ML20247C354
| ML20247C354 | |
| Person / Time | |
|---|---|
| Site: | Palo Verde, Sequoyah, Vermont Yankee, San Onofre, Cook, Maine Yankee, Fort Calhoun, 05000000 |
| Issue date: | 03/17/1989 |
| From: | Zech L NRC COMMISSION (OCM) |
| To: | Markey E HOUSE OF REP. |
| References | |
| TASK-***, TASK-TM CCS, NUDOCS 8903300172 | |
| Download: ML20247C354 (20) | |
Text
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'o UNITED STATES NUCLEAR REGULATORY COMMISSION
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WASHINGTON, D. C. 20556
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March 17, 1989 CHAIRMAN The Honorable Edward J. Markey United States flouse of Representatives Washington, D.C.
20515
Dear Congressman liarkey:
In response to your letter of February 21, 1989, I am enclosing the detailed information you requested concerning the status of implementation of Three Mile Island (TMI) Action Plan items.
The data indicates that although the vast majority of TMI-related action items have been completed, a small number remain to be implemented for specific plants.
Significant progress has been r
made in resolving those remaining, but their final resolution is not needeo to assure the acequate safety of commercial reactor operations.
I have today submitted to the President NUREG-1355, "The Status of Recommendations of the President's Commission on the Accident at Three Mile Island - A Ten Year Review."
A copy of this report is enclosed for your information.
The report summarizes the status of actions taken by the NRC, in response to recommendations made i
by the Presidential Commission, in the 10 years since the accident occurred in March 1979.
This report also reflects how revised practices and standards are being implemented both by the NRC and throughout the industry.
The decade following the TMI accident has witnessed an unparal-1eled growth and strengthening of our regulatory program for the construction and operation of nuclear power plants.
The objective of our program is to improve the overall safety of commercial nuclear power reactor operations and thereby enhance public protection.
The Commission believes that the recent improvement in certain key operational safety indicators that we monitor and l
improvements in Systematic Assessment of Licensee Performance results, as well as the heightened safety awareness and improved understanding of lessons learned from the accident, reflect substantial progress in achieving that objective.
I hope this information will prove useful to you.
Sincerely, Dv.
Lando W. Ze
, Jr.
7 OcE
Enclosures:
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QUESTIONS AND ANSWERS CONCERNING IMPLEMENTATION OF THE TMI ACTION PLAN REQUIREMENTS QUESTION 1,.'
What is the implementation status of improvements ordered under the TMI Action Plan, any related Inspection and Enforcement Bulletins and Orders, and Commission Orders?
ANSWER.
Data from the NRC Safety Issue Management System (SIMS) indicates that there are 10,514 TMI Action Plan issues.
Based on our most recent review of the data, there are 264 TMI-related actions for which implementation is still required. Almost half of these issues (128) are re' lated to 12 plants located at 10 sites.
In addition, resolution of hardware issues related to the control room design human factors review and safety parameter display system imple-mentation accounts for 118 of the issues that are not fully implemented.
These two issues require very detailed and time-consuming analyses and significant physical changes to licensee facilities.
In many cases, these changes were so extensive that they were scheduled for implementation over several refueling cycles.
It should be noted that the NRC staff considers issues to be unimplemented when agreement with licensees has not been reached regarding the adequacy of proposed technical alternatives to TMI Action Plan issues.
QUESTION 2.
Specifically, how many operating nuclear' reactors and reactors under construction have not completed full implementation of all TMI Action Plan Items? Please provide a list of these reactors, the items which remain to be fully implemented at each reactor, and the schedule for final implementation of each incomplete item.
ANSWER.
There are 88. licensed reactors which have not completed implementation of all TMI Action Plan items. The listing below identifies the items not yet t
implemented at these reactors. Current licensee implementation schedules are also provided. The data in the list reflects a recent update of TMI Action Plan status.
In those cases where the projected implementation completion dates are shown as "NONE," the licensees' original schedule had passed without confirmation that implementation was completed. The NRC staff is working with the licensees to confirm these implementation dates so that the data may be incorporated in the next routine update of the SIMS database.
There is a relatively large number of items that have not been implemented at Browns Ferry.
In fact, the Browns Ferry site represents 25% of all of the issues not yet implemented. All three Browns Ferry units have been shut down for an extended period. Browns Ferry Unit 2 is scheduled to restart late this year after almost all of the remaining TMI Action Plan items have been imple-mented. TVA requested deferral until after restart of implementation at Unit 2
, j i
of TMI items related to I.D.1-Detailed Control Room Design Review, I.D.2-Safety Parameter Display System, II.B.3-Post Accident Sampling System (including technical specifications) and II.K.3.28-ADS Modifications.
Interim modifications and/or compensatory actions for these deferred items have been proposed by the licensee and accepted by the staff. Units 1 and 3 do not have restart schedules; however, the NRC will ensure that the outstanding TMI items are factored into the development of their schedules.
Because the implementation status for TMI items changes constantly for plants under construction, the NRC does not require licensees to continually report completion of TMI items while construction is in progress. Although NRC inspectors continually observe and evaluate the quality of ongoing construction i
efforts, the NRC does not audit the completion status of TMI items and other regulatory issues except to ensure that all requirements are met before a plant is licensed. Therefore, we are unable to provide implementation status information for reactors that are under construction, i
i PLG5 TMICVE NOT IMPLEMENTE9 ALL VMI ACTION PLM ITDS PROJECTED IMPLEMDTAi!0N
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PLMT ISSUEt TITLE COMPLEi!ON DATE i
ARKANSAS 2 FA-F071 KTA! LED CONTROL ROOM M S!$N FOLLONUP 12/19 IEAVER VALLEY 2 MPA-F071 KTAILD CONTROL ROOM K S!6N FOLLOWUP 05/09 Ill ROCK Po!NT 1.C.1.2.3 SHORT TEM ACC. 4 PROC REV-!CC REVISED PROCD NONE8 i
818 ROCK POINT
!.C.1.3.1 SHORT TDM ACC. & PROC REV - TRANS & ACC REVISE PROC NOMI Ill ROCK P0lNT 1.9.2.1 PLMT SPDS CONSOLE MSCR!Pi!0N 10/91 IG ROCK PO!NT 1.0.2.2 PLANT SPDS CONSOLE INSTALLED 10/91 l
I!$ ROCK POINT 1.8.2.3 SPDS FULLY INLEMENTED 10/91 I!B ROCK PO!NT MPA-F071 KIA! LED CONTROL ROOM DES!$N FOLLOWUP 12/92 IRAIDWOOO 1 1.1.2.3 SPIS FULLY IN LE E NT D 09/90 f
IRAIDWOOO 1 MPA-F071 KfA!LD CONTROL ROOM DESIGN FOLLOWLP 09/90 MAIDuo08 2
!.0.2.3 SPM FULLY IMPLEMENTED 09/90 f
IRAIDWOOO 2 MPA-F071 MTA! LEO CONTROL ROOM M S!'BN FOLLOWUP 09/90 IR01NS FEMY 1
!!.I.3.4 PAS-PLANTMODS(LLCATIl M/91
{
IROW S FERRY 1
!!.F.1.2.A ACCIMNT MON!f0 RING - NOILE 6AS MON!!0R 04/91
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IROWNS FERRY !
II.F.1.2.0 ACCIID T NONITORIN6 - 109tNE/PARf!CULATE SAMPLING M/91 IRO WS FERRY 1
!!.F.1.2.C ACCIENT MON!iORIN6 - CONTAIN HI6H RANGE MON M/91 IROWNS FEMY 1
!!.F.1.2.3 ACCI ENT HONITORING - CONTAIN PRESSURE M/91 IRO WS FORY !
!!.F.1.2.E ACCIENT MONITORING - CONTAIN MATER LEVEL 06/91 ItouMSFERT1
!!.F.1.2.F ACCIDENT MONITORIN6 - CONTAIN N2 M/91 IROWS FERRY 1 II.F.2.4
!N37 FOR KTECT OF INAS CME C00LINE - INSTALL A00'L INST 06/91 IRouMSFURY1 II.K.3.13.A 940 TASK FORCE - HPCI & RCIC INIT!Ai!ON LEVEL - ANALYSIS 06/91 IROWS FEMT 1
!!.K.3.13.I' I40 TASK FORCE - WCl & RCIC INITIATION LEVEL - MODS M/91 IROWS FEMY !
!!.K.3.18 A H0 TM FORCE - AIS ACTUAfl0N STUDY M/91 N0gNS FE MY 1
!!.K.3.11.I 140 TASK FORCE - PROPOSED APS MOO!FICATIONS 06/91 MONSFERRY!
!!.K.3.18.C H0 TASK FORCE - MKE AIS MODIFICAi!0NS M/91 IROWS FEMI 1
!!.K.3.22.8 HO TASK FORCE - RCIC SUCTION MODS NWEt l
IReuNS FERRY 1
!!.K.3.28 IN Tm FORCE - WALIFICAil0N OF ADS ACCUMULATORS M/91 IROWNS FEM T 1
!.C.1.2.1 SINRf TEM ACC. 4 PROC REV-!CC KVISD PROCD M/91 IROWSFERRY1
!.C.1.3.1 SINRT TERN ACC. 4 PROC REV - TRANS & ACC REVISE PROC M/91 MOWS FEMY 1 f.I.2.1 PLANT SPIS CONSOLE K SCRIPT 10N M/91 IRouuS FERRY !
!.I.2.2 PLANT SPIS CONSOLE l ETALLEI M/91 MOWSFERRY1 1.8.2.3 SPIS FELY INLDENTD M/91 IROWSFEMY!
FA-1083 TS C0VER D If IL 83-36 4 83-37 M/91 MON S FERRY 1 re-F071 NTA! LEI C NTROL RO M M S!$N FOLLOWUP 07/96 IROWS FERRY 2
!!.I.3.3 PAS - PROCDURES NONEt IRO WS FERRY 2
!!.I.3.4 PAS - PL MT MOIS (LL CAT Il 12/90 IR9WS FERRY 2
!!.F.1.2.4 ACCIENT MONITORINS - l WILE 6As MONITOR 06/89 IROWS FEMY 2
!!.F.1.2.0 ACCIDDT MONITORINS - 100!ME/ PARTICULATE SAMLING M/89 IROWSFERRY2 II.F.1.2.C ACCIN NT MONITORING - CONTAll NIIM RANGE MON M/Of l
IRoun$FEMY2 II.F.1.2.0 ACCINNT MONITOR!IE - CORTAIN PRESSURE.
M/89 IROWSFEMY2 II.F.1.2.E ACCIMNT MONITORING - CONTAIN HTER LEVEL M/89 MOWS FERRY 2
!!.F.1.2.F ACCIID T MONITORING - CONTA!N H2 M/89 IROWS FEMY 2
!!.F.2.4
!NT FOR MTECT OF IMS CORE COOLING - INSTALL AD0'L INST 06/19 IROWNS FEMY 2
!!.K.3.13.A 940 TASK FORCE - WCI & RCIC INITIATION LEVEL - ANALYSIS M/89 IRouuSFEMY2
!!.K.3.13.8 H6 TASK FORCE - FCI & RCIC INITIATION LEVEL - MODS 06/89 IRO WS FERRY 2 II.K.3.10.A N0 TASK FORCE - AIS ACTUAi!ON STUDY M/89 IRWNSFERRY2
!!.K.3.18.0 140 TASK FORCE - PROPOSED ADS N00lFICATIONS M/89 BROWSFERRY2
!!.K.3.18.C Ino TASK FORCE - MKE AM MOO!FICAi!DNS M/IT NOWSFERRY2 II.K.3.20 H0 1ASK FORCE - QUALIFICATION OF AM ACCUMULATORS M/89 IROWSFERRY2 1.C.I.2.0 SMORT TEM ACC. & PROC REV-!CC KVISD PROCED M/89 MouuSFEMY2
!.C.1.3.1 SMRT TEM ACC. 4 PROC KV - TRANS 4 ACC KVISE PROC M/89 IRobuSFERY2
!.I.2.1 PLANT SPDS CONBOLE HSCRIPi!ON 12/90 IRWNSFERRY2 fI.2.2 PLMT SPIS CMSOLE INSTALLD 12/90
'NDEE' signifies that the licensee's original projected implementation completion date had passed without confirmation that implementation was completed.
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P ANIS THAT CVE NOT IMPLE;[NTG ALL TMI ACflEN PLC ITEMS BROWNS FERRY 2 1.D.2.3 SPDS FULLY !MPLEMENTED 12/10 BROWNS FERRY 2 MPA-B003 IS COVERED BY SL 83 36 4 83-37 12/90 BROWNS FERRY 2 MPA4071 DETA! LED CONTROL ROOM DES!6N FOLLOWUP 06/93 BROWNS FERRY 3
!!.3.3.4 PAS - PLANT NODS (LL CAT 3) 09/903 BROWNS FERRY 3
!!.E.4.1.3 KDICATED 'H2 PENETRATIONS - INSTALL NONE8 BROWNS FERRY 3
!!.F.1.2.A ACCIENT MONITORIN6 - NOBLE 6AS M0WITOR 09/90 BROWNS FERRY 3
!!.F.1.2.8 ACC!KNT MONITORIN6 - 10 DINE / PARTICULATE SAMPLING 09/90 BROWNS FERRY 3
!!.F.1.2.C ACCIENT MON!iORING - CONTAIN Hl6H RAN6E MON 09/90 8A0WNS FERRY 3
!!.F.1.2.D ACCIENT MONiiORING - CONTAIN PRESSURE 09/90 BROWNS FERRY 3 11.F.1.2.E ACCIENT MONITORIN6 - CONTA!N MATER LEVEL 09/90 SROWNS FERRY 3 II.F.1.2.F ACCIDENT MON!f0 RING - CONTAIN N2 09/90 BROWNS FERRY 3
!!.F.2.4 INST FOR KTECT OF INAD CORE C00LIN6 - INSTALL ADD'l INST 09/90 BA0NNS FERRY 3
!!.K.3.13.A B40 TASK FORCE - FCI & RCIC INITIAi!0N LEVEL - ANALYS!$
09/90 BROWNS FERRY 3
!!.K.3.13.3 H0 TASK FORCE - HPCI & RCIC INiilAi!ON LEVEL - MODS 09/90 BROWNS FERRY 3 II.K.3.!I.A InD IASK FORCE - ADS ACTUAT!ON STUDY 09/90 BROWNF FERRY 3
!!.K.3.18.3 169 TASK FORCE - PROPOSED ADS MODIFICAT!DNS 09/90 BROWNS FERRY 3
!!.K.3.18.C 340 TASK FORCE - MAKE ADS MODIFICAi!ONS 09/90 BROWNS FERRY 3
!!.K.3.28 360 TASK FORCE - QUALIFICATION OF ADS ACCUMULATORS 09/90 BROWNS FERRY 3
!.C.1.2.A SHORT TERM ACC. I PROC REV-ICC REANAL GUIDE 09/90 BROWNS FERRY 3 1.C.1.3.A SHORT TERM ACC. 4 PROC REV -TRANS & ACC REANAL SUIDE 09/90 BROWNS FERRY 3
!.D.2.1 PLANT SPDS CONSOLE KSCRIPi!ON 09/90 BROWNS FERRY 3
!.D.2.2 PLANT SPDS CONSOLE INSTALLED 09/90 BROWNS FERRY 3
!.D.2.3 SPDS FULLY I rLEMENTED 09/90 BROWNS FERRY 3 MPA-1083 TS COVERED BY SL 83-36 4 83-37 09/90 BROWNS FERRY 3 MPA4071 KTAILED CONTROL ROOM ES!6N FOLLOWUP 09/94 BRUNSWICK 1 It!.A.2.2 UPIRAK PREPAREDNESS - METRO DATA 12/89 DRUNSWICK 1 II.F.2.3 INST FOR KTECT OF INAB CORE C00LIN6 - DESCRIBE OTHLR 03/89 BRUNSu!CK 1 II.F.2.4 INST FOR KTECT OF INAD CORE COOLIN6 - INSTA;L ADD'L INST 03/89 MUNSWICK 1 WA-F071 KTA!LD CONTROL ROOM DESIGN FOLLOWUP 10/90 BRUNSulCK 2
!!!.A.2.2 UPGRAK PREPARDESS - MTRO DATA 09/89 BRUNSW!CK 2 FA4071 KTAILD CONTROL ROOM KS!6N FOLLOWUP 10/90 BYRON 1 1.8.2.3 SPDS FULLY ! FLEMENT D 09/93 ITRON 1 MPA4071 KTA! LED CONTROL ROOM KS!6N FOLLOWUP 09/90 3YRON 2 1.B.2.3 SP M FULLY 1rLEMENT D 09/90 BYRON 2 WA4071 KTAILD CONTROL ROOM KS!6N FOLLOWUP 09/90 CALVERT CLIFFS 1 MPA 4071 KTAILD CONTROL ROOM DES!6a FOLLOWUP 06/92 CALVERT CLIFFS 2 FA-F071 KTA!LD CONTROL ROOM KS!6N FOLLOWUP 06/91 CATAtlA 1
!.D.2.1 PLANT SPDS CONSOLE K SCRIPTION 12/89 CATAWBA 1 1.D.2.2 PLANTSPtsCONSOLEINSTALLED 12/99 CATAWBA 1 1.D.2.3 SPDS FIA.LT IFLEENTD 12/89 EATAWBA2
!.D.2.2 PLAsi SPOS CONSOLE INSTALLED 12/89 CATAWBA 2 1.D.2.3 SPDSFULLYIPLEMEWTD 12/89 CLINTON WA-F071 KTA! LED CONTROL ROOM DES!6N FOLLOWUP NOME 8 COOK 1
!!.F.1.2.E ACCIENT MON!TORIN6 - CONTAIN WATER LEVEL 06/89 COOK 2 II.B.3.4 PAS-PLANTMODS(LLCATIl NONEt CRYSTAL RIVER 3
!!!.D.3.4.3 CONTROL ROOM HA0! TAI!Llif - !PLEMENT MODS NONEl CRYSTAL RIVER 3
!!.B.1.3 RCS VENTS PROCD URES 04/89 CRYSTAL RIVER 3 WA 1083 15 COVERD BY EL B3 36 413-37 06/89 CRfSTAL RIVER 3 MPA4071 KTA! LED CONTROL ROOM DES!6N FOLLOWUP 12/10 DAVIS K SSE I.C.1.2.0 SIEIRT TERM ACC. 4 PROC REV-!CC REVISD PROCD 03/90 DAY!S ESSE I.C.1.3.8 SHORT TERM ACC. 6 PROC REV - TRANS & ACC REVISE PROC 03/10 DAvls BESSE FA4008 KTAILD CONTROL ROOM DES!6N REV PR06 PLAN 02/90 DAV!$ K SSE FA-F071 KTAILD CONTROL R00M KSIGN FOLLOWUP 02/10 DRESDEN 2 MPA-F071 KTA! LED CONTR!I. ROOM DESIGN FOLLOWUP 09/90 DRESEN 3 WA-F071 KTAILD CONTROL R00M DES!6N FOLLOWUP 03/91 DUANE ARNOLD
!!!.D.3.4.3 CONTROL ROOM M481TA3!LITY - IFLEENT MODS 07/t9 1
'lIDIIE" signifies that the licensee's original projected tuplementation completion date had passed without confirmation that taplementation was completed.
PtOff, VHAT HAVE NOV IMPLEMENTED ALL iMI ACT!QN PLAN liEMS 4
j FARLET1 MPA-F071 DETA! LED CONTROL ROOM M SIGN FOLLOWUP 00/90 FARLET2 MPA-F071 MTA! LED CONTROL ROOM DES!6N FOLLOWUP 00/91 FEMI 2 III.D 3.4.2 CONTROL ROOM HAlliAl!L!iY - SCHED MODS 10/89 FEMi 2
!!.F.1.2.3 ACCIENT MONITORING-10 DIE / PARTICULATE SAMPLIN6 10/89 i!HI 2
!!.K.3.18.C 340 TASK FORCE MAKE ADS MODIFICAi!DNS 10/19 FT CALHOUN MPA-F071 KTAILED CONTROL ROOM ES!6N FOLLONUP 00/90 Fi. ST. VRA!N
!.C.1.2.A SHORT TER% ACC. 4 PROC REV !CC REANAL SUIDE 09/99 FT. ST. VRAIN l.C.1.2.3 SHORT TERM ACC 4 PROC REV-ICC REVISED PROCD 09/89 Fi 5T. VRAIN
!.C.1.3.A SHORT TERM ACC. 6 PROC REV -TRMS 4 ACC REANAL SUIDE 09/89 FT. St. VRAIN
!.C.1.3.8 SHORT TERM ACC. & PROC REV - TRMS & ACC REVISE PROC 09/89 6!mA
!!!. A.2.2 UP6RADE PREPAREDNESS - METRO DATA N/89 6AAND 6ULF MPA-F071 MTA! LED CONTROL R00M MS!6N FOLLONUP 12/90 HADDAM #ECK III.1.3 RCS VENTS PROCDURES 07/89 HADDAM NECK ll.F.1.2.F ACCIENT MCNITORIN6 - CONTAIN H2 07/90 HADDAM NECK
!!.t.3.23.5 B40 TASK FORCE PONER ON PU W SEALS - MAKE MODS 01/90 HARRIS 1
!.D.2.3 SPDS FULLY IMPLEMENTED 07/99 HARRIS 1 MPA-F071 MTA! LED CONTROL ROOM MS!6N FOLLOWUP 07/89 HATCH 1 MPA-F071 MTAILED CONTROL ROOM DES.'3N FOLLOWUP 12/92 HATCH 2 MPA-F071 DETAILED CONTROL ROOM DES!6N FOLLOWUP 12/92 INDIAN PCINT 2
!!.F.2.4 INST FOR DETECT OF INAD CORE C00L!N6 - INSTALL ADD'L INST 05/89
!NDIAN PO!NT 2 1.A.4.2 LON6-TERM TRAIN!N6 $!MULATOR UP6RADE 03/91 INDIAN POINT 2 MPA-F071 MTA! LED CONTROL ROOM MS!6N FOLLOWUP 05/89
[NDIAN PO!NT 3 II.K.3.12 MTICIPATORT TRIP DN TUR$!NE TRIP 07/89 INDIAN POINT 3 MPA-F071 MTAILD CONTROL ROOM DES 16N FOLLOWUP 06/89 LASALLE 1 MPA-F071 DETA! LED CONTROL ROOM DESIGN FOLLOWUP 00/92 LASALLE2 MPA-F071 KTAIL D CONTROL R00M DES!6N FOLLOWUP 00/92 MC6UIRE 1
!!.D.1.2.8 RELIEF 4 SAFETY VALVE TEST REO - PLMT SPECIFIC REPORT 04/89 MCSUIRE 1
!!.F.1.2.8 ACCIDENT MON!TORIN6 - 10 DINE /PARTIC14. ATE SAMPLIN6 05/89 MC6UIRE2
!!.D.1.2.1 RELIEF & SAFETY VALVE TEST REO - PLANT SPECIFIC REPORT 04/t9 MCSUIRE2
!!.F.1.2.1 ACCIDENT MONITORIN6 - 10 DINE / PARTICULATE SAMPL!N6 01/t9 MILLSTONE 1
!!!.A.2.2 IPSRADE PREPAREDNESS METRO DATA 02/90 MILLSf0NE1
!.C1.2.3 SHORT TERM ACC. 6 PROC REV-!CC REVISD PROCD N/89 GILLSTONE1
!.C.1.3.8 SHORT TERM ACC. A PROC REV - TRANS & ACC REVISE PROC N/89 MILLSTONE 1 1.D.2.1 PLANT SPDS CONSOLE DESCRIPT!DN N/89 j
M!uSTCE 1
!.D.2.2 PLMT SPDS CONSOLE INSTALLD N/89 I
M!uSTONE1
!.D.2.3 SPDS FULLY IMPLEMENTD 06/89 MILLSTONE 1 WA-8083 TS COVERED BY 6L 83 36 4 83 37 00/89 CILLSTONE 1 MPA F071 MTAILD CONTROL ROOM MS!6N FOLLOWlF 00/89 MILLSTONE 2
!!.D.3.2 VALVE POSITION INDICAi!0N - TECH SPEC 09/90 MILLSTONE 2
!!.F.2.5 INST FOR M TECT OF INAD CCRE C00LIN6-TECH SPECS NONEt j
l MILLSTONE 3
!.D.2.3 SPDS FULLY !WLEMENTED 07/89 MONTICELLO
!.A.1.1.4 STA - DESCRIM LON6 TERM PR06RM 09/89 NIE MILE POINT 1 WA-F071 M TA! LED CONTROL ROOM DESIGN FOLLOWUP
/92 N!NE MILE POINT 21.D.2.1 PLANT SPDS CONSOLE DESCRIPTION 03/90 NINE MILE POINT 2 !.D.2.2 PLMT SPDS C0kSOLE INSTALLED 03/90 NIE MILE POINT 2 !.D.2.3 SP96 FULLY !FLEENTO 03/90 NIE MILE POINT 2 MPA F071 KTA!LD CONTROL ROOM DES!6N FOLLOWUP 03/90 NORTH ANM 1
!!.B.1.2.8 RELIEF 4 SAFETY VALVE TEST RE9 - PLMT SPECIFIC REPORT 12/89 NORTH A MA 1 FA-F071 KTAILD CONTROL ROOM ESIGN FOLLOWUP N/89 l
NORTH A MA 2 67.4.1 REACTOR C00LMT PUMP TRIP 06/89
)
NORTH A MA 2
!!.D.1.2.8 REL!EF 4 SAFETY VALVE TEST RED - PLMT SPECIFIC REPORT 12/89 l
NORTH AMA 2 WA-F071 KTAILD CONTROL R00M ESIGN FOLLOWUP N/89 OCONEE 1
!!!.D.3.4.3 CONTROL ROOM HAl!TAl!LITY - !WLEMENT MODS NOEL DCONEE 1 MPA-1083 TS COVERO If 6L 13-36 4 83 37 09/89 OCDEE 1 WA-F065 EER6ENCY OPERATIONS FACILITY N/89 OCONEE 2
!!!.D.3.4.3 CONTROL ROOM HAlliAl!LITY - IMPLEENT MODS NONEl date had passed without coeffraatton that tuplementatio
__n__-__________.
PLM18 YHAT HAVE NOT !MPLEENTE9 ALL YM! ACTION PLAN IVEMS DCCNEE 2 MPA-1083 TS COVERED BY 6L B3-34 4 83-37 09/89 OCONEE 2 MP4-F065 EER6ENCY OPERAi!DNS FACILITY 08/89 OCONEE 3
!!I.D.3.4.3 CONTROL ROOM HAI! TAI!LITY - IMPLEMENT MODS NONE 1
OCONEE 3 MPA4065 EER6ENCY DPERATIONS FACIL!!Y 08/89 OYSTER CREEK MPA4008 MTAILED CONTROL ROOM DES!6N REV PR06 PLAN N0Et OYSTER CREEK M-F071 DETAILD CONTROL ROOM M S!6N FOLLOWUP NONEt PALISAMS
!!.D1.2.I RELIEF 4 SAFETY VALVE TEST REG - PLMi SPECIFIC REPORT 03/90 PALISADES II.S.1.3 RELIEF 4 SAFETY VALVE TEST REG - BLOCK VALVE TESi!N6 03/t0 PAllSADES
!!.F.2.4 INST FOR M1ECT OF IMO CORE CCOLIN6 - INSTALL ADD'l !NST NONEl PALISAMS M-1083 IS COVERED BY 6L 83-34 4 83 37 02/90 PALISADES 944071 MTAILD CONTROL ROOM M S!6N FOLLCWUP 07/10 PEACH 30TTOR 2
!!.F.2.4 INST FOR MTECT OF INAD CORE C00LIN6 - INSTALL ADD'L INST 04/89 PEACH BOTTOM 2
!.A.1.3.1 SHIFT MA M ING - LIMIT OVERi!ME 04/89 PEACH IOTTOM 2
!.D.2.1 PLANT SPDS CONSOLE DESCRIPTION 00/91 PEACH BOTTOR 2
!.D.2.2 PLMT SPDS CCNSOLE INSTALLED 00/91 PEACH BOTTOM 2 1.D2.3 SPDS FULLY IMPLEMENTED 00/91 PEACH 80TTOM 2 M4071 DETAILED CONTROL ROOM DESI6N FOLLOWUP 04/79 PEACH 80ff0M 3
!!.F.2.4 INST FOR DETECT OF INAD CORE C00LIN6 INSTALL ADD'l [NST 12/89 PEACH 80ff0M 3
!.A.I.3.1 SHIFT MAMIN6 - LIMIT OVERf!ME 04/89 PEACH BOTTOM 3 N F071 MTA! LED CONTROL ROOM MS!6N FOLLOWUP 12/89 PERRY 1 MPA4071 DETA! LED CONTROL ROOM DES!6N FOLLOWUP 01/91 P!L6 AIM
!!.E.4.2.5.3 CONTAINMENT !$0L MPENDABILITY - PRESS SETPOINT MODS 06/89 P!L6 AIM
!!.E.4.2.6 CONTA! MENT ISOL DEPENDABILITY - PUR6E VALVES 06/89 P!L6 RIM
!!.E.4.2.7 CONTA! MENT ISOL MPENDAIIL!if - RAD S!6NAL ON PURSE VALVES 06/89 PIL6 RIM
!!.F.2.4
!NST FOR DETECT OF INAD CORE C00LIN6 - INSTALL ADD'l INST NONEl P!LSR!M
!.8.2.1 PLANT SPDS CONSOLE DESCRIPTION 12/89 PIL6 RIM
!.I.2.2 PL MT SPDS CONSOLE INSTALLD 12/89 P!L6 RIM
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O
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!.D.2.3 SPDS FULLY IMPLEMENTED 08/09 SOUTH TEIAS 2
!.D.2.3 SPDS FULLY !FLEENTED 08/90 ST. LUCIE 1 MPA4071 MTAILED CONTROL ROOM M SIGN FDLLOuUP 12/90 ST. LUCIE 2 WA4071 MTA! LED CONTROL R00M DES!6N FOLL0ulF 12/90 SUMER 1
!!.I.1.2.8 RELIEF 4 SAFETY VEVE itsi RED - PLMT SPECIFIC REPORT 04/89
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!.P.2.3 SPDS FULLY IMPLEMD TD 06/91 SURRY !
MPA4071 MTAIL D CONTROL ROOM MSIGN FOLLOWUP NOEt SURRY 2
!!.D.1.2.3 RELIEF 4 SWETY VEVE TEST REO - PLANT SPECIFIC MPORT 04/90 SURRY 2 WA-F071 MTA!LD CONTROL R00M M S!6N FOLLOWUP N0E!
TROJAN MPA4071 MTA!LFD CONTROL ROOM MSIGN FOLLOWUP 12/89 TIRKEY POINT 3 11.1.1.2.0 REllEF i SWETY VEVE TEST REO - PLAiri SPECIFIC REPORT 11/89 TUR EY POINT 4
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QUESTI0h_3.
How many operating reactors and reactors under construction have received exemptions from TMI' Action Plan requirements?
. lease provide a list of those reactors and describe the nature of each exemption.
ANSWER.
An exemption is a permission granted to a licensee to deviate from the requirements of Commission regulations (see 10 CFR 50.12). However, in most cases, the TMI Action Plan issues were not implemented by specific changes to the NRC's regulations, but through the review of new license applications and through the imposition of confirmatory orders and specific license conditions.
For those matters implemented through the initial licensing review or by confirmatory order, the staff found the licensee's actions acceptable whenever they implemented the staff's recommendations or proposed technically acceptable alternatives.
In the five instances discussed below, implementation of the THI Action Plan resulted in new or modified NRC i
regulations. For these items, formal exemptions are required to permit deviation from compliance. For the 112 plants that now have licenses, only five exemptions from these new or modified regulations are now in effect. The following discussion provides further details on the regulations and associated exemptions resulting from the TMI Action Plan.
r i
9 TMI Action Plan I'em I.A.1.4 (Long-term Upgrade of Operations Personnel and t
Staffing) was issued in NUREG-0660. This item was later incorporated into 10 CFR 50.54 on April 23, 1983. Exemptions have been issued from these requirements for the number of licensed operators on site to the two smallest plants, La Crosse and Big Rock Point. La Crosse was permanently shut down in early 1987.
Thus Big Rock Point, a 75 MWe plant, is the only operating plant currently exempt from 10 CFR 50.54 (m)(2).
The regulation requires two senior reactor operators and two reactor operators on site when operating. With the exemption, Big Rock Point is allowed to operate with one senior reactor operator and two reactor operators.
TMI Action Plan Item I.A.3.1.3 (Revise Scope and Criteria for Licensing Exams -
Simulator Exams) was issued in NUREG-0737.
Subsequently,10 CFR 55.45 was modified in May 1987 to require simulator exams for licensed operators of all power reactors. The NRC has not issued any exemptions from 10 CFR 55.45(b).
TMI Action Plan Itcq II.B.1 (Reactor Coolant System Vents) was contained in NUREG-0737.
Subsequently,10 CFR 50.44(c) was modified to add section (iii),
which formalized the requirement for high point vents for the reactor coolant system and the reactor vessel. The NRC has issued three exemptions from this l
regulation. Big Rock Point was issued an exemption from the requirement to install reactor coolant system high point vents on the emergency condenser.
' The staff approved the exemption because the Big Rock Point emergency condenser is not needed or useful for accident scenarios that would generate noncondensible gases that could be vented by high point vent's.
Crystal River 3 and Rancho Seco have been exempted from the requirement to have reactor vessel head vents.
These exemptions were granted because these plants have the capability to vent noncondensible gases from the reactor vessel through high point vents installed in the hot leg of the reactor coolant system.
TMI Action Plan Item II.E.4.1 (Dedicated Hydrogen Penetrations) was contained in NUREG-0660 and NUREG-0737. The NRC staff position was that plants which use external recombiners or purge systems for containment post accident combustible gas control must provide dedicated containment penetrations for the recombiners or purge systems. This position was included in an NRC regulation when 10 CFR 50.44 was amended in late 1981. The NRC has not issued any exemptions from this section of that regulation.
TMI Action Plan Item III.A.2 (Improving Licensee Emergency Preparedness--Long-Term) was included in NUREG-0737 and referred to compliance with new emergency preparedness regulations (10 CFR 50.47) issued in 1980. The NRC has issued a number of one-time schedular exemptions from the required frequency of emergency preparedness exercises, but no technical exemptions from emergency preparedness regulations have been issued. Onij one such exemption is currently in effect.
i
. i For the Pilgrim facility, Boston Edison Company has requested and received three schedular exemptions regarding exercising the state and local offsite emergency response plans. These exemptions were granted in letters to the licensee dated December 9, 1987, May 11, 1988, and December 29, 1988, and were based on the fact that extensive improve 4nents were being made in both the Commonwealth of Massachusetts' and the local governmental emergency plans.
Only the December 29, 1988 exemption is currently in effect. This exemption extends the deadline for j
completion of a full-scale emergency preparedness exercise until 120 days following completion of the Pilgrim power ascension program, which is currently in progress.
i I
l l
'/-
QUESTION 4 Please describe all cases in which a utility reported i
implementation of an Action Plan but was subsequently found to be in violation or noncompliance with the requirement.
l In responding to this request, a search was made of the NRC inspection report data system (the 766 systen) to locate items of noncompliance and deviations from licensee commitments associated with TMI Action Plan items.
Information is entered and sorted in the 766 system in accordance with the inspection procedure used to perfonn the inspection. There are 12 inspection procedures-that relate directly to TMI Action Plan items. These procedures resulted in the issuance of over 400 inspection reports.
The staff reviewed all 766 system inspection data for the 12 procedures and found a total of eight (8) violations and two (2) deviations associated with f
TMI Action Plan items. The attached listing provides a brief description of these deviations and violations.* It is likely, however, that inspections performed under other inspection procedures not directly related to the TMI Action Plan also may have revealed deviations or violations associated with TMI Action Plan items. Violations of this type would not have been discovered by the search previously described.
Information on these deviations and viola-tions is not readily retrievable from the inspection report data system and has not been included. However, NRC inspectors continue to monitor licensee corrective actions for violations and deviations until the deficiencies are resolved.
- The severity level of each violation is noted. Severity levels are described in detail in Appendix C to 10 CFR, Part 2 of the Commission's regulations. Level 1 is the most severe and Level 5 is the least severe.
ATTACHMENT
~
VIOLATIONS AND DEVIATIONS ASSOCIATED WITH TMI ACTION PLAN ITEMS San Onofre, Unit 1; Docket 50-206/ Inspection Report 81-22 Auxiliary Feedwater System Auto Initiation and Flow TMI II.E.1.2 Indication Concrete expansion anchors providing seismic support for the auxiliary feedwater auto initiation instrument panel did not have fully engaged and torqued nuts. QA records disclosed that these nuts had been installed without required quality control inspections and documentation.
(Severity Level 5 violation)
Maine Yankee; Docket 50-309/ Inspection Report 84-02 Verify Correct Performance of Operating Activities TMI I.C.6 Equipment control procedures per ANS 3.2 implementation were inadequate and in violation of licensee comitments and NRC's confirmatory order dated 7/10/81.
(Severity Level 4 violation).
Maine Yankee; Docket 50-309/ Inspection Report 84-17 Accident Monitoring TMI II.F.1.3 Installation of containment hi range monitor channels insufficient in that detector assemblies were not environmentally qualified for post-accident conditions. Cable connector insulation needed.
(Severity Level 4 violation).
Vermont Yankee; Docket 50-271/ Inspection Report 84-11 Accident Monitoring TMI II.F.1 Installation for effluent monitoring of radioiodine insufficient to provide representative samples of effluent release; systems not verified or validated to provide such capability; installation of high range radiation monitoring channels in the drywell inadequate in that detectors were not adequately separated.
(Severity Level 4 violation).
D. C. Cook Unit 1 and 2 Docket 50-315 and 50-316/ Inspection Report 84-06 Containment Isolation Dependability II.E.4.2.7 Containment airborne monitors installed to isolate purge valves in the event of high radiation were tested inadequately but declared operable by the licensee.
(Severity Level 5 violation).
l
' D. C. Cook Unit l' and 2; Docket 50-315 and 50-316/ Inspection Report 85-11 Accident Monitoring TMI II.F.1 Licensee failed to maintain the noble gas effluent monitoring system for the main steam safety valves / power operated relief valve pathway operational in that two of the four loop monitors on each plant (Units 1 and 2) had been out of service at time of inspection.
(Severity Level 4 violation).
Fort Calhoun; Docket 50-285/ Inspection Report 87-29 TMI II.F.2 Instrumentation for Detection of Inadequate Core Cooling Licensee failed to issue and implement procedures for surveillance testing of the core exit thermocouple and heated junction thermocouple of the inadequate core cooling instrumentation system (Severity Level 4 violation).
Fort Calhoun; Docket 50-285/ Inspection Report 86-18 Safety Parameter Display System TMI I.D.2 Deviation from commitment relative to the safety parameter display system in that the parameters were not monitored for reactor coolant system average temperature, baronometer reading, and temperature of the containment.
(deviation).
Palo Verde, Unit 1 Docket 50-528/ Inspection Report 86-22 Post-Accident Sampling System TMI II.B.3 Program to ensure post-accident sampling capability under accident conditions not established at time of inspection (Severity Level 3 violation).
Sequoyah, Units 1 and 2; Docket 50-327 and 50-328/ Inspection Report 86-28 Reactor Coolant System Vents TMI II.B.1 Licensee failed to meet commitment to include procedures for use of the pressurizer PORVs as reactor coolant system high point vents in upgraded plant emergency instructions (deviation).
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house of Representatives INTERIOR AND INSULAN Masfjington, DC 20515
^"a s COMMIS$10N ON SECUR TV ANO
.coorEa4 Tion m U ore February 21, 1989 The Honorable Lando W.
Zech, Jr.
Chairman Nuclear Regulatory Commission 1717 H Street, NW Washington, DC 20555
Dear Chairman Zech:
I am writing to you concerning NUREG-0660, the Nuclear Regulatory Commission Action Plan Developed as a Result of the Three Mile Island-2 Accident.
As you know, this document contains a list of the plant modifications, procedural changes, and internal NRC improvements ordered following the TMI accident.
A later document, NUREG-0737, Clarification of TMI Action Plan Requirements, extended the time for compliance with certain Action Plan requirements and added several new requirements.
As a mettber of three House Subcommittees with oversight responsibilities for the NRC, I am interested in learning the i
status of the implementation of the improvements ordered under t
NUREG-0660 and NUREG-0737.
I would appreciate answers to the following questions:
1.
What is the implementation status of improvements ordered under the TMI Action Plan, any related Inspection and Enforcement Bulletins and Orders, and Commission Orders?
i 2.
Specifically, how many operating nuclear reactors and reactors under construction have not completed full implementation of all TMI Action Plan Items?
Please provide a list of these reactors, the items which remain to be fully implemented at each reactor, and the schedule for final implementation of each incomplete item.
1 1
3.
How many operating reactors and reactors under construction have received exemptions from TMI Action Plan requirements?
Please provide a list of those reactors anc. describe the nature of each exemption.
4.
Please describe all cases in which a utility reported implementation of an Action Plan but was subsequently found to be in violation or noncompliance with the requirement.
l S1O W YN f-
r i
4.'
l c.
The Honorable Lando W.
Zech, Jr.
l February 21, 1989 Page 2 It is my understanding that much of this information is readily retrievable from Commission computer records.
I ask that the Commission respond in writing within 10 working days or by March 6, 1989.
If for any reason the Commission is unable to fully respond by this deadline, please contact Andrew Cohen of my staff at 225-2836 so that arrangements can be made for the fullest possible response by March 6.
With best wishes, Sincerely, F-Edward J.
arkey Member of ongress EJM/awc
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