal ments on waste forns; submit Ope ration-revised Process Control no. speci fic Program (if required) date 2/6'/80 All Holders of Power IEB 80-03 Loss of Charcoal from Requiring inspection and a5 Days Reactor OLs and cps Standard Type II, 2 Inch. Tray evaluation of charcoal adsor-Adsorber Cells ber cells 2/8/80 All PWR Reactor IEB 80-04 Analysis of a PWR Main Review accident analysis'for-90 Davs Facilities Holding OLs Steam Line Break with Continued containment overpressure and and to those nearing Feedwater Addition the reactivity increase from Licensing cooldown 2/23/80 All LWR Licensees LWR Primary Coolant System Pressure Requires 1) description of valve 14 Days Isolation Valves configuration 2) description of testing and 3) description of modifications if necessary
RESP 04SE DATE TO SUBJECT PURPOSE DATE
~
2/29/80 All Power Reactor Facilities IEB 79-OlB Enviro'nmental Qualifi-Transmits supplemental None with an OL cation of Class IE Equipment infonnation in the fonn required of questions and answers 3/6/80 All Operatf ; B&W Reactor Crystal River 3 Reactor Trip from Requires information on 60 Days Licensees Approximately 100% Full Power
'NNI/ICS, corrective actions and
'and expanded review of 11 Days IEB 79-27 Enhanced F.ission Gas Release information that the Problem Nond
~
3/10/80 All LWRs 4
has been resolved required 3/18/80
~All PWR Power Reactor IEB 80-05 Vacuum Condition Requires review of all systems 90 Days Facilities -ciding OLs Resulting in Damage to Chemical.
that contain low pressure or and to these afth a CP Volume Control System (CVCS) holdup tanks and description of Holdup Tanks corrective action if necessary i.
l 3/10/80 All Power hactor Emergency Planning Transmitting NUit.G-0654 None Licensees and Applicants
" Criteria for Preparation and required for a Licease to Operate Evaluation of Radiological a Nuclear Power Rea.ctor Emergency Response Plants and (FSAR Docke:ed)
Preparedness in Support of i
Nuclear Power Plants (For Interim Use and Consnent).
e
RESP 0ftSE DATE TO SUBJECT PURPOSE DaTE 3/12/80 All Operating Nuclear Plants NRC Nuclear Data Link (NDL)
Transmits for information
'bae
" Nuclear Data Link Eeautred Soecifications" 3/1 3/80 All Power Reactor Facilities IEB B0-06 Engineered Safety Revien system drawings and T-? Days i
with an OL Feature (ESF) Reset Controls provide a schedule of testing to asture that upon reset all ESF equipment remains in the energency mode 4
3/28/B0 All Power Reactor Applicants Qualifications of Reactor Revised criteria for reactor Various -
and Licensees Operators operator training and licensino: 39 Days 4
(1) experience,2) training,3]
229 Days facility certifications, 4) and i
increased scope of exans 5)
'?1 Days requalification programs i
4/4/80 All GE BWR-3 and BWR-4 IEB 80-07 BWR Jet Pump Assembly Requires visual inspections and 33 Days Facilities with an OL Failure ultrasonic examinations of jet oump structures, written report i
4/7/80 All Power Reactors with a IEB 80-08 Examination of Requires report of non-63 Days CP and/or OL no later than Containment Liner Penetration destructive examinations of l
April 7,1980 Welds flued head design penetrations
RESPONSE '
DATE
))[
SUBJECT PURPOSE DATE j~ /7/80 All BWR Licensees Modifications to Boiling Water Information concerning the None A
J Reactor Control Rod Drive Systens NRC staff's conclusions on Required l
CRD system modifications to eliminate cracking in i
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 3
for safety systems required tech. Spec.submittals t
M l4/17/80 All Power Reactor Operating IEB 80-09 Hydramotor Actuator Report verifications that 60 Days l
Facilities and Holders of Deficiencies ample margin exists for Power Reactor Construction actuation with improper Fermits springs installed i
l4/25/80 All Power Reactor Licensees Clarification of NRC Requirements Information on facilities.
None i
for Emergency Response Facilities Required j
at Each Site 1
I4/25/80 Individual Licensees Effect of a DC Power Supply Confirm that the GE reference 30 Days Failure on ECCS Performance study regarding minimum ECCS l
equipment availability with a 1-DC power supply failure is appropriate for plant specific application
k
RESPONSE
DATE
]f )
SUBJECT PURPOSE DATE j
l5/6/80 All Power Reactor Facilities IEB 80-10 Contamination of Non-Report on the review of 45 Days with an OL or CP radioactive System and Resulting systers that could become Potential for Unmonitored. Uncon-contaminated due to leakage trolled Release to Environment valving errors; establish routine monitoring program n
5/7/80 All Operating Reactor Five Additional TMI-2 Related Transmits requirements for:
Various(See Licensees Requirements to Operating Reactors
- 1) Shift Manning 2) Licensing enclosure 1 1
Exams, 3) Licensee Dissemination of letter) of Operating Experiences 4)
LOFW and SBLOCA Generic Review and 5) Control Room Habitability 5/8/80 All Power Reactor Facilit-IEB 80-11 Masonry Wall Design Report on reevaluation of masonry 60 Days ies with an OL, except wall design with attachments and i
Trojan from safety related equipment 180 Days l
5/8/B0 Individual Licensees Transmitting NUREG-0645 " Report Information None of the Bulletins and Orders Task Required Force and appropriate NUREG-0626
" Generic Evaluation of Feedwater Transients and Small Break Loss-of-Coolant Accidents"
RESPONSE,
DATE Tf!
SUBJECT PURPOSE DATE 5/9/80 Each PWR with an OL IEB B0-12 Decay Heat Removal Report on adequacy of 30 Days System Operability decay heat removal capability during all modes of operation 5/12/80 All BWR's with an OL IEB 80-13 Cracking in Core Inspect and recort on core 30 Days Spray Spargers spray spragers and related piping 5/19/80 All Licensees with Reactor Fire Protection Rule Enclosing orcaosed rule None Operating Licenses Issued
" Fire Protection Program Required Prior to January 1,1979 for Nuclear Power Plants Operating Prior to Jan. 1, 1979 4
5/19/80 All Power Reactor Licensees Generic Technical Activity A-12 Requesting connents on Potential 60 Days fracture Toughness for Low Fracture Toughness.
and Lamellar Tearing on PWR Steam Generater and Reactor Coolant Pump Suoports NUREG-0577
! 5/22/80 All Licensees with Reactor Fire Protection Rule Enclosuir.g revised pages to None Operating Licenses Issued 5/19/80 letter on Fire Required Prior to January 1,1979 Protection 9
~.
- J RESPONSE.
DATE TC)
SUBJECT PURPOSE DATE i6/3/80 Individual Licensees Nuclear Safeguards Problems Participation in a study of No'ne people-related problems in Required nuclear safeguards
- 6/5/80 All BWR licensees Generic Activity A BWR Transmitting NUREG-0619 30 Days Cracks "BWR Feedwater Nozzle and l
Control Rod Drive Return Line Nozzle Cracking, requesting comments.
I 6/9/80 All Operating Reactor Five additional TMI-2 related Transmitting errata sheets to None Licensees requirements May 7 letter on five Required additional TMI-2 related 4
requirements 6/11/80 All Operating Pressurized Decay Heat Removal Capability Requesting amendment to TS re 120 Days Water Reactors reactor decay heat removal capability 6/12/80 All BWR's with an OL IEB 80-14 Degradation of Scram Report on review of SDV level 45 Days Discharge Volume Capability switches and associated piping
. RESPONSE DATE T0, SUBJECT PURPOSE DATE
~
6/18/80 All Nuclear Facilities IEB 80-15 Possible Loss of Hot-Report that all ENS facilities 60 Cays Holding OLs line with Loss of Off-Site Power would remain operational with a loss of offsite power 6/25/80 All Power Reactor Applicants Comission Memorandum and Order Transmitting Memorandum and None i
and Licensees (EQ)
Order dated May 27. 1980 re Required fire protection for electrical cables, and environmental qualification of electrical components j6/27/80 All Power Reactor IEB 80-16 Potential Misapplication Report on review and corrective 32 Eays Facilities with an OL of Rosemount Inc., Models 1151 and actions for improper Rosemount or a CP 1152 Pressure Transmitters with Transmitters Either "A" or "D" Output Codes j 6/30/80 All Applicants for Meetings on EQ Transmitting Federal Register.
None Construction Permits. Power Notice re Regional Meetings to Required Reactor Licensees -
discuss environmental Architect / Engineers and qualification of electrical Reactor Vendors equipment 4
I
l i,
RESPONSE -
l DATE TC, SUBJECT PURPOSE DATE F/2/80 All Pressurized Water Reactor TMI-2 Lessons Learned Enclosing Model Techical 60 Days Licensees Specifications for NUREG-l 0578 TMI-2 Lessons Learned Category A Items, requires i
submittal l7/2/80 All Boiling Water Reactor TMI-2 Lessons Learned Enclosing Model Technical 60 Days Licensees Specifications for NUREG-0578 TMI-2 Lessons Learned Category A Items, Requires submittal h/3/09 All BWR Power Reactnr IEB 80-17 Failure of Control Report on review of emergency 14 Days Facilities Holding Ols Rods to Insert During a Scram operating procedures. on one at a BWR manual and one automatic scram test l
i F/7/80 All Boiling Water Reactors.
Scram Discharge Volume Designs Requesting amendment to technica199 Days specifications with respect to control rod drive scram discharge volume capability F/11/80 To All Applicants for Licensing Schedule Requests Comment 30 Days Operating Licenses and Construction Permit Holders
RESPONSE
DATE T0[
SUBJECT PURPOSE DATE 7/18/80 All BWR Power Reactor IEB 80-17 Supplement 1 Report on 50V systems.
45 Days Facilities Holding OLs Failure of Control Rods to install water level Insert During a Scram at a monitoring system BWR 7/22/80 All Boiling Water Reactors Scram Discharge Volume Referencing 7/7/80 letter None and stating that T5 change Required request is a Class III license fee submittal 7/22/80
' All BWR Power Reactors IEB B0-17 Supplement 2 Report on review of 50V 7 Days failures Revealed by Testing vent system Subsequent to Failure of Control Rods to Insert During A Scram at a BWR 7/24/80 All PWR Power Reactor IEB 80-18 Maintenance of Report on calculations of 60 Days Facilities Holding OLs Adequate Minimum Flow Thru minimum cooling flow for and to those PWRs Centrifugal Charging Pumps centrifugal charging pumos nearing Licensing Following Secondary Side High and corrective actions if Energy Line Rupture necessary 7/ 31/ 80 All Nuclear Power IEB 80-19 Failures of Mercury-Report on use and surveillance 90 Days facilities llaving Either Wetted Matrix Relays in Reactor of mercury-wetted matrix an OL or a CP Protective Systems of Operating relays Nuclear Power Plants Designed by Combustion Engineering
. RESPONSE, DATE TO SUBJECT PURPOSE 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 W-2 spring return switches 7/31/80 All Licensees of Operating Interim Criteria for Shift Staffing Requires the development and None Plants and Applicants for implementation of adminis-Required Operating Licenses and Holders trative procedures by of Construction Permits 10/31/80 8/1/80 All Applicants for Con-
" Functional Criteria for Emergency For information and connent 30 Days struction Permits, Licensees Response Facilities" NUREG-0696 of Plants Under Constru-ction and All Operating Nuclear Power Plants B/7/80 All Operating Power lessons Learned Tech Specs Referencing Letters of None Reactor Licensees 7/2/80 and requesting Required Amendment fee C1assification 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
. RESPONSE.
]f l SUBJECT PURPOSE DATE j
DATE 8/20/80 All BWRs with Mark I Mark I Containment Long-Term Enclosing Cy of NUREG-None Containment Program 0661 " Mark I Containment Required Long-Term Program Safety Evaluation Report, Re-solution of Generic Technical Activity A-7"
- 8/22/80 All BWR Power Reactor IEB 80-17 Supplement 3 Report on procedures requiring 14 Days Facilities Holding OLs Failures Revealed by Testing innediate manual scram on Subsequent to Failure of various conditions Control Rods to Insert During a Scram at a BWR
- 9/5/B0 All Licensees of Preliminary Clarification of Requests connents, discusses No specific Operating Plants and TMI Action Plan Requirements Regional Meetings date -
Applicants for Approx.
Operating Licenses and 30 Days Holders of Construction Permits i
- 9/19/80 All Licensees of Preliminary clarification of Addendum to 9/5 letter None Operating Reactor Plants TMI Action Plan Requirements Required and Applicants for Operating Licenses and lloiders of Construction Permits
. RESPONSE LTE TO SUBJECT PURPOSE DATE 130/80 All Power Reactor Facilities IEB 79-OlB Supplement 2 Information in the form None with an OL Environmental Qualification of of questions and answers Required Class IE Equipment
)/1/80 All Licensees of Operat.ing Environmental Qualification of Requests voluntary 30 Days Plants and Applicants for Safety-Related Equipnent assistance in an EQ testing audit program Operating Licenses and Holders of Construction Permits 0/1/80 All BWR Licensees BWR Scram System Submit plans for partici-30 Days pation in long term program to upgrade scram systems 0/6/80 All Power Reactor Implementation of Guidance from Information and summary of Nane Licensees and Applicants Unresolved Safety Issue A-12 staff's program required
" Potential for low Fracture Toughness and Lamellar Tearing on Component Supports" 10/21/80 All Operating Pressurized Seismic Qualification of Forwards preliminary None Water Reactor Licensees Auxiliary Faadwater Systens probabilistic assessment of Required seismically induced loss of decay heat renoval systems, discusses long term program
. RESPONSE DATE TO SUBJECT PURPOSE DATE 10/24/80 All Power Reactor facilities IEB 79-010 Supplement 3 Clarification of submittal None with an OL Environmental Qualification of requirements Required IE Equipment 10/ 31/B0 All Licensees of Operating Post TMI Requirements Forwarded requirements and 30 Days Plants and Applicants for NUREG-0737 implementation dates.
Operating Licenses and requested commitments lloiders of Construction Permits 31/04/80 All lloiders of Construction ODYN Code Calculation Information on staff's use None Permits and Operating of ODYN Code in analyses of Required Licenses for BWRs pressurization transients 11/6/80 All Light Water Reactor IEB 80-21 Valve yokes Report on inspection and 30 Days F6cilities lloiding Ol.s or supplied by Malcolm Founory corrective actions concerning cps Company, Inc.
Malcom valve yokes ll/13/ B0 All Licensees of Oper-Emergency Plan Describes submittal schedules None ating Reactor Plants, of new rule Required lloiders of Construction Permits and Applicants for Construction Permits
% RESPONSE
- DATE TO SUBJECT PURPOSE DATE
- - 11/13/80 All BWR Licensees Generic Activity A-10 Forwards requirements of 45* Days NUREG-0619 "BWR Feedwater Nozzle and Control Rod Drive Return Line Nozzle Cracking"
- 11/14/80 All Power Reactors Fire Protection Forwards new Section 50.48 None and Appendix R, discusses Required schedules and SERs 4
l11/14/80 All Nuclear Power IEB 80-23 Failures of Report on use and replacement 45 Days OL or CP solenoid Valves Engineering scheduie for affected valves l
Corporation l
Ill/20/80 All Power Reactors IEB 80-24 Prevention of Roport on actions to prevent 45 Days with OLs Damage due to Water Leakage flooding of containment Inside Containment 4
l11/24/80 All Power Licenses with Appendix R to 10 CFR 50 re.
F6rwards new regulations, lists 30 Days Plants Licensed prior to Fire Protection open items concerning fire if January 1, 1979 protection for each facility necessary 4
j e
RESPONSE
DATE T0[
SUBJEL' PURPOSE DATE
- 11/25/B0 Operating Reactors with Inservice inspection Programs Requests voluntary-infor-None Prestressed Concrete Contain-Fation on containment Required i
ment Structures tendon tests 111/25/80 To All Power Reactor Fire Proetction Forwards revised None Licensees with Plants Federal Register Notice Required Licensed Prior to Jan'#ry 1, 1979 4
4
- 11/26/80 All Licensees of Operating Orders on Environnental Provides clarification on None Plants and Applicants for Qualification of Safety record requirements Required Operating Licenses and Related Electrical Holders of Construction Equipment Permits 12/9/ 80 To All BWR Licensees BWR Scram Discharge System Transmits staff's Generic None Safety Evaluation Report Required for Information a
1 RESPONSE DATE 11!
SUBJECT PURPOSE DATE 12/9/B0 All Licensees of Operating Emergency Planning Forwards 1) NUREG-0654, None Reactor Plants, Holders of Revision 1" Criteria for Required Construction Permits and Preparation and Evaluation Applicants for Construction of Radiological Emergency Permits Response Plans and Preparedness in Support 4
of Nuclear Power Plants" and 2) sunenary rating sheets for evacuation time estimates 4
1 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/Br All BWR Licensees IES 80-17 Supplement 4 Requires testing of 45 Diys
- Failure of Control Rods to' Insert Continuous Monitoring During a Scram at a BWR System for Scram Discharge Volume 12/19/B:
All BWR Power Reactor IEB 80-25 Operating Problems Review and testing require-90 Days facilities with an OL with. Target Rock Safety Relief ments for Target Rock S/RV and fermi 2, Shoreham Valves a
12/22/B0 All Licensees of Operating Control of Heavy Loads Implement interim action 90 Days Plants and Applicants for Operating Licenses and Review and Report 0 Months Permits Results 9 Months
b LETTERS TO OPERATING LICENSE AND CONSTRUCTION PERMIT APPLICANTS E
o
RESPONSE
- DATE TO SUBJECT PURPOSE DATE lI/18/B0 All BWR Applicants Issuance of NUREG-0313 Rev.1 For information and 60 Days
" Technical Report on Material connents Selection and Processing Guide-lines for BWR Coolant Pressure Boundary Piping" 9
2/5/B0 All Construction Permit Issuance of NUREG-0588, " Interim Transmitting NUREG-0588 60 Days and Operating License Staff Position on Equipment for interim use and Applicants Qualifications of Safety-Related connent (All PWR & BWR Electrical Equipment
-Applicants) 2/21/80 All Operating License Qualification of Safety-Related Requires review of all.
45 Days Applicants Electrical Equipment safety related electrical equipment qualification documentation and description of descriptive action if necessary 1
l 3/10/8C All Pending Operating Actions Required from Operating Requires information related~
Info. to License Applicants of License Applicants of Nuclear to Auxiliary Feedwater Systems be provided Nuclear Steam Supply Steam Supply Systems Designed by as amend-
]
Systems Designed by Westinghouse and Combustion Eng.
ment on
~i Westinghouse and resulting from the NRC Bulletins application Combustion Engineering and Orders Task Force Review Regarding the Three Mile Island 4
l Unit 2 Accident
RESPONSE
'DATE 10 SUBJECT PURPOSE DATE-3/10/80 All Power Reactor Licensees Issuance of NUREG-0654/ FEMA-REP-1, Transmitting NUREG-06S4/ FEMA l/1/81
& Applicants for a License
" Criteria for Preparation and REP-1 for interir u>e in to Operate a Nuclear Power Evaluation of Radiological Emergency evaluation of erergency plans Reactor FSAR Docketed Response Plans and Preparedness in Call Power Reactor Licensees)
Support of Nuclear Power Plants 1
3/11/80 All Applicants for Constru-Change of _ Submittal Date for Postpones date for submittal 45 Days ction Permits and Licensees Evaluation Tine Estimates of evacuation tine estimates of Plants Under Construction pending GA0 review completion 4/21/80 All Construction Permits Information Request on Category I Requests response to list of None and Operating Licensee Masonry Walls Employed by Plants questions concerning Category I given Applicants Under CP and OL Review pasonry walls
!4/2,4/80 All Pending Operating Actions Required from Operating Requires evaluaticns and other Info. to License Applicants of License Applicants of Nuclear Steam information concerning auxiliary be provided Nuclear Steam Supply Supply Systems Designed by Babcock feedwater systers as an Systems Designed by and Wilcox Resulting from the NRC amendment Babcock and Wilcox Bulletins and Orders Task Force on applica-Review regarding the Three Mile tion Island Unit 2 Accident (auxiliary feedwater systems) 11/25/80 All Applicants for Operating Commission Menorandum and Order of Requests date fer completion of None Licenses and Holders of May 23,1980 (referencing IE staff review relating to. equip-given Construction Permits Bulletin 79-OlS-Supplement No. 2 -
ment qualificatien of electrical Q.2 & 3 - Sept. 30,1980) equipment 5