NRC-97-0010, Forwards Rev 8 to UFSAR for Fermi 2 & Rev 1 to 94-0033, Fermi 2 SE Summary Rept. Encl 1 Being Submitted to Fulfill Requirements of 10CFR50.54(a)(3)(ii)
| ML20148A266 | |
| Person / Time | |
|---|---|
| Site: | Fermi  |
| Issue date: | 05/02/1997 |
| From: | Gipson D DETROIT EDISON CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| Shared Package | |
| ML20148A270 | List: |
| References | |
| CON-NRC-97-0010, CON-NRC-97-10 NUDOCS 9705080166 | |
| Download: ML20148A266 (20) | |
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DIugts R. elpxn Sernor Vice President Nuoear Generation Detroit re-6 Edison
~400NorthDixieHighway
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013) 586-$249 May 2,1997 NRC-97-0010 U. S. Nuclear Ngulatory Commission Attn: Document Control Desk Washington, D. C. 20555
Reference:
Fermi 2 NRC Docket No. 50-341 NRC License No. NPF-43
Subject:
Submittal of Revision 8 to the Fermi 2 Updated Final Safety Analysis Report, Safety Evaluation Summary Report, Summary of Quality thRragge._Pggram_Ch gg.es and Commitment Management Reriort A
Pursuant to 10 CFR 50.71(e) and 10 CFR 50.59(b)(2), Detro! I!dison hereby submits Revision 8 to the Fermi 2 Updated Final Safety Analysis Repm t (UFSAR) and the Safety Evaluation Summary Report. Also, enclosed is a summary description of the changes to the Quality Assurance Program. This summary (Enclosure 1)is being submitted to fulfill the requirements of 10 CFR 50.54(a)(3)(ii).
In accordance with 10 CFR 50.71(e) the information provided in this submittal describes the plant configuration through November 5,1996 as a minirnum, and reflects changes made since the Revision 7 that were made under the provisions of 10 CFR 50.59.
';5 is the Safety Evaluation Summary Report containing a brief description gg of safety evaluations performed for changes to plant design, procedures, tests, gg experiments, temporary modifications, and the UFSAR.
SE Detroit Edison revised Fermi 2 administrative programs and procedures in 1996 to be
/kOb eu consistent with NEl's " Guideline for Managing NRC Commitments" Revision 2, dated December 19,1995. Consistent with these guidelines a Commitment Management Report (Enclosure 3) is included which provides a brief summary of g yg,
commitments that have been changed by Detroit Edison using these guidelines.
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USNRC NRC-97-0010 Page 2 If you have any questions, please contact Mr. Peter W. Smith at (313) 586-4097.
Sincerely, I
i Enclosures (3) cc: A. B. Beach (w/ Enclosures)
G. A. Harris (w/ Enclosures)
M. J. Jordan (w/ Enclosures)
A. J. Kugler (w/ Enclosures) 1 l
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i I, DOUGLAS R. GIPSON, do hereby affirm that the foregoing statements are based on facts and circumstances which are true and accurate to the best of my knowledge and belief.
6 1
DOUGLAS R. GIPSON Senior Vice President 1
On this
,M A A day of /
40d'
,1997 before me personally appeared Douglas R. Gipson, being first duly / worn and says that he executed the 1
foregoing as his free act and deed.
MLEw
'7W Notary Public ROSAUE A. ARMETTA NOTARY PUBUC-LONROECOUNTY,MI MYCOMMISS!0N EXPlRES10n1/90 j i
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DESCRIPTION OF CHANGES TO THE OUALITY ASSURANCE PROGRAM INCORPORATED IN REVISION 8 OF THE FERMI 2 UFSAR.
SECTION 17.2 1.
Section 17.2 has been revised to incorporate Fermi 2 site organization changes that were implemented since the last QA program changes. The i
organization changes are to enhance communications and performance and to i
better align the organization for the future. Each change was evaluated for QA program effectiveness. The basis for concluding that the revised i
program continues to satisfy the criteria of Appendix B and does not reduce Quality Assurance Program commitments can be summarized as: 1)no t
Quality Assurence functions were eliminated, and 2) the Quality Assurance l
3 organization contmued to report to the same level of management.
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l 2.
Numbering and minor editorial changes were made for consistency with '
UFSAR format and clarification. Details of the changes made are discussed below.
i 3.
Sections 17.2.1.1,17.2.1.4,17.2.1.5,17.2.2.1,17.2.2.6,17.2.18.3, and Figure 17.2 1 were revised to add the position of Nuclear Assessment Manager who I
reports to the Senior Vice President. The Director-Nuclear Quality Assurance, Director-Nuclear Training, and the Director-Nuclear Licensing i
report to the Nuclear Assessment Manager. Also, the title of head of turbine group was changed to Supervisor Turbine Group, in Section ".2.1.3.
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This change consolidates assessment type activities under one manager to improve the utilization of assessment resources. The reporting position of
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Nuclear Assessment Manager is separate from the line operating i
3 organization. The Director-Nuclear Quality Assurance continues to have access to the Senior Vice President-Nuclear Generation for reporting of quality problems. Therefore, this change does not reduce a commitment to Regulatory Guide 1.33 Rev. 2, and ANSI N18.7-1976; and does not cease to e
satisfy the criteria of 10 CFR 50, Appendix B.
4.
Sections 17.2.1.3,17.2.1.3.1 and Figure 17.2-1 were revised to restructure Assistant Vice President & Manager-Technical, and Technical Manager i
positions. This change is to simplify reporting relationships and add j
i flexibility in the organization. Additionally, sections 17.2.1.1,17.2.1.2, and Figure 17.2-1 were revised to eliminate Assistant Vice President and Manager-Operations position. The Plant Manager now reports directly to the l
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Enclosure I to NRC-97-0010 Page 2 Senior Vice President. The Plant Manager has retained all of the functions and reports to a higher level of management. Therefore, restructuring these positions does not reduce commitments previously accepted by the NRC, and continues to satisfy the criteria of the Quality Assurance Program per 10 CFR 50, Appendix B.
5.
Sections 17.2.1.3,17.2.1.5.17.2.3, and Figure 17.2-1 were revised to change the names of two engineering groups. " Plant Engineering" was changed to
" Plant Support Engineering", and " Technical Engineering" was changed to
" System Engineering" These changes were made to reflect their assigned tasks and functions more descriptively, and do not reduce any commitments or cease to satisfy the criteria of the Quality Assurance Program per 10 CFR 50, Appendix B.
J 6.
Section 17.2.1.3.2 was revised to remove risk analyses from the responsibilities description for the Director-Nuclear Licensing. Risk analysis is not required per 10 CFR 50, Appendix B, and is not part of the Quality Assurance Program. Moreover, this change does not reduce commitments previously accepted by the NRC.
7.
Sections 17.2.1.2.1,17.2.1.5.1,17.2.1.5.2 were revised, and Figure 17.2-2 was deleted to consolidate responsibilities of the Quality Assurance section supervisors (Supervisor-Inspection and Surveillance, and Supervisor-Audits) under the Director-Nuclear Quality Assurance. Addressing section supervisors responsibilities is not required per 10 CFR 50, Appendix B, and deleting them does not reduce any commitments.
Section 17.2.15 was also revised to clarify Nuclear Quality Assurance'r.
periodic analysis and reporting of quality data obtained from nonconformance documents as to when and how it is performed. The previous wording gave the interpretation that a quality trend analysis report is issued to management.
However, no regulatory requirement exists for issuing a trend analysis report, and the clarification does not reduce any commitments.
Therefore, these changes do not reduce any commitments or cease to satisfy the criteria of the Quality Assurance Program per 10 CFR 50, Appendix B.
8.
Sections 17.2.1.5, and 17.2.16, were revised to reflect organization changes eliminating safety engineering, Director-Safety Engineering, and relocating their functions to Nuclear Licensing, and Nuclear Quality Assurance. The Director, Nuclear Quality Assurance is responsible for administration of the plant corrective action program, including trending and tracking of corrective
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action program documents. The Director-Nuclear Licensing is responsible 4
for the Independent Safety Engineering Gn ap (ISEG) functions.
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This change does not affect the Independent Safety Engineering Group
)
(ISEG) functions. ISEG will continue to provide indepcindent verification of plant activities as required by Technical Specifications and the UFSAR.
j Similarly, these changes do not afiect the ability of the Nuclear Quality Assurance organization to perfotm its function as described in the Quality Assurance Program. Therefore, these changes do not reduce any commitments previously accepted by the NRC, or cease to satisfy the criteria j
of the Quality Assurance Program per 10 CFR 50, Appendix B.
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SAFETY EVALUATION
SUMMARY
REPORT i
I (This is in a separate 3 ring binder attached to NRC-97-0010 as Enclosure 2) 3
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Page1 Commitment Management Renort In 1996 Fermi 2 administrative programs and procedures were revised to be consistent with NEI's " Guidelines for Managing NRC Commitments," Revision 2, dated December 19,1995. Fermi 2 began using the basic criteria included in the NEI process during the NEI-NRC Pilot Program for the Guidelines in 1995. These Guidelines discuss the need for a report to be submitted either annually or along with the FSAR updates required by 10 CFR 50.71(e). This Enclosure constitutes the initial Fermi 2 Commitment Management Report.
l The NEI process also prc mies for notifying the NRC of commitment changes when certain criteria are met. These criteria have been incorporated in Fermi 2 procedures for managing commitments. For example, a revised schedule for implementing commitments made in response to a Generic Letter would require specific and timely NRC notification. The purpose of this report is to provide a record of those commitment changes that did not require a notification at the time of the change.
I The report consists of three tables as described below. Each table includes a brief statement of the commitment subject and origin. The changes being reported in these tables do not in any way affect or change commitments or descriptions included in the UFSAR. Furthermore, in many cases the only " change" being made is that the activity will no longer be tracked by Fermi 2 as a regulatory commitment.
These two points are very imponant and are discussed further in the following paragraphs.
This report involves only changes that have been made in the Fermi 2 commitment management program (referred to as the Regulatory Action Commitment and Tracking System or RACTS). Some commitments identified in this report as being revised by this process may also be redundant to similar statements or licensing basis
" commitments" included in the Fermi 2 UFSAR. Including a change in this report does not, however, infer that the commitment or statement in the UFSAR has been revised. Application of the NEI Guidelines ensure that changes to such commitments in the UFSAR, including the Quality Assurance Program, would continue to be made and reported using the appropriate regulatory process (i.e. 50.59 or 50.54.)
Many of the " changes" being reported do not actually involve a change in the underlying activity or item that was the subject of the original commitment. The activity itself may be continued; however, Detroit Edison will no longer track the individual item as a regulatory commitment. This action, in effect, " withdraws" or eliminates the original commitment. This practice is consistent with the NEI Guidelines that recognize that licensees need the flexibility to change or eliminaf:
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Commitment changes being reported are included in the following three tables:
TABLE 1: Commitments that were deleted from the Fermi 2 commitment tracking program because they are included in an ongoing program or procedure that is subject to a revision review process. Table 1 may also include commitments that were deleted from the tracking program because ticy were redundant to commitments in the UFSAR.
TABLE 2: Commitments that were deleted from the Fermi 2 commitment tracking program for reasons other than those listed for Table 1.
TABLE 3: Commitments that were not deleted, but were revised in the commitment tracking program. A statement of the original commitment and reference is given along with a brief description of the revision.
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i REGULATORY COMMITMENTS INCLUDED IN THE UFSAR, PROCEDURES OR PROGRAMS AND DELETED FROM RACTS COMMITMENT TRACKING PROGRAM 1
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(
L DECO REF LcTI ER ORIGINAL DESCRIPTION RACTS DOCUMENT COMMIT NO.
DATE/
YEAR 2245 I MFR-96-0019 1982 PROCEDURE LIMITATION AND SPECIFICATIONS FOR MOVEMEN T OF RPV llEAD.
2559 EF2-66117 GL 83-28 1983 DECO IIAS A SYSTEM FOR CORRELAllNG SURVEILLANCE PROCEDURES TO REQUIREMENTS 2566 EF2-66117 1983 DEVELOP PROGRAM CONTROLS TO ENSURE ALL SERVICE INFO LETI ERS (SILS) ARE
]
RECEIVED 2641 EF2-67208 1984 REQUIREMENI'S FOR INSPECllON AND CLOSURE OF AN OPEN SYSTEM 2660 EF2-66729 1984 CORRESPONDENCE 10 Tile NRC TO I E SIGNED BY TIIE SR VICE PRESIDEN I NUC UEN I
2686 El'2-67127 INSP 8328 1984 PROVIDE INST RUCTIONS FOR MAINTAINING CLEANLINESS OF QA I PIPING.
2786 INSPRT 8320 1984 PROCEDURE TO IMPROVE CON 1 ROL OVER LIFTED LEADS AND PROVIDE FOR l
IDENTIFICATION 2788 QA84-0081 1984 IMPROVE PROCEDUPAL REQUIREMENTS FOR llOUSEKEEPING INSPEC110NS l
2799 EFI-66487 INSP 8320 1984 DEVELOP PROGRAM FOR CONI ROL OF ITEMS WITil LIMITED SilELF LIFE 2800 EF2-66487 1983 INCORPORAT E SilELF LIFE DATA GATilERED FROM VENDORS INTO ONGOING PROGRAM 2820 EF2-66487 1984 IMPROVEMENTS TO Tile SilELF LIFE CONTROL PROGRAM 2826 QA84-0081 1984 PROCEDURE MODIFIED TO INDICATE TilAT SCRAP CONTAINERS SilOULD BE CLEARLY LABELED l
2850 EF2-67811 1984 CORRECT DISCREPANCY IN STORAGE /IIANDLING OF SAFETY RELATED MATERIALS 2971 1 MFR-96-0019 1982 PROCEDURES WILL BE WRITIEN PRIOR TO IIANDLING LOADS AND WILL INCLUDE CERTAIN I
REQUIREMENTS.
2972 TMFR-96-0019 1982 PROCEDURES WILL REFERENCE SPECIFIC INST RUCTIONS IN RIGGING MANUAL FOR SELECTION AND ATTACllMENT OF SLINGS TO SPECIFIED LOADS.
2992 1 MFR-96-0019 1982 PROCEDURE SilALL SPECIFY LOAD llEIGitT LIMITATIONS OF Tile VESSEL llEAD j
INSULATION ALONG DESIGNATED PATil.
l 2993 1 MFR-96-0019 1982 PROCEDURE SilALL SPECIFY 5FT 4 INCil llEIGilT LIMITATION FOR ANY LIFI OF STORAGE POOL SLOT PLUGS ALONG DESIGNATED TRAVEL PATilS.
2994 TMFR-96-0019 1982 PROCEDURE WILL SPECIFY TilAT FUEL POOL SLOT PLUGS ARE NOT TO BE LIFTED BEYOND j
12FT ABOVE FLOOR DURING REFUELING.
[
3372 EF2-72770 INSP 84-15 1984 CONSIDERATION OF PLANT CONDITIONS IN FORMULATION OF EP PRol'ECllVE ACTION RECOMMENDATIONS.
3436 EF2-68328 1984 PERFORMANCE OF TIIE RilR IIEAT EXCilANGERS ARE MONITORED TilROUGilOUT PLANT OPERATION.
~
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Table 1 Regulatory Commitments included in the UFSAR, Procedures or Programs l
and Deleted From RACTS Commitment Tracking Program DECO REF LEriER ORIGfdAL DESCRIPTION RACTS DOCUMENT COlVMIT NO.
DATE/
YEAR 3485 EF2-69282 1985 PROCUREMENT REQUIREMElffS I OR NEW IIOISTS TO CONFORM WI fil ANSI B30.16 I
3486 EF2-67211 1985 PROCUREMENT REQUIREMENTS FOR NEW llOISTS TO CONFORM Willi NURLG-0544 GUIDELINES 3563 EF269709 INSP 84-17 1984 IDENTIFICATION OF PROCEDURES AND SPECIFICATIONS FOR APPLICATION OF RAYCilEM IIEAT SilRINK BEING IDENTIFIED L
3564 EF269709 INSP 84-17 1984 PROCEDURES WILL REQUIRElilAT CRAFTSMEN RECEIVE APPROPRIATE RAYCilEM llEAT SilRINK APPLICATION TRAINING 3568 EF2-69709 1984 VERIFICATION OF PROPER FUSE INSTALLATION WilEN CLEARING TAGS DR PERFORMING LINE-UPS 356")
EF2-69709 1984 INDEPENDENT VEOFICATION OF PROPER FUSE INSTALLATION 3612 EF2-69714 1984 ITEMS WITil SilELF ilFE REQUIREMENTS TO BE CONTROLLED BY Tile SilLLF LIFE PROGRAM 3820 EF2-70390 1988 IMPROVEMENTS TO PLANT EQUIPMENT LABELING PROGRAM 3884 NE 85-0365 1985 COMBUSTIBLES WILL BE CONTROLLED BY ADMINISTitAllVF PROCEDURES 3942 EF2-70388 1985 PROVIDE GUIDELINES FOR INSPECTORS IN PROCEDURES 4124 EF2-70041 1984 QA TO REVIEW SURVEILLANCE FINDINGS FOR ADVERSE TRENisS l
4172 EF2-70221 1984 PROCEDURE 21.000.01,"SilllT OPERATIONS AND CONTROL ROOM" REVISED ~1O CLARIFY WilEN ABNORMAL LINEUP SilEET(ALS)IS REQUIRED.
4186 EF2-69714 1984 MAINT INSTRUCilON ON SilELF LIFE ADDRESSES NEW STOCK, MATERIAL IN STOCK AND ORDERED 4187 EF2-69714 1984 MAINIENANCE INSTRUCTION INCORPORAI ES STANDARDS FOR ESTABLISillNG SilELF LIFE OF MATERIALS 4188 EF2-69714 1984 REVISED WAREllOUSE PROCEDURE IN RESPONSE TO NON COMPLIANCE I
4237 EF2-69709 1984 PROCEDURAL CONTROLS PREVENT LOSS OF CONFIGURATION CONTROL 4278 EF2-70032 1984 CONSTRULTION QA REQUIREMENT FOR USE OF A TRAVELLER SYSTEM TO CONTROL WORK.
L 4354 INSPRT 8448-02 1984 ENSURE SOURCE INSPECTION PROCEDURES ARE REVIEWED AND APPROVED BY QA I
J490 NE 85-0339 1985 CLARIFICATION ON Tile NON-APPLICABILil'Y OF PROCEDURE PMI-02 FOR EQ 4935 EF2-72247 1984 RPS, SAFE SilUTDOWN, AND ESF PANELS AND RACKS WILL BE LABELED t
4936 EF2-72247 1984 PROGRAM DEVELOPED 1O ENSURE TIIAT ALT MAJOR EQUIPMENT IS LAllELED 5786 NP 85-0577 LER 85-012 1985 INCREASED ASSURANCE TIIAT OPERATORS ARE INFORMED OF PROCEDURE CilANGES L
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DATE/
YEAR 5813 EF2-672 t l 1984 PROCUREMENT REQUIREMENTS FOR NEW ilOISTS TO CONFORM WITil NUREG-0544 GUIDELINES 6024 INSPRT 1985 PROVIDE A MEANS FOR OBI AINING FEEDilACK ON PROBLEMS Willi MAINTENANCE RC-LG 85-014 PROCEDURES 6027 INSPRT 8531 1985 PwOVIDE GUIDANCE ON Tile CONTENT AND FORMAT OF WORK PACKAGES RC-LG 85-018 6398 RC-LG-85-0015 1985 REVISE PROCEDURES TO FORMALLY REQUIRE A SYSTEM TO DE ENTERED IN TIIE OUT-OF-SPECIFICATION LOG WilEN A SYSTEM OUTAGE IS DECLARED.
6399 VP-85-0229 INSPRT 8541 1985 REVISE RERP TRAINING TO PLACE iiMPilASIS ON USE OF METEOROLOGICAL DATA IN PROCEDURE EP-545 6631 FSAR 1985 DEVELOP AND MAINTAIN Q LIST 7059 EF2-60134 1982 ESTAllLISilED TRAVEL PA~1IIS WILL BE INCLUDED IN MAIN'lENANCE PROCEDURFS 7073 EF2-61200 1984 CORRECT ERROR IN PREOP 1 EST PROCEDURE FOR RELIEF VALVE SET POINT 7192 EF2-67127 INSPRT 83-28 1984 FSTABLISil PROCEDURES ON CLEANLINESS CONTROL OF TORUS AND PIPING 7193 EF2-67127 INSP 83-28 1984 CONTROL OF MATERIAL GOING IN AND OUT OF Tit.3 TORUS WilEN 11 IS OPEN 7211 QA 84-0081 INSP 83-20 1984 IDENTIFICATION AND CONTROL OF MATERIAL UN rIL llOLD TAGS ARE CLEARED 7212 Q A 84-0081 INSP 83-20 1984 CORRECI SPECIFIC INSTANCES OF TAGGING PROllLEMS 7213 QA 84-0081 1984 CORRECT PROBLEM Willt EXCESS TAGS ON PALLETS 7250 EF2-68206 1984 TO PERMIT RAPID STARTUP OF Tile IIPCI SYSTEM, Tile LINE IS KEPl 110T BY REQUIRING BOTil TIIE INBOARD ISOLATION VALVE AND Tile (I-INCll) BYPASS VALVE AROUND TIIE OUTBOARD ISOLATION VALVE TO BE KEPT OPEN.
7562 INSPRT 86-011 1986 SPECIFIC PROCEDURE REQUIREMENTS TO TRACK AND EVALUATE TIMELINESS OF CORRECTIVE ACTIONS.
7593 VP 86-0054 1986 REVISE Tile CORRECTIVE ACTION PROGRAM TO PROVIDE MORE EFFECTIVE SUPPORT 7597 VP86-0054 1986 IMPROVEMENTS TO Tile DESIGN CilANGE PROCESS 7637 LER 86-02 1986 CONT ROL WORK ON INOPERABLE SYSTEMS TilROUGil USE OF TIIE ENG OPER CONSTRAINT 7731 DER 86-012 1986 NRC LICENSE AMENDMENTS WILL BE REVIEWED IN DETAll WilEN RECEIVED 7752 INSPRT 8627
'986 SEMI-ANNUAL CilEM TECil1 RAINING WITil SPIKED SAMPLES 7777 GL 86-15 1986 ENSURE EQ ISSUES ARE ADDRESSED BY CORRECTIVE ACrlON PROGRAM.
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DATE/
YEAR 7848 LER 85-06 1986 Tile PROCEDURE COVERING WORK ORDERS WAS REVISED TO PROVIDE IMPROVED CONTROL AND DOCUMENTATION OF POST-MAINTENANCE TESTING.
7853 11R 85-033-01 1986 GENERAL PROCEDURE 22.000.11,"S!!UI'DOWN I ROM RATED POWER IO IlOT STANDilY (MSIV'S CLOSED")" WAS REVISED TO CONTROL PRESSURE DEMAND WITIIIN CONTROLLER BAND.
7862 LER 85-06 1986 SYSTEM PROCEDURES FOR SYSlEMS IIA vlNG PRIMARY CONTAINMENT PENETRATIONS WERE REVISED TO ENSURE TIIAT TEST, VENT AND DRAIN VALVES WERE SPECIFIED M BE IN T!!E CLOSED POSITION WITil TIIE LINE CAPPED.
7925 NRC-87-0028 (NOV l87 PROCEDURES WERE REVISED TO IMPROVE CONTROLS ON EQUIPMENT STATUS AND PLANT RESPONSE)
CONFIGURATION.
7937 VP 87-0001 1987 ESTAllLISil llEAVY LOAD 1 RAVEL PA7 '.lS PRIOR TO !!ANDLING AITER INITIAL CRIllCALil Y 7944 TMFR-96-0019 1987 PROCEDURES WILL INCLUDE Tile REQUIREMENTS OF NUREG-0612 TO CONTROL FU I'URE IIEAVY LOADS TO BE IIANDLED OVER OR NEAR SPENT FUEL OR SAFE SIIUTDOWN EQUIPMENT.
7957 VP 87-0001 1987 RETENTION OF TRAINING RECORDS REGARDING ilEAVY LOADS FOR PERSONNEL 7972 TMER-96-0019 1987 S IORAGE POOL SLOT PLUGS WILL NOT llE IIANDLED IN CLOSED PROXIMITY TO FUEL POOL OR REACTOR VESSEL 7973
'I Mi R-96-0019 1987 RESTRICT!ONS ON llANDLING REACTOR SillELD Pl.UGS, DRYWELL llEAD. STUD TENSIONER.
7980 TMFR 96-0019 1987 RESTRICIlONS ON llANDLING RPV IIEAD MORE TilAN 4 FEEL ABOVE FLOOR.
7983 TMFR-96-0019 1987 PROCEDURE SilALL SPECIFY T0"IIEIGilT LIMITATION FOR ANY LIFT OF THE STORAGE POOL SLOT PLUGS ALONG DESIGNATED TRAVEL PATilS.
7984 TMER-96-0019 1987 PROCEDURE SilALL SPECIFY DESIGNATED 1 RAVEL PATil FOR FUEL POOL SLOT PLUGS.
7985 1 MER-96-0019 1987 PROCEDURE SilALL SPECIFY A MAX. l.IMIT OF 12 !T. FOR LOAD TO BE LIFTED ABOVE Fl.OOR (STUD TENSIONER).
7986 TMFR-96-0019 1987 Tile SIEAM DRYER AND STEAM SEPARA10R ARE ONLY MOVED DURING COLD SilUTDOWN.
8022 LER 87-028 1987 RESTRIC1 ED USE OF TEMPORARY PROCEDURE CilANGES TO OPERATIONS PROCEDURES 8027 VP 85-0198 1985 MODIFY WORK ORDER SYSTEM TO CLEARLY SPECIFY POST MAINT TESTING REQUIREMENTS 8033 VP 85-0198 1985 SPECIFIED NSS ROLE IN WORK CON 1 ROL ON SilllT
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DATE/
I YEAR 8037 LER 87-27 1987 SillFT STAFFING TO BE AUGMENTED AS NECESSARY 1O ENSURE PERSONNEL CAN PERFORM DUTIES 8039 LER 87-27 1987 PROVIDE ADDITIONAL GUIDANCE TO SillFT PERSONNEL ON RESPONSIBil.IllES 8045 RG-LG85-021 1985 PROCEDURE IMPROVEMEN FS FOR POS11NG OF CONFIGURATION CllANGES ON CONI ROL RM DWGS 87181 INSPRT 86624 1987 IMPROVE CORRECIIVE ACTION PROGRAM Willi REGARD TO REPIsilTIVE EQUIPMiiNF r
PROBLEMS 87211 LER 87-018 (NRC-87-0086) 1987 INCLUDE IN Tile APPROPRI Al E PROCEDURES WillCl] ISOLAllONS OF Tile RWCU SYSI EM ARE EXPECTED.
87355 IEli 87-01 1987 EROSION / CORROSION INSPECllONS TO BE PERFORMED IN FUTURE 87431 INSPRT 87026 1987 ESTABLISil SURVEILLANCE PROCEDURE 1 RAINING IN INPO ACCRED 1 RAINING PROGRAMS 87432 INSPRT 87026 1987 INDIVIDUALS PERFORMING SURVEILLANCE PROCEDURES WILL llE TRAINED ON CIIANGES 87434 NRC 87-0l76 NOV87-026 1987 INCREASE. ATTENTION TO Tile TECllNICAL REVIEW OF TECII SPEC SURVEILLANCE REQ 87556 NRC 87-0258 1987 COMPLETION OF REVISIONS TO TIIE APPROVED / CONTROLLED MATERIALS LIST 88229 CAL-Rill-88-009 1988 PROCEDURES WILL HE REVISED TO REQUIRE FREQUENT MONITORING OF SilUTDOWN COOLING FLOW.
88252 INSPRT 8721 1987 ENilANCEMENTS TO SAFETY EVALUAllON PROGRAM TO ENSURE COMPLIANCE WITil 50.59 88329 NRC 88-0167 NOV 8806-3 1988 VAllDATE Tile SPRS DATA IIASE FOR ALL SAFETY RELA'l ED AND CLASS IM PARTS 88384 INSPRI 88-012 1988 SEVEN EECW PROCEDURES IIAVE HEEN REVISED TO ADD NOl E/CAUllON CONCERNING Tile ACTUATION AND REPORTABILITY OF AN EECW ACTUATION.
i 88399 NRC 88-147 NOV 8818-03 1988 UPGRADE AND REVIEW HOP INSTRUMEN FATION MAINTENANCE lilSTORY 88425 NRC-88-0198 1988 REVISE PROCEDURES 10 INCLUDE INSTRUMEN T LINEUPS AFTER REFUELING OU I AGES.
88450 NRC-88-Ol%
1988 SYSTEM OPERATING PROCEDURES FOR RETURNING RWCU TO SERVICE IIAVE HEEN CilANGED WITil RESPECT TO FILL AND VENT REQUIREMENTS AND SAMPLE LINE ISOLATION.
88529 lek 88-033 1988 PROCEDURES IIAVE HEEN REVISED TO RE-ESTABLISII RWCU PUMP FLOW AS SOON AS POSSIBLE AITER PUMP TRIP.
88565 INSPRT 8821 1988 ESTABLISil LOCKED VALVE GUIDELINES / PROGRAM 88591 NRC 89-0012 NOV 8805-02 1989 CONTRACTORS TO II.WE APPROPRIATE QUALIFICATIONS FOR PERFORMING SAFETY i
RELATED ACTIVITIFS L
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DATE/
YEAR l
88594 LER 88-036 1988 REVISED PROCEDURE 23.425.01 TO ADDRESS PERFORMANCE PROllLEM.
88665 NRC 88-288 1988 DEVELOP A PROCEDURE TO PROVIDE GUIDANCE FOR MOV IROUBLESilOOrtNG 88666 NRC 88-288 1988 UPGRADES TO MOV MAINTENANCE PROCEDURES; 88667 NRC 88-0288 1988 UPGRADE TO PROCEDURES FOR LONG TERM MOV PROGRAM 88693 LER 88-036 1988 REVISE PROCEDURE 23.425.01 TO CLARIFY WilEN ATI ACilMENT 10 (ELECFRICAL LINEUP FOR CONTAINMENT ENTRY) MUST BE DONE.
89009 NOV 88-30-IB 1988 TRAINING AND DOCUMENTATION ENilANCEMENTS FOR VERBAL APPROVAL OF PARTS SUBSTITUTIONS 89010 INSPRI 88-030 1989 PROCEDURE IMPROVEMENTS RELA 1 ED TO FAILURE TO RE-ENERGlZE CONTAINMEN I LIGitTING.
89011 INSPRI 88-030 1989 PROCEDURE IMPROVEMENTS RELATED TO FAILURE TO RE-ENERGIZE CONTAINMENT LIGIITING 89043 NRC 89-0004 DEI RPI 1989 ORGANIZATIONAL IMPROVEMENTS IN ENGINEERING FUAC1 TONS RELNI ED TO DESIGN AC11VITIES l
89069 NRC 89-0015 1989 IMPROVE INTERNAL INTERFACES BETWEEN ENGINEERING, MAINTENANCE AND TECII GROUPS 89070 NRC 890004 1989 A METilOD 10 EVALUATE SIMULA10R INSTRUCTORS WILL llE DEVELOPED 89071 NRC 89-0004 1989 MONITOR PERFORMANCE OF TRAINING INSTRUCTORS.
i 89094 INSPRT 8917 1989 PROCEDURE CLARIFICAllONS MADE TO ENSURE COMPLIANCE WITil 50.59 89095 INSP 89-13 1989 CONTROLS ON CLASSROOM TRAINING MATERIALS 891II INSP 88-037 1988 PROGRAM ENilANCEMENTS TO RESOLVE CONCERNS ABOUT SPARE PARTS AVAILAlllLil Y 89113 INSP 89-013 1909 PROGRAM ENilANCEMENTS TO RESOLVE CONCERNS ABOUT ADEQUACY OF POST MAINTENANCE TESTING 89173 GL 88-14 1989 PM ACTIVil~lES ON AIR SUPPLY COMPONENTS
~89295 INFO NO TE 89-47 1989 PROCEDURE CONTROLS TO PREVENT POTENTIAL PROBLEMS WITil WORN OR DISTORTED IIOSE CLAMPS ON SELF-CONTAINED BREATIIING APPARATUS.
89338 REGULAIlON NA EPA RULE ON EFFLUENT REPORTING 89346 REG GUIDE I.114 1989 FERMI PROCEDURES CONSISTENT WITil REGULATORY GUIDE I.114." GUIDANCE TO OPERATORS AT TIIE CONTROLS AND TO SENIOR OPER'. TORS IN TIIE CONTROL ROOM OF A NUCLEAR POWER UNIT."
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! to NRC-97-0010 Page 10 Table 1 l
Regulatory Commitments Included in the UFSAR, Procedures or Programs and Deleted From RACTS Commitment Tracking Program DECO REF LETIER ORIGINAL DESCRIPIION RACTS DOCUMENT COMMIT NO.
DATE/
[
YEAR 89365 INSPRT 89-011 1989 PROCEDURE NPP-35.000.240" BOLTING AND TORQUING", WAS REVISED TO SPECIFY WilEN TORQUE VALVES ARE TO BE PRESCRIBED.
89370 INSPRT 89-01 I-07 1989 IMPLEMENT ACTIONS TO STRENGTilEN Tile LUBR! CATION PROGRAM 89388 INSPRT 89-016 1989 IMPROVE ACCESSIBILITY OF DESIGN BASIS DOCUMENTATION 89436 NRC-88-0187 1988 MOV GREASE CONDITION TO BE INCLUDED IN PM ACllVITIES 90055 INSPRT 89-035 1990 REVISE RERP PROCEDURES TO DOCUMENT ANNUAL VERIFICATION OF COMMUNICATIONS 90084 INSPRT 8930 1990 DEVELOP AN INSTRUCllON TO PROVIDE GUIDANCE ON llOW TO PERFORM QA SURVEILLANCES 90132 INSPRT 8901 NRC 90-025 1989 i% VISE PROCEDURES 1O IMPROVE GUIDANCE ON USE OF TEMPORARY MODIFICATION 11U'EDURE.
90170 NRC 90-043 NOV 89-24-03 1990 CLARIFY DEFINITION 01-CONDillON ADVERSE TO QUALITY IN PROCEDURES 90175 INSPRT 89-034 1990 PROCEDURE CllANGES MADE 10 IMPROVE CONTROL OF TAGGING AND LCO 1 RACKING.
90183 INSPRT 89-034 1990 CORRECFIONS MADE TO SYSTEM OPERAl eNG PROCEDURE 23A09,"TilERMAL RECOMBINER SYSTEM", REV 21.
90252 INSP RPI'90-005 1990 TAKE ACTIONS TO ENSURE ACCURATE INFO IS PROVIDED TO NRC 90346 NRC-90-0122 1990 REVISION TO MAINI ENANCE PROCEDURES FOR Tile 1 URBINE BYPASS VALVES, MAIN STEAM STOP AND TilROTTLE VALVES, AND Tile LOW PRESSURE TURBINE STOP AND INTERCEPT VALVES.
90353 NRC-90-01 I I 1990 CONCERNS WITil Tile USE OF llPCl/RCIC FOR PRESStJRE AND LEVEL CONTROL RESOLVED
+
BY PROCEDURE CilANGES.
[
90385 NRC-90-0130 1990 CONIROLS WILL BE ESTABLISilED TO PROPERLY MATCil REFUELING TOOLS Wil'Il A IIOIST'S UPTRAVEL STOP SETTING TO ENSURE TIIE TECll SPEC UPTRAVEL LIMIT HS CORRECTLY ESTABLISliLD.
90481 NRC 90-0168 NOV 90-13-3 1990 ABNORMAL LINEUP SilEET PROGRAM REVIEW AND PROCEDURE IMPROVEMENIE 91089 INSP 91-04 NCV 9104-02 1991 PROCEDURE IMPROVEMENTS 'IU SPECIFY CORRECT llOUSEKEEPING REQUIRED l'OR MAINTENANCE 91312 GEN LIR 91-06 1991 TIIE LOCAL BATIERY GROUND DETECTOR IS MONilORED ONCE A DAY BY AN Ol"ERAl'OR PERFORMING Tile DAILY ROUNDS.
91314 N RC-91-0128 1998 OPERATOR RECORDS Tile DC BUS VOLTAGE DURING TIIF-DAILY ROUNDS AND ACIION IS TAKEN FOR VOLTAGE ABOVE 138 VDC OR 1)ELOW 132.5 VDC.
i i
i to NRC-97-0010 Page1I Table 1 Regulatory Commitments Included in the UFSAR, Procedures or Pmgrams and Deleted From RACTS Commitment Tracking Program DECO REF LETIER ORIGINAL DESCRIPTION RACIS DOCUMENT COMMIT NO.
DATE/
YEAR 91316 NRC 91-0128 UL 91-06 1991 BYPASSED /INOP CIRCUIT BREAKERS INDICA 1 ED VIA ADMIN CONI ROLS 91347 NRC 91-0134 1991 IMPROVE TECil SPEC CIIANGE IMI LEMENTATION PROCESS 92123 INFO NorlCE 85-51 1992 PROCEDURAL CONTROLS TO PRECLUDE INADVERTENT LOSS OR IMPROPER ACIUAIlON OF SAFETY-RELATED EQUIPMENT.
93192 NRC-93-0030 1993 ASSIGN ENGINEERS 10 Tile MODIFICATIONS ORGANIZATION FOR IMPLEMENI ATION OF MAJOR DESIGN CIIANGES DURING REFUEL OUTAGES.
93216 NRC-93-0059 1993 CilANGES WILL BE MADE 10 Tile IIPCI SYSTEM OPERATING PROCEDI 'RE 23.2021 O ELIMINATE TIIE IIPCI SYSTEM DISCIIARGE PIPING WATER llAMMER.
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, to NRC-97-0010 Page 12
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Table 2 Commitments Deleted From RACTS Commitment Tracking Program For Other Reasons DECO REF LETTER ORIGINAL DESCRIPTION REASON FOR DELETING s
RACTS DOCUMENT COMMIT COMMITMENT NO.
DATF1-YEAR 91209 LER 91-15 1991 POST MAINTENANCE CllECK OF MAIN TRANSFORMER FOR COMMITMENT IS NO LONGER l
POTEN11AL INTERFERENCE APPLICABLE DUE TO TRANSFORMER l
DESIGN CllANGE 3599 EF2-72035 1984 DECO QA ORGANIZATION WILL MONITOR NUS RADWASTE NUS PROGRAM IS NO LONGER USED.
PROGRAM IMPLEMENTATION 91011 NRC 91-0001 1991 FFD TESTING PROCEDURES TO PREVENT RECURRENCE OF TESTING LAB NO LONGER USED LAB TESTING PROBLEM 90017 LER 89-32 1989 PROCEDURAL STEP CIIANGED TO PRECLUDE ESF TESTING REQUIREMENT WAS ACTUATIONS ELIMINATED i
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, to NRC-97-0010 Page 13 Table 3 Revised Commitments DECO REF LEITER ORIGINAL DliSCRIPilON REVISED COMMI FMENT RACTS DOCUMENT COMMIT NO.
DATE/ YEAR 43 %
INSP RPT 84-20-05 1984 CORRECT llED RELAl ED TO IDENTIFICAllON OF COMMilMENT REVISED TO ALLOW
[
NORMAL OPERATING RANGE ON CR METERS Tile USE OF DIGITAL RECORDERS WIIICil DO NOT llAVE TIIIS CAPABILITY 4308 INSPRPF 84-20-08 1984 CORRECTllED RELATED TO IDENTIFICATION OF COMMITMENT REVISED TO ALLOW i
NORMAL OPERATING RANGE ON CR RECORDERS TIIE USE OF DIGITAL RECORDERS WillCII DO NOT IIAVE Tills t
CAPABILITY 8050 NRC-87-016; 1987 MAINTAIN RX BETWEEN 140 AND 175 DEGREES CIIANGED TEMPERATURE CONTROL i
WillLE IN SIIUTDOWN COOLING BAND TO 105-175 DEGREES 87292 NRC-87-0167 1987 MAINTAIN RX llETWEEN 140 AND 175 DEGREES CIIANGED TEMPERATURE CONTROL WillLE IN SillTIT)OWN COOLING BAND TO 105-175 DEGREES
[
90125 NRC 90-0052 INSPRT 8917 1989 FORMAL PROCESS WITil APPROPRIATE MGMT REVISED TO MAKE MORE GENERAL APPROVALS FOR EXTENDING DER DUE DATES WITil REGARD TO POSITION TITLES AND REVIEW CRITER8 A 92237 INSPRT 92-011 1992 SCAITOLDING INSTALLATIONS TO IIE INSPECTED REVISED TO ALLOW INSPECllON BY f
BY AN INDIVIDUAL WITil SRO LICENSE INDIVIDUAL WITil RO LICENSE
[
93191 LER 93-008 1993 JOINT WALKDOWN OF COMPLETED MODS BY CIIANGED TO ALLOW ALTERNNIE OPS AND ENGINEERING USING A TURNOVER MEANS OF INSPECTION WilEN CilECKLIST MODIFICATION IS NOT VISIDLE TO VERIFIERS 90127 NRC 90-0025 1990 SAFETY EVALUATION (50.59) REQUALIFICATION REVISED COMMil MENT TO BE LESS l
REQUIREMENTS ESTABLISilED PRESCRIPTIVE REGARDING Tile TYPE OF REQUAL TRAINING TilAT i'
WILL BE PROVIDED.
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