ML18058B201

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Forwards Safety Related Piping Reverification Project Periodic Status Rept for Oct 1992,per 920122 Meeting W/Nrc & .Next Update Will Be Submitted by Sept 1993,since Next Eight Month Cycle Would Coincide W/End of 1993 Outage
ML18058B201
Person / Time
Site: Palisades 
Issue date: 10/30/1992
From: Donnelly P
CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.)
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NUDOCS 9211120068
Download: ML18058B201 (18)


Text

--* -.

l'OWERINli MICHlliAN'S l'ROliRESS Palisades Nuclear Plant 27780 Blue Star Memorial Highway, Covert, Ml 49043 October 30, 1992 Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 DOCKET 50-255 - LICENSE DPR PALISADES PLANT - SAFETY RELATED PIPING REVERIFICATION PROJECT - PERIODIC STATUS OCTOBER 1992.

A meeting was held at NRC Headquarters on January 22, 1992 to discuss the Safety Related Piping Reverification Project (SRPRP).

As was discussed in that meeting and documented in your February 13, 1992 letter, we committed to submit a status report for the SRPRP approximately every eight months.

Enclosed is the first of those periodic reports.

Because the next eight month cycle would coincide with the end of our 1993 refueling outage and to allow us to incorporate the results of the work completed during the outage, our next update will be submitted by September

!~ ~---#

Patrick M Don~;~~

Plant Safety and Licensing Director CC: Administrator, Region III, USNRC Resident Inspector - Palisades Enclosure 9211120068 921030 PDR ADOCK 05000255 R

PDR A CMS ENERGY COMPANY

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ENCLOSURE 1 Consumers Power Company Palisades Plant Docket 50-255 SAFETY RELATED PIPING REVERIFICATION PROJECT Periodic Status October 1992 October 30, 1992 2 Pages

SAFETY RELATED PIPING REVERIFICATION PROJECT PERIODIC STATUS - OCTOBER 1992 The Safety-Related Piping Reverification Program (SRPRP) was initiated to reverify the seismic design adequacy of large bore safety-related piping systems.

The program is divided into two phases.

1 Phase I consisted of 18 piping stress packages and approximately 300 pipe supports which include portions of systems inside and outside of containment.

These systems were selected for the Phase I scope, to assure that the Primary Coolant System (PCS) inventory is maintained, that the PCS could be borated to shutdown concentrations, and that redundancy exists to remove decay heat following shutdown.

Walkdowns of those portions of systems outside the containment building were completed in early 1990.

The walkdowns of those systems inside containment were completed during the 1990 maintenance outage and the 1990 steam generator replacement outage.

Reverification of eight piping stress packages and their associated pipe supports was completed in 1990.

The remaining ten piping stress packages in Phase I were reanalyzed during 1991 and any requisite hanger modifications were made during the 1992 refueling outage. Analyses have shown that, to date, no system has exceeded the interim operability criteria which has been approved by the NRC staff (CPCo letter dated November 22, 1989).

A listing of all support work completed as a result of the SRPRP is included as Attachment C.

The listing shows Phase I work associated with 83 supports.

Seventeen of the items (adjusting shim gaps and repairs to the damaged SI bottle discharge piping) are not considered as modifications required to correct design deficiencies.

Phase II of the SRPRP consists of field walkdowns, field-verified piping and support drawing updates, pipe stress and support re-qualification, and updating of pipe stress package documentation for the remaining safety-related piping systems.

The scope also includes the design and implementation of any modifications required to bring piping and supports to within FSAR compliance.

The analytical work for Phase II is in progress and is estimated to be completed by February 1993.

During Phase I of the project, certain piping design criteria were changed.

These changes were agreed to by Consumers Power Company and the NRC as a result of the NRC Special Team Inspection performed in 1991 (Inspection Report 91-202).

As a result, three stress packages from Phase I of the program will be reviewed as part of Phase II to determine any potential impact from the criteria changes.

The remaining Phase I stress packages have been determined to be unaffected by the p.iping design criteria changes.

2 The Phase II schedule for the rema1n1ng subphases of the project is provided in Attachment A.

A listing of the stress packages associated with the work is included as Attachment B.

Phase II of the program is currently scheduled to be completed by the end of 1996.

Walkdowns will be performed on a continuing basis.

A limited scope Pipe Support Preventive Maintenance program was implemented as the result of an evaluation of Phase I physical discrepancies, past in-service inspection findings, and past deviation reports. The evaluation identified attributes of a recurring nature.

The results of this study indicated loose and missing fasteners (nuts and bolts) as a recurrent condition which required repeat inspection.

The repeat inspections will provide for a determination, on a case-by-case basis, of the need for revised ISi inspection periodicity.

The limited scope Pipe Support Preventative Maintenance program requires any pipe support identified as having loose or missing fasteners be reinspected for two additional refueling cycles. If both inspection results are acceptable, the support is removed from the active inspection database and no change in its current in-service inspection periodicity is recommended.

Any repetitive findings will result in initiation of corrective action to address the repetitive condition. The corrective action will require that in-service inspection program periodicity be revised to an inspection cycle commensurate with the observed degradation or a root cause determination will be performed and action such as modifications taken to prevent recurrence;

ATTACHMENT A Consumers Power Company Pali sades Pl ant Docket 50-255 Safety Related Piping Reverification Project Periodic Status - October 1992 Phase II Schedule October 30, 1992 1 Page

ATTACHMENT A SRPRP SUPPORT SCHEDULE

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  • NUM uoo~..,~ *uN PTY llIN CAL DOU RDU TF AS /ES CURR EF 1992 1993 1994 1995 1996 J A s 0 ND JF M A M J J A s 0 ND JF M A M J J A s 0 ND JF MA M J JA so ND J F MA MJ J A s 0 ND RllP AODITlONAL INFORMATION DRl6 ES ORIG EF Ill 1111 REFDUT-93 SUPPORT (PHASE II A/Bl I

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REFOUT-9A SUPPORT (PHASE llCl I

I 5 SRPRP580 199A OUTAGE I

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ATTACHMENT B Consumers Power Company Palisades Plant Docket 50-255 Safety Related Piping Reverification Project Periodic Status - October 1992 List of Stress Packages October 30, 1992 3 Pages

Attachment B List of Stress Packages:

Phase I (Complete)

Stress Package SP02502+

SP02503+

SP03342 SP03356 SP03359 SP03360*

SP03361 SP03362 SP03363 SP03364 SP03365 SP03366+

SP03367 SP03368+

SP03375 SP03378 SP05101*

SP05102*

SP05903 SP05904 Long Term Cooling Long Term Cooling Aux Feedwater Discharge Aux Feedwater Pump Suction Pressurizer Surge Primary Loop Auxiliary Piping Pressurizer Spray LPSI to Primary Loop 1 A LPSI to Primary Loop 18 LPSI to Primary Loop 2A LPSI to Primary Loop 28 HPSI to Primary Loop; Superseded by 02503 HPSI to Primary Loop; Supersedes SP-06901 Redundant HPSI; Superseded by 02502 Pressurizer Relief Valve Discharge Piping HPSI Piping Discharge Auxiliary Feedwater Piping to Steam Generator E-50A Auxiliary Feedwater Piping to Steam Generator E-508 Aux Feedwater Pump Suction Aux Feedwater Pump Discharge

Phase llA Stress Package SP03320 SP03322 SP03325 SP03382 SP03383 SP03384 SP03385 SP03386 SP03387 SP05901 SP05902 Phase llB Stress Package SP03312 SP03313 SP03316 Safety Injection, Cont Spray and Shutdown Cooling Safety Injection, Cont Spray and Shutdown Cooling SFP Cooling Pump Discharge to Spent Fuel Heat Exchangers Service Water From Eng Safeguard Cooler VHX-3 Service Water to Eng Safeguard Cooler VHX-3 Service Water From Eng Safeguard Cooler VHX-4 Service Water to Eng Safeguard Cooler VHX-4 Service Water to Eng Safeguard Cooler VHX-2 Service Water From Eng Safeguard Coolers VHX-1, VHX-2, VHX-3, and VHX-4 Aux Feedwater Pump Suction Aux Feedwater Pump Suction Component Cooling Water Component Cooling Water Service Water From Eng Safeguards

Phase 11 C - Approximately 1 7 stress packages Phase 11 D - Approximately 29 stress packages

+

To be Reanalyzed with Phase 118 Stress Packages SP03366 and SP03368 have been merged with SP02502 and SP02503 for final analysis

ATTACHMENT C Consumers Power Company Palisades Plant Docket 50-255 Safety Related Piping Reverification Project Periodic Status - October 1992 Phase I Modification List October 30, 1992 7 Pages

10/28/92 SRPRP Modification List Page '

Mod Item ID FC/SC Stress Type Note (1)

Note (9)

Package Hanger No.

Note (2)

Description Major Cause Co11111ents D

FC-912 SP05101 DBB1-H42 p

Weld @ BOM #7 and plate Revised response spectra.

See note (8) is 17"/o overstressed and BOM #8 and plate is 5%

overstressed.

2 D

FC-912 SP05102 DBB2-H56 p

Weld overstressed Revised response spectra.

See note (8) 3 D

FC-912 SP05102 DBB2-H59 s

swing angle greater than Thermal movements.

See note (8) 5 degrees e

4 D

FC-912 SP05102 DDB2-H60 p

Weld overstressed Revised response spectra.

See note (8) 5 AB SC-90-094 SP03362 GC1-H747 s

Repair/Modify damaged support damaged due to waterha11111er support.

of SI Bottles piping 6

AB SC-90-094 SP03363 GC1-H735 s

Repair/Modify damaged Support damaged due to waterha11111er support.

of SI Bottles piping 7

AB SC-90-094 SP03364 GC1-H756 s

Repair/Modify damaged Support damaged due to waterha11111er support.

of SI Bottles piping 8

AB SC-90-094 SP03365 GC1-H765 s

Repair/Modify damaged Support damaged due to waterha11111er support.

of SI Bottles piping 9

AB SC-90-177 SP06901 CC4-H737 s

Modify support to Walkdown discrepancy/interference eliminate unintentional with adjacent pipe.

restraint/interference 10 D

SC-90-191 SP03360 CC9~H801 s

Replace 1/211 anchor Fricition considered in new bolts with 5/811 Hil ti analysis.

Kwik Bolts.

11 D

SC-90-191 SP03360 CC9-H805 s

Loosen nut on underside Thermal movements.

to allow free swing of e

rod hanger 12 D

SC-90-191 SP03360 GC8-H802 p

Remove support which has Revised response spectra.

rod uplift 13 D

SC-90-191 SP03360 GC8-H804 p

Remove support which has Revised response spectra.

See note (4) rod uplift

Page 2

Mod Item ID FC/SC Stress Type Note (1)

Note (9)

Package Hanger No.

Note (2)

Description Major Cause Conmen ts 14 AB SC-90-231 SP03378 DC1-H198.1 s

Modify support to reduce Exceeded current project criteria.

excessive gap.

15 AB SC-90-231 SP05904 DBB4-H1 s

Shim gap.

Exceeded current project criteria.

16 AB SC-90-231 SP05904 EBB6-H2 s

Shim gap.

Exceeded current project criteria.

17 D

SC-90-252 SP02502 CC6-H714 p

Change rod hanger to Uplift existed on rod hanger from See note (8) strut IE 79-14 analysis, however it was acceptable at that time.

18 D

SC-90-252 SP02502 CC6-H775.5 p

Increase weld length and Design calculation discrepancy.

See note (8) size 19 D

SC-90-252 SP02503 CCB2-H724 p

Remove LI-bolt and add B31.1, Sunmer'73 requires a higher See note (8) angles to restrain SIF (2.1) for socket welds than lateral load.

the original code of record (1.3). This caused a thermal over stress condition.

20 AB (Note 11)

SP02503 Pipe Node 191 p

Relocate unintentional Insufficient clearance between restraint near node 191.

pipe and support from adjacent system.

21 AB SC-90-252 SP03366 DC1-H709 s

Shim gap.

Exceeded current project criteria.

See note (8) 22 AB SC-90-269 SP03367 CC4-H703.4 p

Add new lateral Walkdown discrepancy.

restraint.

23 AB SC-91-147 SP05903 HBC37-H1 s

Increase 3/1611 weld size Physical weld discrepancy.

to 5/1611 24 D

SC-91-147 SP05903 HBC37-H5 s

3/411 X 511 plate welded Design calculation discrepancy.

to bottom side of tube steel to increase moment of inertia. Plate added to take LI-bolt side load.

25 AB SC-91-147 SP05903 HBC37-H8 s

Shim gap.

Exceeded current project criteria.

26 AB SC-91-147 SP05904 EB14-H229 s

Stiffen baseplate to Walkdown discrepancy/anchor bolt utilize rigid plate spacing violation.

analysis on anchor bolts.

Page 3

Mod Item ID FC/SC Stress Type Note (1)

Note (9)

Package Hanger No.

Note (2)

Description Major Cause Conmen ts 27 D

SC-91-148 SP05904 DBC1-H6 p

Change anchor bolts from Design calculation discrepancy.

1/2" to 1" Hilti Kwik bolts 28 D

SC-91-148 SP05904 EB14-H222.1 p

Replace clamp & strut Revised response spectra.

with structural tubing.

29 D

SC-91-148 SP05904 EB14-H232.1 p

New deadweight support B31.1, Sunmer 73 requres a higher SIF (2.0) for a reducer than the original code of record (1.0).

30 D

SC-91-148 SP05904 EBC3-H1.1 p

New X-rigid Revised response spectra.

31 D

SC-91-148 SP05904 Pipe nodes p

Contour fillet weld to Higher SIF required by B31.1 840 & 905 allow Lower SIF Sunmer 73 w/o contoured weld profi Le.

32 D

SC-91-149 SP03367 CC4-H702 p

cut stanchion IWA design calculation discrepancy.

33 D

SC-91-149 SP03367 CC4-H702.2 s

Change existing tack Design calculation discrepancy.

weld to a load carrying fillet weld 34 D

SC-91-149 SP03367 CC4-H703 p

Remove Z-restraint IWA design calculation discrepancy.

35 D

SC-91-149 SP03367 CC4-H704 p

Revise support stanchion IWA design calculation discrepancy.

36 D

SC-91-149 SP03367 CC4-H705 p

Revise support stanchion IWA design calculation discrepancy.

37 D

SC-91-149 SP03367 CC4-H726 p

Add up-Lift restraint to Revised response spectra.

existing hanger.

38 AB SC-91-149 SP03367 CC4-H726.1 s

Cut existing channel &

Walkdown discrepancy/seismic reconnect with 1/2" x 7" displacement in the unrestrainted x 16" plate.

direction (1.138") exceeded existing gap (3/16°).

39 D

SC-91-149 SP03367 CC4-H770 p

Add uplift restraint to Original IE 79-14 analysis showed existing hanger.

an uplift force, however, it was acceptable at that time.

40 AB SC-91-149 SP03367 CC4-R770.1 s

Modify anchor bolts.

Walkdown discrepancy/anchor bolt spacing violation.

Item ID Note (1) 41 42 43 44 45 46 47 48 49 50 51 52 53 D

D D

D D

D D

D D

D D

D D

FC/SC Note (9)

SC-91-149 SC-91-149 SC-91-150 SC-91-150 SC-91-150 SC-91-150 SC-91-150 SC-91-150 SC-91-150 SC-91-150 SC-91-151 SC-91-152 SC-91-152 Stress Package SP03367 SP03367 SP03378 SP03378 SP03378 SP03378 SP03378 SP03378 SP03378 SP03378 SP03359 SP03362 SP03362 Mod Type Hanger No.

Note (2)

CC4-R772 GC1-H712 CC6-R202.1 CC6-R203.3 DC1-H195.2 DC1-H196.2 DC1-H196.3 DC1-R201.2 DC2-H4B Pipe node 117 CC2-H535 CC4-H741 GC1-H743 p

p p

p s

p p

p p

p s

p s

Description New Z-restraint Add uplift restraint to existing hanger.

New X-Z rigid New Y-rigid Modify entire support Change from vertical/lateral to vertical restraint only Disable restraint New Y-rigid Delete support Contour fillet weld to allow lower SIF Modified from a trapeze hanger with a channel on one side and a rod on the other to rods on both sides.

New Lateral and vertical restraint Re-align strut Major Cause Revised deflection criteria Original IE 79-14 analysis showed an uplift force, however, it was acceptable at that time.

Revised response spectra/Valve weight discrepancy.

Revised response spectra/Valve weight discrepancy.

Friction considered in new analysis.

Thermal expansion.

Thermal stresses.

Revised response spectra/Valve weight discrepancy.

Socket weld SIF increased from 1.3 to 2.8/SAM considerations.

Higher SIF required by B31.1 summer 73 w/o contoured weld profile.

Thermal movements.

Revised response spectra.

Design calculation discrepancy.

Page 4

Comments

Page 5

Mod Item ID FC/SC Stress Type Note (1)

Note (9)

Package Hanger No.

Note (2)

Description Major Cause Comments 54 AB SC-91-152 SP03362 GC1-H745 s

Shim gap.

Exceeded current project criteria.

55 AB SC-91-152 SP03362 GC1-H746.1 s

Shim gap.

Exceeded current project criteria.

56 D

SC-91-152 SP03362 GC1-R741.1 p

New Lateral restraint Revised response spectra.

57 D

SC-91-153 SP03363 CC4-H728 s

Change intermittent Undersized weld not evaluated in fillet weld to full IE 79-14 calc.

Length fillet weld 58 D

SC-91-153 SP03363 CC4-H730 p

Change spring to rigid Revised response spectra.

59 D

SC-91-153 SP03363 CC4-S730.1 p

Replace snubber Revised response spectra.

60 AB SC-91-153 SP03363 GC1-H733 s

Shim gap.

Exceeded current project criteria.

61 D

SC-91-153 SP03363 GC1-H734.1 p

Modify structure at weld Revised response spectra.

Locations.

62 D

SC-91-153 SP03363 GC1-R731.1 p

New Lateral restraint Revised response spectra.

63 D

SC-91-154 SP03364 CC4-R749.2 p

New z-restraint Revised response spectra.

64 AB SC-91-154 SP03364 GC1-R754 s

Shim gap.

Exceeded current project criteria.

65 AB SC-91-154 SP03364 GC1-R755 s

Shim gap.

Exceeded current project criteria.

66 AB SC-91-154 SP03364 GC1-R755.1 s

Shim gap.

Exceeded current project criteria.

67 D

SC-91-155 SP03365 CC4-R760.1 p

New vertical restraint Revised response spectra.

68 D

SC-91-155 SP03365 CC4-S758.1 p

Modify snubber.

New thermal movements.

69 AB SC-91-155 SP03365 GC1-H762.1 s

Shim gap.

Exceeded current project criteria.

70 AB SC-91-155 SP03365 GC1-H763 s

Shim gap.

Exceeded current project criteria.

71 AB SC-91-155 SP03365 GC1-H764 s

Shim gap.

Exceeded current project criteria.

72 D

SC-91-155 SP03365 GC1-R761.1 p

New Lateral restraint Revised response spectra.

73 D

SC-91-156 SP03361 CC5-H4.4 s

Box existing angle Design calculation discrepancy/Revised def Lection criteria.

74 D

SC-91-156 SP03361 CC9-H10.1 s

Modify entire support Design calculation discrepancy.

75 D

SC-91-156 SP03361 CC9-H10.2 s

Modify entire support Incorrect design assumption.

76 D

SC-91-156 SP03361 CC9-H13 p

Change spring to strut Revised response spectra.

77 D

SC-91-156 SP03361 CC9-H21.1 s

Modify entire support Design calculation discrepancy.

(.

Page 6,

Mod Item ID FC/SC Stress Type Note (1)

Note (9)

Package Hanger No.

Note (2)

Description Major Cause Comments 78 D

SC*91-156 SP03361 CC9-R19 s

Box existing angle Design calculation discrepancy/original IE 79-14 walkdown discrepancy.

79 AB SC-91-156 SP03361 CC9-R19.1 s

New support at Original IE 79-14 walkdown penetration.

discrepancy/penetration not grouted.

80 D

SC-91-156 SP03361 CC9-R21 s

Modify entire support Design calculation discrepancy.

81 D

SC-91-156 SP03361 CC9-R22 p

Modify entire support Revised response spectra.

82 AB SC-91-156 SP03361 CC9-R22.1 s

New support at Original IE 79-14 walkdown penetration.

discrepancy/penetration not grouted.

83 AB SC-91-156 SP03361 CC9-R25 s

Repair weld of channels Modification resulted from as-to angle-emergent.

built weld profile.

SRPRP Modification List Page 7 NOTES:

( 1)

A "D" designation denotes the modification may be attributed to design considerations; an "AB" designation denotes the modification may be attributed to As-built considerations.

(2)

A "P" designation denotes the modification was driven by piping analysis or as-built considerations; an "S" designation denotes the modification was driven by support analysis or as-built considerations.

-(3)

A pipe clamp was replaced for support CC9-H802.1 (SP03360) under SC-90-191. This modification is not included in the attached list since later reanalysis by EAS showed the original clamp to be acceptable.

(4)

Support GC8-H804 was removed, in two parts, under SC-90-191. Removal of both parts are counted as one modification.

(5)

Modification to supports GC1-S743.1 (SC-91-152) and CC4-S730.2 (SC-91-153) was performed to replace existing snubbers with struts.

Since these were elective mods for the purpose of snubber reduction, they are not counted as SRPRP driven modifications.

(6)

The following pipe support related work which was not performed under an SC is considered maintenance and is not included in the attached list:

a.

Grating was trimmed under WO 241 04456 to remove a seismic interference with SP05904.

b.

A shim was added to support DC2-H2C (SP03378) via WO 24200165.

c.

A shim was added to support GC1-H746 (SP03362) via WO 24200151.

d.

Spring support DBB2-H61 (SP05102) was reset via WO 24002711.

(7)

Supports DBC2-H4 and EB14-H220.5 were originally identified as requiring shim modifications and are detailed in. the EAS trending report.

(8)

However, they were later accepted as-is and documented as such in EA-SP05904-01.

Several modifications in the attached list were performed by projects other than the SRPRP (such as the SGRP); however, they are included herein because the modifications resulted from SRPRP driven concerns and not changes or problems associated with those other projects.

(9)

Facility Change (FC) and Specification Change (SC) are the two procedures which control physical work, other than maintenance, for the Palisades Plant.

(10)

Spring supports CC4-H702.1 and CC4-H702.2 were reset under SC-91-149. These resettings were elective adjustments made under SC-91-149 for convenience and are not considered modifications.

(11)

Unintentional restraint in SP02503 is removed per response to RFl-181-90-P-072 contained in EA-SP02503-01.

. r.*