NRC Generic Letter 1993-04
K.UNITED STATESNUCLEAR REGULATORY COMMISSIONWASHINGTON, D.C. 20555June 21, 1993TO: FOR ACTION -ALL HOLDERS OF OPERATING LICENSES OR CONSTRUCTIONPERMITS FOR WESTINGHOUSE (W)-DESIGNED NUCLEAR POWER REACTORS EXCEPTHADDAM NECKFOR INFORMATION -ALL HOLDERS OF OPERATING LICENSES OR CONSTRUCTIONPERMITS FOR COMBUSTION ENGINEERING (CE)-DESIGNED AND BABCOCK ANDWILCOX (B&W)-DESIGNED NUCLEAR POWER REACTORS AND HADDAM NECKSUBJECT: ROD CONTROL SYSTEM FAILURE AND WITHDRAWAL OF ROD CONTROL CLUSTERASSEMBLIES, 10 CFR 50.54(f) (GENERIC LETTER 93-04)
Purpose
The U.S. Nuclear Regulatory Commission (NRC) is issuing this generic letter(1) to notify addressees about a single failure vulnerability within theWestinghouse solid state rod control system that could cause an inadvertentwithdrawal of control rods in a sequence resulting in a power distribution notconsidered in the design basis analyses, and (2) to require, in accordancewith Section 50.54(f) of Part 50 of Title 10 of the Code of FederalRegulations (10 CFR 50.54(f)), that all action addressees provide the NRC withinformation describing their plant-specific findings related to this issue andactions taken. The NRC will use this information to assess licenseecompliance with the plant-specific licensing basis regarding single failuresin the rod control system.BackgroundThe staff issued Information Notice 93-46, "Potential Problem WithWestinghouse Rod Control System and Inadvertent Withdrawal of a Single RodControl Cluster Assembly," dated June 10, 1993, to alert licensees to thepotential for an inadvertent withdrawal of one or more rod control clusterassemblies in Westinghouse plants in response to an insert signal.
Description of Circumstances
On May 27, 1993, operators at the Salem Nuclear Generating Station, Unit 2,experienced problems with the rod control system. During an attempt towithdraw Shutdown Bank A, the operator observed that the analog rod positionindicator (ARPI) did not indicate that the control rods were being withdrawn.The operator stopped attempting to withdraw rods at 20 steps as indicated onthe group demand indicator. At this time the ARPI indicated that all of therods in Shutdown Bank A were at the 0 step position. (The function of thegroup demand indicator is to provide the operator with information on the9306170326 PaP 4J t O~ri) oo3 9 f56Z/t& ) i0
KGeneric Letter 93-04 -2 -June 21, 1993position to which the rods should have moved on the basis of the demand fromthe rod control system. The function of the ARPI is to show the actualposition of each rod.) The operator then attempted to insert Shutdown Bank A.However, one control rod (1SA3) withdrew to 8 steps as indicated by the ARPIwhile the group demand indicator counted down from 20 steps to 6 steps. Theoperator continued to try to insert the Shutdown Bank A control rods until thegroup demand indicator showed a rod position of zero. The operator observedthat the indicated position on the ARPI for control rod 1SA3 was 15 steps.Public Service Electric & Gas (the licensee) removed power from the rod bypulling fuses, and rod 1SA3 dropped to the 0 step position as indicated by theARPI.The licensee initiated troubleshooting activities on the rod control system atSalem, Unit 2. An NRC augmented inspection team (AIT) was sent to SalemUnit 2 to evaluate this issue and observe the investigation of this event bythe licensee.The licensee, in response to NRC questions, has postulated that, for the eventthat occurred on May 27, 1993, a single failure in the rod control systemcaused a single rod to withdraw from the core 15 steps while the operator wasapplying a rod insertion signal. The failure of an integrated circuit on aslave cycler decoder card disrupted the normal sequence of pulses that the rodcontrol system sends to the rods in the selected bank. Normally, on insertdemand, the pulses are staggered in a sequence that leads to rod insertion.With the failure, the rod control system periodically sent simultaneous pulsesto the movable gripper coil, lift coil, and stationary coil for each of therods in the selected bank. Under these conditions each rod in the bank mayeither remain where it is or withdraw from the core when a rod movement demandoccurs.When the rod control system is in the automatic mode of operation, a rodmovement demand is generated automatically in response to changes in turbineload and changes in the average reactor coolant temperature. Rod movementthen occurs without any operator action until the demand is satisfied. Whenthe rod control system is in the manual mode of operation, a rod movementdemand is generated only in response to operator manipulation of the IN-HOLD-OUT switch, given no failures in the demand circuit.DiscussionThe rod control system installed at Salem Unit 2 is used at all Westinghouse-designed pressurized-water reactors (PWRs) except Haddam Neck. Initialassessments by Westinghouse showed that a single failure in the rod controlsystem could result in unintended rod withdrawal movements in multiple controlrods. Although the reactor protection system is independent of the rodcontrol system logic and, therefore, the scram function is not compromised,there remains a concern that a previously unanticipated single-failuremechanism may exist in the control system that can initiate or aggravatereactivity excursions and result in fuel failure. This is of particularimportance since the frequency of demand on the rod control system for poweradjustments is very high (daily in many plants).
Generic Letter 93-04 -3 -June 21, 1993General Design Criterion (GDC) 25, "Protection system requirements forreactivity control malfunctions," of Appendix A to 10 CFR 50 specifies thatacceptable fuel design limits not be exceeded for any single malfunction ofthe reactivity control systems. The Standard Review Plan (NUREG-0800)Sections 15.4.1, 15.4.2 and 15.4.3, discuss the specified acceptable fueldesign limits for single failures in the reactivity control system (in thiscase the rod control system). One of these fuel design limits is that fuelrods do not violate the minimum departure from nucleate boiling ratio (DNBR)criterion.The staff requested activation of the Westinghouse Owners Group RegulatoryResponse Group (RRG) on June 8, 1993. The Westinghouse Owners Group RRG metwith the staff on June 14, 1993, to discuss the RRG generic safety assessmentof the Salem event. The RRG concluded that the failure can produce awithdrawal signal if either a manual or automatic insert command is given toany rod control cluster assembly (RCCA) bank or overlapping banks. The RRGalso discussed analysis results showing that asymmetric RCCA withdrawal atpower and from a subcritical condition are the limiting cases. For both ofthese cases conservative bounding evaluations indicate that a small percentage(less than 5 percent) of the fuel rods experience a calculated DNBR below thelimit value.The staff believes that the safety significance of this issue is not highbased on the following information:* All automatic safety functions will perform as designed.* For the worst cases of single failures in the rod control system only asmall number (or none) of the fuel rods will be below the DNBR limit.* Not all events will lead to fuel rods below the DNBR limit.Furthermore these events do not provide a challenge to the reactor coolantsystem or the containment boundary. Although the staff believes that thesafety significance of this issue is not high, it believes that compliancewith plant-specific licensing bases is in question for all action addressees.GDC 25 specifies that acceptable fuel design limits not be exceeded for anysingle malfunction of the reactivity control systems. The analyses discussedby the Westinghouse Owners Group indicated that fuel failures could resultfrom single failures identified as a result of the Salem event.Westinghouse issued a Nuclear Safety Advisory Letter (NSAL)93-007, datedJune 11, 1993, recommending the following actions:1. Licensed operators should continue the normal process of verifyingthat rod motion is proper for required movement.2. Licensees should confirm the functionality of rod deviationalarms.3. Operators should review the advisory letter to ensure theirunderstanding of the event.
Generic Letter 93-04-4 -June 21, 19934. The Westinghouse Owners Group (WOG) survey its members regardingrod misalignment events and provide a summary.Implementation of the recommendations in the Westinghouse NSAL is judged bythe NRC staff to be a prudent action.The licensee for Salem is implementing several compensatory actions prior tothe startup of either unit. These actions include:* Enhanced rod control system surveillances prior to startup and duringoperation* More frequent periodic surveillances of the rod control system* Modification of the startup procedure to preclude an asymmetric rodwithdrawal from the subcritical condition by-first pulling control rods while still highly borated to theestimated critical position, then,-deborating to criticality* Classroom and simulator training addressing the effects of potentialsingle failures in the rod control system* Issuance of standing orders to heighten operator awareness of potentialrod control system malfunctions* Review of event response procedures to assure adequate guidance tooperators in the event of a rod control system malfunctionRequired ResponsePursuant to Section 182a of the Atomic Energy Act of 1954, as amended, and10 CFR 50.54(f), each action addressee is required to submit writteninformation as follows:1. Within 45 days from the date of this generic letter:(a) Provide an assessment of whether or not the licensing basis foreach facility is still satisfied with regard to the requirementsfor system response to a single failure in the rod control systemand provide a supporting discussion for this assessment in lightof the information generated as a result of the Salem event.(b) If the assessment in 1(a) indicates that the licensing basis isnot satisfied* provide an assessment of the impact of potential singlefailures in the rod control system on the licensing basis ofthe facility Generic Letter 93-04 -5 -June 21, 1993describe any compensatory short-term actions taken or that willbe taken to address any actual or potential degraded ornonconforming conditions (see Generic Letter 91-18,Reference 1) such as-additional cautions or modifications to surveillance andpreventive maintenance procedures-additional administrative controls for plant startup andpower operation-additional instructions and training to heighten operatorawareness of potential rod control system failures and toguide operator response in the event of a rod control systemmalfunction2. If the assessment in 1(a) indicates that the licensing basis is notsatisfied, within 90 days from the date of this generic letter provide aplan and schedule for the long-term resolution of this issue.Address the required written reports to the U.S. Nuclear RegulatoryCommission, ATTN: Document Control Desk, Washington, D.C. 20555, under oathor affirmation under the provisions of Section 182a of the Atomic Energy Actof 1954, as amended, and 10 CFR 50.54(f). In addition, submit a copy to theappropriate regional administrator. This generic letter requires informationthat will enable the NRC to verify that the licensee is complying with itscurrent licensing basis regarding single failure vulnerability within the rodcontrol system. Accordingly, an evaluation justifying this informationrequirement is not necessary in accordance with 10 CFR 50.54(f).
Backfit Discussion
This generic letter does not involve any backfitting. It only requires (underthe provisions of 10 CFR 50.54(f)) the submittal of information needed by theNRC staff to assess the compliance by the action addressees with existing NRCrules and regulations.Although the staff believes that the safety significance of the issueaddressed by this generic letter is not high, there is an urgency to theinformation requirement involved based on the consideration that plants may becurrently operating outside of their licensing bases and the information isneeded promptly to allow the staff to assess this situation. Therefore, anotice of opportunity for public comment on this generic letter was notpublished in the Federal Register.
Generic Letter 93-04-6 -June 21, 1993
Paperwork Reduction Act Statement
This generic letter contains information collection requirements that aresubject to the Paperwork Reduction Act of 1980 (44 U.S.C. 3501 et seq.).These requirements were approved by the Office of Management and Budget,Approval Number 3150-0011, which expires June 30, 1994.The public reporting burden for this collection of information is estimated toaverage 40 hours4.62963e-4 days <br />0.0111 hours <br />6.613757e-5 weeks <br />1.522e-5 months <br /> per response, including the time for reviewing instructions,searching existing data sources, gathering and maintaining the data needed,and completing and reviewing the collection of information. Send commentsregarding this burden estimate or any other aspect of this collection ofinformation, including suggestions for further reducing reporting burden, tothe Information and Records Management Branch (MNBB-7714), U.S. NuclearRegulatory Commission, Washington, D.C. 20555; and to the Desk Officer, Officeof Information and Regulatory Affairs, NEOB-3019, (3150-0011), Office ofManagement and Budget, Washington, D.C. 20503.Compliance with the request for the following information is purely voluntary.The information would assist the NRC in evaluating the cost of complying withthis generic letter.(1) the licensee staff time and costs to perform requested inspections,corrective actions, and associated testing(2) the licensee staff time and costs to prepare the requested reports anddocumentation(3) the additional short-term costs incurred as a result of the inspectionfindings such as the costs of the corrective actions or the costs ofdown time(4) an estimate of the additional long-term costs that will be incurred inthe future as a result of implementing commitments such as the estimatedcosts of conducting future inspections or increased maintenanceThe NRC is issuing this generic letter to the information addressees to alertthem to a problem with the Westinghouse rod control system and inadvertentwithdrawal of a control rod. It is expected that recipients will review theinformation for applicability to their facilities and consider actions, asappropriate, to avoid similar problems. However, the requested actions andreporting requirements applicable to the action addressees are not applicableto the information addressees; therefore, no specific action or writtenresponse is required from them.
Generic Letter 93-04-7 -June 21, 1993If you have any questions about this matter, please contact one of thetechnical contacts listed below or the appropriate Office of Nuclear ReactorRegulation project manager.Sincerely,ames G. Partlowssociate Director for ProjectsOffice of Nuclear Reactor RegulationEnclosure:List of Recently Issued NRC Generic LettersTechnical contacts: Margaret Chatterton, NRR(301) 504-2889Timothy Collins, NRR(301) 504-2897Lead project manager: Thomas Alexion, NRR(301) 504-1326Reference:Generic Letter 91-18, "Information to LicenseesRegarding Two NRC Inspection Manual Sectionson Resolution of Degraded and NonconformingConditions and on Operability," issuedNovember 7, 1993 EnclosureGL 93-04June 21, 1993 LIST OF RECENTLY ISSUED GENERIC LETTERSGenericLetterDate ofIssuanceSuijhietT ciiad Tn--,,, ------ ----- --JW _ s@JUS93-03NOT AS YET ISSUED93-0293-01NRC PUBLIC.WORKSHOP ONCOMMERCIAL GRADE PRO-CUREMENT AND DEDICATIONEMERGENCY RESPONSE DATASYSTEM TEST PROGRAMLIMITED PARTICIPATION BY NRCIN THE IAEA INTERNATIONALNUCLEAR EVENT SCALETHERMO-LAG 330-1FIRE BARRIERSOFFICE OF NUCLEAR REACTORREGULATION REORGANIZATION03/23/9303/03/9312/31/9212/17/9210/10/92ALL HOLDERS OF OLs ORCPs FOR NPRs AND ALLRECIPIENTS OF NUREG-0040,"LICENSEE CONTRACTOR ANDVENDOR INSPECTION STATUSREPORT" (WHITE BOOK)ALL HOLDERS OF OLs ORCPs FOR NPRs, EXCEPTFOR BIG ROCK POINT ANDFACILITIES PERMANENTLYOR INDEFINITELY SHUTDOWNALL HOLDERS OFOLs OR CPsFOR NPRsALL HOLDERS OFOLs OR CPsFOR NPRsALL HOLDERS OFOLs OR CPsFOR NPRs92-0992-0892-0783-28SUPPLEMENT 1REQUIRED ACTIONS BASED ONGENERIC IMPLICATIONS OF SALEMATWS EVENTS10/07/92ALL LIGHT-WATERREACTOR LICENSEESAND APPLICANTS92-06OPERATOR LICENSING NATIONALEXAMINATION SCHEDULENRC WORKSHOP ON THESYSTEMATIC ASSESSMENT OFLICENSEE PERFORMANCE(SALP) PROGRAM09/06/9209/04/92ALL POWER REACTORLICENSEES ANDAPPLICANTS FOR ANOLALL HOLDERS OFOLs OR CPsFOR NPRs92-05OL = OPERATING LICENSECP = CONSTRUCTION PERMIT
Generic Letter 93-04 --7 -\1J June 21, 1993If you have any questions about this matter, please contact one of thetechnical contacts listed below or the appropriate Office of Nuclear ReactorRegulation project manager.Sincerely,Original signed byJames G. PartlowJames G. PartlowAssociate Director for ProjectsOffice of Nuclear Reactor RegulationEnclosure: ( uJ4-)List of Recently Issued NRC Generic LettersTechnical contacts: Margaret Chatterton, NRR(301) 504-2889Timothy Collins, NRR(301) 504-2897Lead project manager: Thomas Alexion, NRR(301) 504-1326Reference:Generic Letter 91-18, "Information to LicenseesRegarding Two NRC Inspection Manual Sectionson Resolution of Degraded and NonconformingConditions and on Operability," issuedNovember 7, 1993*SEE PREVIOLg CONCURRENCEADPR:NRR *ADT:NRRJGPartlow\' WTRussell064\/93 06/21/93*C/HICB:DRCH:NRR *D/DRCH:NRRJSWermiel BABoger06/17/93 06/17/93*OGCB:DORS:NRR *ADM:RPBNECampbell TechEd06/17/93 06/16/93*D/DORS:NRRBKGrimes06/18/93*D/SRXB:NRRACThadani06/18/93*SRXB:DSSA:NRRMSChatterton06/18/93*C/OGCB:DORS:NFGHMarcus06/18/93*OGCSHLewis06/18/93*SRXB:DSSA:NRRTECollins06/18/93*C/SRXB:DSSA:NRRRCJones06/18/93DOCUMENT NAME: 93-04.GL
-Generic Letter 93-XX\-June XX, 1993-7 -If you have any questions about this matter, please contact one of thetechnical contacts listed below or the appropriate Office of Nuclear ReactorRegulation project manager.James G. PartlowAssociate Director for ProjectsOffice of Nuclear Reactor RegulationTechnical contacts:Margaret Chatterton, NRR(301) 504-2889Timothy Collins, NRR(301) 504-2897Lead project manager: Thomas Alexion, NRR(301) 504-1326Reference:Generic Letter 91-18, "Information to LicenseesRegarding Two NRC Inspection Manual Sectionson Resolution of Degraded and NonconformingConditions and on Operability," issuedNovember 7, 1993Attachments:List of Recently Issued NRCGeneric Letters*SEE PREVIOUSADPR:NRRJGPartlow06/ /93*C/HICB:DRCH:tJSWermiel06/17/93*OGCB:DORS:NRFNECampbell06/17/93CONCURRENCE06/"2J93IRR *D/DRCH:NRRBABoger06/17/93t *ADM:RPBTechEd06/16/93OV.Irnes% W /93*D/ SRXB:NRRACThadani06/1&/93*SRXB:DSSA:NRRMSChatterton06/18/93C/OGCB:DORS:NRRGHMarcus(4#.1106/i' /93*OGCSHLewis06/18/93*SRXB:DSSA:NRR *1TECollins I06/18/93 XC/SRXB:DSSA:NRRRCJones06/18/93DOCUMENT NAME: SALEM.GL
- Generic Letter 93-XX-7 -June XX, 1993If you have any questions about this matter, please contact one of thetechnical contacts listed below or the appropriate Office of Nuclear ReactorRegulation project manager.James G. PartlowAssociate Director for ProjectsOffice of Nuclear Reactor RegulationTechnical contacts:Margaret Chatterton, NRR(301) 504-2889Timothy Collins, NRR(301) 504-2897Lead project manager: Thomas Alexion, NRR(301) 504-1326Reference:Generic Letter 91-18, "Information to LicenseesRegarding Two NRC Inspection Manual Sectionson Resolution of Degraded and NonconformingConditions and on Operability," issuedNovember 7, 1993Attachments:List of Recently Issued NRCGeneric Letters*SEE PREVIOUSADPR:NRRJGPartlow06/ /93*C/HICB:DRCH:tJSWermiel06/17/93*OGCB:DORS:NRFNECampbell06/17/93CONCURRENCEADT:NRRWTRussell06/ /93IRR *D/DRCH:NRRBABoger06/17/93Z *ADM:RPBTechEd06/16/93D/DORS:NRR C/OGCB:DORS:NRRBKGrimes Marcus06/ /93 06/ /93D/SRXB:N OGCACTh#/a SHLewis06//t093 06/ /93*SRXB :DSSA:NRR *SRXB:DSSA:NR SRXB:DSSA:NRRMSChatterton TECollins CJones-'06/18/93 06/18/93 6/ /93DOCUMENT NAME: SALEM.GL
Aeneric Letter 93- XX'-7 -June XX, 1993If you have any questions about this matter, please contact one of thetechnical contacts listed below or the appropriate Office of Nuclear ReactorRegulation project manager.James G. PartlowAssociate Director for ProjectsOffice of Nuclear Reactor RegulationTechnical contacts:Margaret Chatterton, NRR(301) 504-2889Timothy Collins,(301) 504-2897NRRLead project manager:Thomas Alexion, NRR(301) 504-1326Reference:Generic Letter 91-18, Information to LicenseesRegarding Two NRC Inspection Manual Sectionson Resolution of Degraded and NonconformingConditions and on Operability," issuedNovember 7, 1993Attachments:List of Recently Issued NRCGeneric Letters*SEE PREVIOUSADPR:NRRJGPartlow06/ /93*C/HICB:DRCH:tJSWermiel06/17/93*OGCB:DORS:NRFNECampbell06/17/93CONCURRENCEADT:NRRWTRussell06/ /93IRR *D/DRCH:NRRBABoger06/17/93t *ADM:RPBTechEd06/16/93D/DORS:NRRBKGrimes06/ /93D/SRXB:NRRACThadani06/ /936 RXB:DSSA:NRRSChattertonr6/C/93C/OGCB:DORS:NRFGHMarcus06/ /93OGCSHLewis06/ /93SRXB:DSSA:NRRTEColIi906//X/93C/SRXB:DSSA:NRRRCJones06/ /93DOCUMENT NAME: SALEM.GL
Gdeneric Letter 93--7 J-7 -June XX, 1993If you have any questions about this matter, please contact one of thetechnical contacts listed below or the appropriate Office of Nuclear ReactorRegulation project manager.James G. PartlowAssociate Director for ProjectsOffice of Nuclear Reactor RegulationTechnical contacts:Margaret Chatterton, NRR(301) 504-2889Timothy Collins, NRR(301) 504-2897Lead project manager: Thomas Alexion, NRR(301) 504-1326Reference:Generic Letter 91-18, "Information to LicenseesRegarding Two NRC Inspection Manual Sectionson Resolution of Degraded and NonconformingConditions and on Operability," issuedNovember 7, 1993Attachments:List of Recently Issued NRCGeneric Letters*SEE PREVIOUSADPR:NRRJGPartlow06/ /93*C/HICB:DRCH:tJSWermiel06/17/93*OGCB:DORS:NRFNECampbell06/17/93CONCURRENCEADT:NRRWTRussell06/ /93IRR *D/DRCH:NRRBABoger06/17/931 *ADM:RPBTechEd06/16/93D/DORS:NRRBKGrimes06/ /93D/SRXB:NRRACThadani06/ /93SRXB:DSSA:NRRMSChatterton06/ /93C/OGCB:DORS:NRRGHMarcus06/ 93~SHLewi s06//f/93SRXB:DSSA:NRR ITECollins 106/ /93 1legid 04t'8lo.C/SRXB:DSSA:NRRICJones)6/ /93DOCUMENT NAME: SALEM.GL
"Generic Letter 93-6 J-6 -June XX, 1993If you have any questions about this matter, please contact one of the technicalcontacts listed below or the appropriate Office of Nuclear Reactor Regulationproject manager.James G. PartlowAssociate Director for ProjectsOffice of Nuclear Reactor RegulationTechnical contacts:Margaret Chatterton, NRR(301) 504-2889Timothy Collins, NRR(301) 504-2897Lead project manager: Thomas Alexion, NRR(301) 504-1326Attachments:List of Recently Issued NRCGeneric Letters*SEE PREVIOUS CONCURRENCEADPR:NRR ADT:NRRJGPartlow WTRussell0 /93 06/ /93C/ wDRCH:NRR NRRSbmiel BABoger06/17/93 064 7/ 3OGCB:DORS:NRR *ADM:RPBNECampbell TechEd06//7/93 khC6/16/93D/DORS:NRRBKGrimes06/ /93D/SRXB:NRRACThadani06/ /93SRXB:DSSA:NRRMSChatterton06/ /93C/OGCB:DORS:NRRGHMarcus06/ /93OGCSHLewis06/ /93SRXB:DSSA:NRRTECollins06/ /93C/SRXB:DSSA:NRRRCJones06/ /93I
rv)-'Generic Letter 93-ih---5 -June XX, 1993Compliance with the following request for information is purely voluntary.The information would assist NRC in evaluating the cost of complying with thisgeneric letter:(1) the licensee staff time and costs to perform requested inspections,corrective actions, and associated testing(2) the licensee staff time and costs to prepare the requested reports anddocumentation(3) the additional short-term costs incurred as a result of the inspectionfindings such as the costs of the corrective actions or the costs ofdown time(4) an estimate of the additional long-term costs which will be incurred inthe future as a result of implementing commitments such as the estimatedcosts of conducting future inspections or increased maintenanceNRC is issuing this generic letter to the information addressees to alert themto a problem with the Westinghouse rod control system and inadvertentwithdrawal of a control rod. It is expected that recipients will review theinformation for applicability to their facilities and consider actions, asappropriate, to avoid similar problems. However, the requested actions andreporting requirements applicable to the action addressees are not applicableto the information addressees; therefore, no specific action or writtenresponse is required from them.If you have any questions about this matter, please contact one of thetechnical contacts listed below or the appropriate Office of Nuclear ReactorRegulation project manager.James G. PartlowAssociate Director for ProjectsOffice of Nuclear Reactor RegulationTechnical contacts:Margaret Chatterton, NRR(301) 504-2889Timothy Collins, NRR(301) 504-2897Lead project manager: James Stone, NRR(301) 504-1419Attachments: (aOJ)( a s A e* )List of Recently Issued NRC Generic Letters*SEE PREVIOUS CONCURRENCEADPR:NRR ADT:NRRJGPartlow WTRussell06/ /93 06/ /93HICB:DRCH:NRR C/HICB:DRCH:NRR D/DRCH:NRRECHarinos JSWermiel BABoger06/ /93 06/ /93 06/ /93OGCB:DORS:NRR ADM:RPB SRXB:DSSA:NRRNECampbell TechEd smut> MSChatterton06/ /93 06/11/9306/ /93D/DORS:NRRBKGrimes06/ /93D/SRXB:NRRACThadani06/ /93SRXB:DSSA:NRRTECollins06/ /93C/OGCB:DORS:NRRGHMarcus06/ /93OGCSHLewis06/ /93C/SRXB:DSSA:NRRRCJones06/ /93