NRC-2013-0025, Update to Next Era Energy Point Beach. LLC Response to 10 CFR 50.54(f) Request for Information Regarding Near-Term Task Force Recommendation 2.3. Seismic

Update to Next Era Energy Point Beach. LLC Response to 10 CFR 50.54(f) Request for Information Regarding Near-Term Task Force Recommendation 2.3. Seismic

ML13277A109
Person / Time
Site:	Point Beach
Issue date:	10/03/2013
From:	Meyer L Point Beach
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
NRC-2013-0025
Download: ML13277A109 (116)

Text

NEXTera***

ENERGY~

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October 3, 2013 NRC 2013-0025 10 CFR 50.54(f)

U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 Point Beach Nuclear Plant, Units 1 and 2 Docket 50-266 and 50-301 Renewed License Nos. DPR-24 and DPR-27 Update to Next Era Energy Point Beach. LLC Response to 10 CFR 50.54(f) Request for Information Regarding Near-Term Task Force Recommendation 2.3. Seismic

References:

(1) NRC letter to All Power Reactor Licensees and Holders of Construction Permits in Active or Deferred Status, dated March 12, 2012, Request for Information Pursuant to Title 10 of the Code of Federal Regulations 50.54(f) Regarding Recommendations 2.1, 2.3, and 9.3, of the Near-Term Task Force Review of Insights from the Fukushima Dai-lchi Accident (ML12053A340)

(2) NextEra Energy Point Beach, LLC letter to NRC, dated November 26, 2012, NextEra Energy Point Beach LLD Response to 10 CFR 50.54(f) Request for Information Regarding Near-Term Task Force Recommendation 2.3, Seismic (ML12332A070)

On November 26, 2012, NextEra Energy Point Beach, LLC (NextEra) responded to the NRC staff's request for information pursuant to 10 CFR 50.54(f) (Reference 1). Enclosure 3 of Reference (1) contains specific Requested Actions and Requested Information associated with Recommendation 2.3 for Seismic. Requested Information Item 2 of Reference (1 ), Enclosure 4, requested addressees conduct a seismic walkdown and submit a final report which addressed various requirements detailed in the item. Reference (1 ), Enclosure 3 required addressees submit a final seismic walkdown report within 180 days of the NRC's endorsement of the seismic walkdown process.

Via Reference (2), NextEra submitted the required reports for Units 1 and 2 regarding seismic walkdowns. Subsequent to submitting this report, NextEra determined that there were errors in these reports. The errors are administrative in nature and have no impact on the contents of this report. Additionally, NextEra determined that some information in the reports could be better presented.

NextEra Energy Point Beach, LLC, 6610 Nuclear Road, Two Rivers, WI 54241

Document Control Desk Page 2 contains the updated information for the Point Beach Nuclear Plant, Unit 1 seismic walkdown report. Enclosure 2 contains the updated information for the Point Beach Nuclear Plant, Unit 2 seismic walkdown report. A table is provided in the beginning of each enclosure describing the updates. Walkdowns that have been completed after the report will be submitted to the NRC when all of the remaining walkdowns are complete.

This letter contains no new Regulatory Commitments and no revision to existing Regulatory Commitments.

If you have any questions please contact Mr. Michael Millen, Licensing Manager, at 920/755-7845.

I declare under penalty of perjury that the foregoing is true and correct.

Executed on October 3, 2013.

Very truly yours, NextEra Energy Point Beach, LLC Larry Me er Herqice President Enclosures cc: Administrator, Region Ill, USNRC Project Manager, Point Beach Nuclear Plant, USNRC Resident Inspector, Point Beach Nuclear Plant, USNRC Director, Office of Nuclear Reactor Regulation, USNRC

ENCLOSURE 1 NEXTERA ENERGY POINT BEACH, LLC POINT BEACH NUCLEAR PLANT, UNITS 1 AND 2 UPDATE TO NEXTERA ENERGY POINT BEACH, LLC RESPONSE TO 10 CFR 50.54(F)

REQUEST FOR INFORMATION REGARDING NEAR-TERM TASK FORCE RECOMMENDATION 2.3, SEISMIC SEISMIC WALKDOWN REPORT POINT BEACH NUCLEAR PLANT, UNIT 1 1200114-R-001 REVISION 0 56 pages follow

Updates to Seismic Walkdown Report Point Beach Nuclear Plant, Unit 1 1200114-R-001 Revision 0 Executive Summary No Changes Section 1 No Chan_ges Section 2 No Changes Section 3 No Changes Section 4 No Changes Section 5 An additional item was added to Table 5.2 (D-63). An additional item was added to Table 5.3 (AWB 24, Abandoned Pipe Support).

Section 6 No Changes Section 7 No Changes Section 8 No Changes Section 9 No Chan_g_es Appendix A No Changes Appendix B Table 3, IPEEE and A-46 Outlier Resolution, is updated to only include the equipment for Unit 1. Resolution dates were also added.

Attachment C was added to provide the selected equipment list. The enclosed pages, B-14 through B-51, replace pages B-14 through B-38 of the original report.

Appendix C Administrative changes made on pages C-49, C-56, and C-179.

Appendix D Administrative change made on pages D-35 and D-40.

Appendix E Table E-1 has been updated Appendix F Administrative changes made on pages F-3 and F-4.

Table 5-2: Table of Actions Resulting from Seismic Walkdown lns(!ection Cl "C "C s::: Q)

Q) N Equipment "C I E >- Action Taken to ID Potentially Adverse Seismic Condition ...Cl ltl s::: ...

0 0 z.,_

'iij s::: Address the Condition Current Status Q) s::: ltl c 0 CJ s:::

J NextEra Engineer A section of tubing is supporting the solenoid and determined from P&ID attached flexible conduit fitting. The solenoid and the drawings that a loss of Being tracked in 1MS-02090 X fitting are relatively heavy compared to the capacity of air to the valve results in the CAP.

the tubing supporting them. the valve going to a safe position. Initiated CR.

NextEra performed an evaluation of contents of the panels and The south side of panel DY-OC is in contact with an 1-83/DY-03 determined that the electrical fitting attached to panei1-83/DY-03. It is X Closed and DY-OC interaction would not uncertain what components are in each panel.

affect the operability of the components.

Initiated CR.

The condition was evaluated and determined to be acceptable. A review of Cracks identified in concrete along centerline of Being tracked in 1B-04 X the modification and anchors. the CAP.

calculation determined that there is sufficient margin to accommodate the crack. Initiated CR.

Informed maintenance Closed.

1P-002A Light supported off incorrectly oriented beam clamp. X and operations to repair. Identified issue Initiated CR. repaired.

D-63 Overhead 3" Service Water line (return) has The walkdown team Work Request condensation on it. Part of the line is above 1SMS- X determined that this is initiated to repair.

02020. not a seismic concern

Table 5-2: Table of Actions Resulting from Seismic Walkdown lns(;!ection C) "C "C  !: Q)

Q) N Equipment "C I E >- Action Taken to ID Potentially Adverse Seismic Condition ...

!tl C) 0 0 z-!:

(ij

!: Address the Condition Current Status Q) !tl c 0 u

J The walkdown team determined that the light fixture would not fall and interact with seismically An overhead light fixture was raised by overlapping the qualified equipment Work Request 1P-014A X light fixture chain and securing it with ty-wraps. since the chain would initiated to repair.

support the light fixture if the ty-wraps were to break.

Initiated CR.

The walkdown team determined that the missing bolt does not adversely affect the Work Request 1B-03 Rear bottom panel is missing a mounting bolt. X seismic capability of the initiated to repair.

equipment. The bolt is one of many that attach the rear panel to the frame. Initiated CR.

The chain was secured Closed.

behind conduit and Chain for valve SF-1 can interact with the oiler on the Chain is tied off P-012A X judged not to pose a pump. to a support with current concern.

seal type lock.

Initiated CR.

Table 5-2: Table of Actions Resulting from Seismic Walkdown lnsQection C) "C "C  !: Q)

Q) N Equipment "C I E >- Action Taken to ID Potentially Adverse Seismic Condition ...11:1 C) 0 0 z.,_

iii

!: Address the Condition Current Status Q)  !: 11:1 c 0  !:

(J =>

Per calculation 91 C2696-C-021 a spacing of 9", 9", 9" is used. There is a safety East bolt spacing is not per drawing EC-36A-3, Job factor of 42.5 on these 12703, Rev. 3. Bolts are spaced at 8", 9" and 8" in the Being tracked in HX-013A X anchors. Therefore, they north south direction. The drawing shows the bolts the CAP.

are concluded to be spaced at 9", 9" and 9".

capable of carrying the load with the slightly reduced spacing.

Initiated CR.

Per calculation 91C2696-C-021 a spacing of 9", 9", 9" is used. There is a safety East bolt spacing is not per drawing EC-36A-3, Job factor of 42.5 on these 12703, Rev. 3. Bolts are spaced at 7 %"", 9 %""and Being tracked in HX-013B X anchors. Therefore, they 7 %"" in the north south direction. The drawing shows the CAP.

are concluded to be the bolts spaced at 9", 9" and 9".

capable of carrying the load with the slightly reduced spacing.

Initiated CR.

NextEra Engineer determined junction box Overhead trolley control pendant wedged between and pump casing are Work request P-32A X pump junction box and pump casing. rugged and will not be initiated to repair.

damaged by the pendant. Initiated CR.

Table 5-3: Table of Actions Resulting from Area Walk-b~ lns~ections C) 't:J

't:J Q)

Q)

't:J I.E1: N

>- Action Taken to Area Potentially Adverse Seismic Condition ...!tl C) 1: ...

0 0 z-1:

iii 1: Address the Condition Current Status Q) !tl c 0

(.)

1:

J The seismic walkdown team assessed the potential interaction during the walkdown and determined not to The instrument pipe behind valve 1RH-716B has a long Work request AWB3 X be a concern. The pipe horizontal cantilever. The first support clamp is loose. initiated to repair.

will not move enough to interact and damage seismically qualified equipment.

Initiated CR.

NextEra Engineer determined that the Masonry wall located behind 2CV-351. Could not masonry wall was not in AWBS X Closed determine if wall was seismically evaluated. vicinity of safety related equipment. Initiated CR.

Initiated CR. NextEra Engineering performed a preliminary calculation to show that there is The nuts for the south post for 1T-006A are not fully sufficient capacity in the Work request AWB8 X tightened. remaining bolts to initiated to repair.

prevent the tank from overturning and becoming an interaction concern.

Table 5-3: Table of Actions Resulting from Area Walk-by lnsRections C) '0

'0  !: Q)

Q) N

'0 I E >- Action Taken to Area Potentially Adverse Seismic Condition ...ns C) 0 0 z,._

jij

!: Address the Condition Current Status Q)  !: ns c 0 0

J In the judgment of the walkdown team, the An S-Hook supporting a light fixture was observed to be light fixture would not Work request AWB9 X opened. fall and interact with any initiated to repair.

seismically qualified equipment. Initiated CR.

The seismic walkdown team determined that the tubing was The public address speaker is close to an instrument sufficiently rugged that Work request AWB 15 X line and could interact with it. it would not be initiated to repair.

damaged by the speaker in a seismic event. Initiated CR.

The walkdown team judged that the tube was not an interaction hazard and would deflect but not break in A 3/8" tube for valve 1SI-881A has a long span (-1 0') Work request AWB 19 X a seismic event. A and is very flexible. initiated to repair.

preliminary calculation of the tubing spans showed that the tubing will not overstress.

Initiated CR.

Table 5-3: Table of Actions Resulting from Area Walk-by: lnsQections C) '0

'0 Q) c Q)

N

'0 I "j§ c ,_ >-

Ill Ia Action Taken to Area Potentially Adverse Seismic Condition 0 0 Current Status C) z-c c Address the Condition Q) Ill 0 0 c

(.) :::1 The walkdown team determined that the On the west wall there is a flexible pipe from SI-917A condition was not a AWB 19 that appears to bearing on some conduit clamps. The Work request X seismic concern. There hose could dislodge from the clamps and interact with initiated to repair.

were no soft targets items below.

immediately below.

Initiated CR.

A conduit for valve 2SI-825C is attached to the flange of Thecondu~isattached AWB 19 a vertical hanger with clamps oriented such that they to nearby cable tray Work request X

are resisting dead load with friction. Clamps should be JG08 and will not fall. initiated to repair.

re-orientated. Initiated CR.

The bottom support of the pipe is oriented A copper instrument air pipe is attached to a vertical correctly. There is a AWB 19 hanger with clamps oriented such that they are resisting support in the horizontal Work request X

dead load with friction. The clamps should be run at the top of the initiated to repair.

reoriented. riser. Based on this the pipe is judged not to fall. Initiated CR.

There are two lights in the area that are attached to The lights were tug AWB 19 structural steel with magnets. It is suggested that the tested and determined X Closed magnets be backed up with lanyards to assure they will to be adequately not fall. supported. Initiated CR.

Table 5-3: Table of Actions Resulting from Area Walk-by lns12ections C) "0 "0 Q)

Q)

"0 I -=E N

>- Action Taken to Area Potentially Adverse Seismic Condition ...

IU C) s::: ...

0 z-s:::

0 "ii s::: Address the Condition Current Status Q) IU c 0

(.)

s:::

A pipe support in the north west corner of the room was observed to have potential deficiencies. The support is The walkdown team a structural member (W shape) with the weak axis judged it to be resisting dead load welded to a four bolt anchor plate at Being tracked in AWB20 X acceptable since the each end. One of the anchors on the south plate is the CAP.

support is lightly loaded.

missing. The west flange of the support and about% of CR initiated.

the web are notched in three places. There is a shackle on the south west anchor on the north plate.

The walkdown team judged the items Various housekeeping items identified at Elevation 66, Work request AWB24 X acceptable due to no above the SFP Hx area initiated to repair.

soft targets in the area.

Initiated CR.

The walkdown team The anchors for T-161A appear to be in oversized holes judged the anchors to Work request AWB24 X and some had minor corrosion. be adequate to support initiated to repair.

the tank. Initiated CR.

The walkdown team judged the piping to not The piping from T-161C to the header is not clamped to be a falling hazard Work request AWB24 X the supports. Hence it is not laterally supported. since there are no soft initiated to repair.

targets below. Initiated CR.

AWB24 The walkdown team judged the connection Work request There is an abandoned pipe support in the SW corner of the pipe support is X initiated to remove of the SFP HX area. robust, and therefore the support.

does not pose an interaction hazard.

Table 5-3: Table of Actions Resulting from Area Walk-b~ lns~ections C'l "C "C

Q) c: Q)

N "C I E >- Action Taken to ctS c: .... iii Area Potentially Adverse Seismic Condition .... 0 0 c:

Current Status C'l z-c: Address the Condition Q) ctS c 0 c:

(J  :::J There is a missing anchor bolt on the pipe support west Previously identified Work Request AWB27 X of P-31A and evaluated in CR. initiated to repair.

There is a missing anchor bolt on the base plate north Previously identified Work Request AWB27 X west of P-31A for a chlorination line. and evaluated in CR. initiated to repair.

Corrosion evaluated by Closed.

NextEra Engineering Will be tracked and determined to AWB27 There is corrosion on P-31A and P-318 base plates. X through structures minor surface corrosion monitoring and not a concern. CR program.

initiated.

NextEra Engineering performed a walkdown and determined that The G-01 diesel room contains threaded fire protection much of the area is not piping that is supported from threaded rod hangers.

susceptible to issues do The fire protections system is only laterally supported at to spray. A preliminary a connection to a fire protection header which comes evaluation was into the room through a wall. The lines are supported performed for the piping off various lengths threaded rods that are typically at the west end of the attached to a shell type anchor in the concrete ceiling. Being tracked in AWB42 X room and it was On the west end, the fire protection line and a sprinkler the CAP.

determined that the head are relatively close to the room fans. The Seismic piping is within code Walkdown Team was unable to conclude that the fire allowable stresses and protection pipe and sprinkler head would not move and will not leak. This interaction with the fans. In addition, the team could not preliminary evaluation conclude that the fire protection line would not deflect in was considered a a manner that would cause the threaded fittings to leak.

bounding case and thus the remaining piping will not leak. Initiated CR.

Table 5-3: Table of Actions Resulting from Area Walk-by Ins~ections Cl "C "C s:::

Area Potentially Adverse Seismic Condition Q)

"C

...Clco

. *e s::: ... ~

Q)

N co Action Taken to Current Status 0 0 z..,_ s:::

co Address the Condition Q) s::: s:::

0 0

(,)  ::l The walkdown team determined that the The cable tray overhead spanning from C-180 to C-181 AWB48 X cable tray is sufficiently Closed is sagging and several of the rungs are bent.

supported that it would not fall. CR initiated.

POINT BEACH NUCLEAR PLANT, UNIT 1 1200114-R-001, REVISION 0 B-14 Table 3 IPEEE and A-46 Outlier Resolution -Unit 1 Outlier Program Equip System Equip Noun Name Status at Time of SRT Outlier Description Interim Resolution Documented Status I Final Required Date No. Class ID Walkdown in 1993 in the USI A-46 Seismic Resolution Close Out Completed Evaluation Report to NRC A, I 2 480V 18- 480v 0-ANCHORAGE The anchorage weld There is sufficient anchorage MR 95-005 SQ-001544, 7/6/99 3 03 Safeguards INSUFFICIENT, Weld spacing is too large, capacity in the existing welds to installed new SQ-001531 Load Center spacing is to large. every 3rd cabinet in carry the seismic anchorage anchorage (WO completed Every 3rd cabinet in some cases. The loads. However, the switchgear 9700600). EWR some cases. TROLLEY trolley hoist that was declared an outlier because 96-042 evaluated HOIST needs to be rides along the top it is not good engineering breaker handling clamped in place. T. of the switchgear practice to transfer the seismic trolley. EWR Dykstra to submit poses an interaction loading through the switchgear closed. MR 98-094 separate EWRs for weld hazard. structure. The switchgear is installed trolley and trolley hoist. considered seismically stops.

operable. Modification MR 95-005 is initiated to install new anchorage. The trolley hoist will be evaluated.

A, I 2 480V 18- 480v 0-ANCHORAGE The anchorage weld There is sufficient anchorage MR 95-005 SQ-001545, 7/6/99 5 04 Safeguards INSUFFICIENT, Weld spacing is too large, capacity in the existing welds to installed new SQ-001535 Load Center spacing is to large. every 3rd cabinet in carry the seismic anchorage anchorage. EWR complete Every 3rd cabinet in some cases. The loads. However, the switchgear 96-042 assigned to some cases. TROLLEY trolley hoist that was declared an outlier because evaluated breaker HOIST needs to be rides along the top it is not good engineering handling trolley.

clamped in place. T. of the switchgear practice to transfer the seismic EWR closed. MR Dykstra to submit poses an interaction loading through the switchgear 98-094 installed separate EWRs for weld hazard. structure. The switchgear is trolley stops.

and trolley hoist. considered seismically operable. Modification MR 95-005 is initiated to install new anchorage. The trolley hoist will be evaluated.

A, I 4 4.16KV 1X- 8-03 Station 0- ANCHORED WITH The transformer The friction clips provide MR 94-012 SQ-001703 8/1/97 8 13 Service FRICTION CLIPS. MR anchorage uses adequate capacity to withstand installed new completed Transformer in process. MR 94-012 friction clips which the P8NP SSE, because the anchorage-are not covered by friction coefficient exceeds the accepted 4/16/96.

the GIP. seismic demand level. The anchorage will be upgrade under modification MR 94-012.

A, I 4 4.16KV 1X- 8-04 Station 0 - ANCHORED WITH The transformer The friction clips provide MR 94-012 SQ-001799 8/1/97 10 14 Service FRICTION CLIPS. MR anchorage uses adequate capacity to withstand installed new completed Transformer in process. MR 94-012 friction clips which the P8NP SSE, because the anchorage-are not covered by friction coefficient exceeds the accepted 4/16/96.

the GIP. seismic demand level. The anchorage will be upgrade under modification MR 94-012.

POINT BEACH NUCLEAR PLANT, UNIT 1 1200114-R-001 REVISION 0 B-15 Outlier Program Equip System Equip Noun Name Status at Time of SRT Outlier Description Interim Resolution Documented Status I Final Required Date No. Class ID Walkdown in 1993 in the USI A-46 Seismic Resolution Close Out Completed Evaluation Report to NRC A, I 12 5 RH 1P-10A Residual Heat Removal 0 - Anchorage failed The pump anchorage has less The pump anchorage was analyzed in accordance with S&ACalc 91 C2696-C-008 SQ-1842 completed.

11/5/02 Pump than GIP minimum ACI 349-80 Appendix 8 and uses guidelines required edge shown to have sufficient from ACI-349-80 to distance, resulting in capacity. show pump anchorage failure anchorage when evaluated in adequate accordance with the GIP.

A, I 5 RH 1P- Residual Heat The pump 13 108 Removal 0 - Anchorage failed anchorage has less The pump anchorage was analyzed in accordance with S&ACalc 91 C2696-C-008 SQ-1802 completed.

11/5/02 Pump than GIP minimum ACI 349-80 Appendix 8 and uses guidelines required edge shown to have sufficient from ACI-349-80 to

. distance, resulting in capacity. show pump anchorage failure anchorage when evaluated in adequate accordance with the GIP.

14 A,I,C 5 cc 1P- Component 0-ANCHOR The anchor J-bolts A calculation per ACI 318-63 S&ACalc SQ-1804 11/5/02 11A Cooling Water have an embedment and ACI 349-80 Appendix 8 91 C2696-C-009 completed.

Pump < 16D as required by shows that the pump anchorage uses the guidelines the GIP. has sufficient capacity. from ACI 318-63 and ACI 349-80 Appendix 8 to show that the pump anchorage has sufficient capacity.

15 A,I,C 5 cc 1P- Component 0-ANCHOR The anchor J-bolts A calculation per ACI 318-63 S&A Calc SQ-1803 11/5/02 118 Cooling Water have an embedment and ACI 349-80 Appendix 8 91 C2696-C-009 completed.

Pump < 16D as required by shows that the pump anchorage uses the guidelines the GIP. has sufficient capacity. from ACI 318-63 and ACI 349-80 Appendix 8 to show that the pump anchorage has sufficient capacity.

A, I Sl 1P- Containment The anchor J-bolts A calculation per ACI 318-63 16 5 14A Spray Pump 0 - Failed Anchorage Calc PIPE LOAD ON have an embedment and ACI 349-80 Appendix 8 S&ACalc 91 C2696-C-019 SQ-1805 completed.

11/12/02 SUCTION NOZZLES < 16D as required by shows that the pump anchorage uses the guidelines the GIP. has sufficient capacity. from ACI 318-63 and ACI 349-80 Appendix 8 to show that the pump anchorage has sufficient capacity.

POINT BEACH NUCLEAR PLANT, UNIT 1 1200114-R-001 ' REVISION 0 B-16 Outlier Program Equip System Equip Noun Name Status at Time of SRT Outlier Description Interim Resolution Documented Status I Final Required Date No. Class ID Walkdown in 1993 in the USI A-46 Seismic Resolution Close Out Completed Evaluation Report to NRC A, I 5 Sl 1P- Containment 0 - Failed Anchorage The anchor J-bolts A calculation per ACI 318-63 S&A Calc SQ-1806 11/12/02 18 148 Spray Pump Calc PIPE LOAD ON have an embedment and ACI 349-80 Appendix 8 91 C2696-C-019 completed.

SUCTION NOZZLES < 16D as required by shows that the pump anchorage uses the guidelines the GIP. has sufficient capacity. from ACI 318-63 and ACI 349-80 Appendix 8 to show that the pump anchorage has sufficient capacity.

A, I 6 SW P- Service Water 0 - Anchorage/capacity The pump extending The pump is considered S&ACalc SQ-1808 6/15/99 20 32A Pump check on bolts & studs, casing is 34' long > operable based on original 91 C2696-C-012 completed.

restraint of overhead the 20' allowable. design calculations. S&A shows pump shaft trolley, The overhead crane calculation 91 C2696-C-012 stresses within poses an interaction shows that the pump shaft limits. EWR 96-hazard. stress is within allowable limits. 041 evaluated the overhead hoist.

Concluded that the existing configuration does not present an interaction hazard to the SW pumps -

completed 12/5/96.

A, I 6 sw P- Service Water 0 - Anchorage/capacity The pump extending The pump is considered S&ACalc SQ-1809 6/15/99 21 328 Pump check on bolts & studs, casing is 34' long > operable based on original 91 C2696-C-012 completed.

restraint of overhead the 20' allowable. design calculations. S&A shows pump shaft trolley, The overhead crane calculation 91 C2696-C-012 stresses within poses an interaction shows that the pump shaft limits. EWR 96-hazard. stress is within allowable limits. 041 evaluated the overhead hoist.

Concluded that the existing configuration does not present an interaction hazard to the SW pumps -

completed 12/5/96.

POINT BEACH NUCLEAR PLANT, UNIT 1 1200114-R-001 , REVISION 0 8-17 Outlier Program Equip System Equip Noun Name Status at Time of SRT Outlier Description Interim Resolution Documented Status I Final Required Date No. Class ID Walkdown in 1993 in the USI A-46 Seismic Resolution Close Out Completed Evaluation Report to NRC 22 A, I 6 sw P- Service Water 0 - Anchorage/capacity The pump extending The pump is considered S&ACalc SQ-1810 6/15/99 32C Pump check on bolts & studs, casing is 34' long > operable based on original 91C2696-C-012 completed.

restraint of overhead the 20' allowable. design calculations. S&A shows pump shaft trolley, The overhead crane calculation 91 C2696-C-012 stresses within poses an interaction shows that the pump shaft limits. EWR 96-hazard. stress is within allowable limits. 041 evaluated the overhead hoist.

Concluded that the existing configuration does not present an interaction hazard to the SW pumps -

completed 12/5/96.

23 A, I 6 sw P- Service Water 0 - Anchorage/capacity The pump extending The pump is considered S&ACalc SQ-1811 6/15/99 32D Pump check on bolts & studs, casing is 34' long > operable based on original 91C2696-C-012 completed.

restraint of overhead the 20' allowable. design calculations. S&A shows pump shaft trolley, The overhead crane calculation 91C2696-C-012 stresses within poses an interaction shows that the pump shaft limits. EWR 96-hazard. stress is within allowable limits. 041 evaluated the overhead hoist.

Concluded that the existing configuration does not present an interaction hazard to the SW pumps -

completed 12/5/96.

24 A, I 6 sw P- Service Water 0 - Anchorage/capacity The pump extending The pump is considered S&ACalc SQ-1812 6/15/99 32E Pump check on bolts & studs, casing is 34' long > operable based on original 91 C2696-C-012 completed.

restraint of overhead the 20' allowable. design calculations. S&A shows pump shaft trolley, The overhead crane calculation 91 C2696-C-012 stresses within poses an interaction shows that the pump shaft limits. EWR 96-hazard. stress is within allowable limits. 041 evaluated the overhead hoist.

Concluded that the existing configuration does not present an interaction hazard to the SW pumps -

completed 12/5/96.

POINT BEACH NUCLEAR PLANT, UNIT 1 1200114-R-001 , REVISION 0 B-18 Outlier Program Equip System Equip Noun Name Status at Time of SRT Outlier Description Interim Resolution Documented Status I Final Required Date No. Class ID Walkdown in 1993 in the USI A-46 Seismic Resolution Close Out Completed Evaluation Report to NRC 25 A, I 6 sw P- Service Water 0 - Anchorage/capacity The pump extending The pump is considered S&ACalc SQ-1813 6/15/99 32F Pump check on bolts & studs, casing is 34' long > operable based on original 91C2696-C-012 completed.

restraint of overhead the 20' allowable. design calculations. S&A shows pump shaft trolley, The overhead crane calculation 91 C2696-C-012 stresses within poses an interaction shows that the pump shaft limits. EWR 96-hazard. stress is within allowable limits. 041 evaluated the overhead hoist.

Concluded that the existing configuration does not present an interaction hazard to the SW pumps -

completed 12/5/96.

A,I,V 7 cs 1CS- Hx-1a Sg 0- Block Wall The valves are The function of the valve is to EWR- Functional No 8/30/00 26 466 Feedwater interaction adjacent to a large close to isolate feed to the S/Gs. Evaluation. walkdown Regulator unanalyzed block The valve is not required to shut 6/20/96 - EWR 96- required Control wall. The block wall during the 30 second period of 043 assigned to SQ-001814 poses an interaction strong motion. However, it is document update hazard for the valve desired to have it shut during evaluation. complete.

and it sub- the 72 hour8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> recovery period. As Evaluation components. a backup to the valve failing to concluded that this close, the operators can turn off valve is not the feed pumps and condensate required to be on pumps. the SSEL.

A,I,V 7 cs 1CS- Hx-1b Sg 0- Block Wall The valves are The function of the valve is to EWR - Functional No 8/30/00 28 476 Feedwater interaction adjacent to a large close to isolate feed to the S/Gs. Evaluation. walk down Regulator unanalyzed block The valve is not required to shut 6/20/96 - EWR 96- required Control wall. The block wall during the 30 second period of 043 assigned to SQ-001816 poses an interaction strong motion. However, it is document update hazard for the valve desired to have it shut during evaluation. complete.

and it sub- the 72 hour8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> recovery period. As Evaluation components. a backup to the valve failing to concluded that this close, the operators can turn off valve is not the feed pumps and condensate required to be on pumps. the SSEL.

POINT BEACH NUCLEAR PLANT, UNIT 1 1200114-R-001 REVISION 0 B-19 Outlier Program Equip System Equip Noun Name Status at Time of SRT Outlier Description Interim Resolution Documented Status I Final Required Date No. Class ID Walkdown in 1993 in the USI A-46 Seismic Resolution Close Out Completed Evaluation Report to NRC 30 A,I,V 7 cs 1CS- Hx-1a Sg 0- Block Wall The valves are The valve is normally close and EWR- Functional No 8/30/00 480 Regulator interaction adjacent to a large must remain closed to isolate Evaluation. walkdown Control unanalyzed block feed to the S/Gs. Therefore, 6/20/96 - EWR 96- required Bypass wall. The block wall during the 30 second period of 043 assigned to SQ-001818 poses an interaction strong motion, the valve is not document update hazard for the valve required to change state. It is evaluation. complete.

and it sub- not likely, that the block wall Evaluation components. interaction would cause the concluded that this valve to open. As a backup to valve is not the valve inadvertently opening, required to be on the operators can turn off the the SSEL.

feed pumps and condensate pumps.

32 A,I,V 7 cs 1CS- Hx-1b Sg 0- Block Wall The valves are The valve is normally close and EWR- Functional No 8/30/00 481 Regulator interaction adjacent to a large must remain closed to isolate Evaluation. walkdown Control unanalyzed block feed to the S/Gs. Therefore, 6/20/96 - EWR 96- required Bypass wall. The block wall during the 30 second period of 043 assigned to SQ-001820 poses an interaction strong motion, the valve is not document update hazard for the valve required to change state. It is evaluation. complete.

and it sub- not likely, that the block wall Evaluation components. interaction would cause the concluded that this valve to open. As a backup to valve is not the valve inadvertently opening, required to be on the operators can turn off the the SSEL.

feed pumps and condensate pumps.

I,V,RG 7 RM 1RM- Re-211/Re- 0 - Based on visual The valve is located The item has been walked down 12/28/98 - EWR SQ-001985 3/10/98 34 3200 212 Monitor inspection, the building in a climate control for the IPEEE only. Subsequent 96-044 complete. resolves A Return the RMs are located in is hut that has no to the walkdown, it has been ID'd the anchorage. this outlier not anchored. Need to visible base screened out using the Seismic S&L completed check any drawings. 1 anchorage. PSA screening criteria. calc. Calculation OF 4 ANCHOR BOLTS resolves outlier.

MISSING. Need to determine which ISRS would be applicable

POINT BEACH NUCLEAR PLANT, UNIT 1 1200114-R-001 REVISION 0 B-20 Outlier Program Equip System Equip Noun Name Status at Time of SRT Outlier Description Interim Resolution Documented Status I Final Required Date No. Class ID Walkdown in 1993 in the USI A-46 Seismic Resolution Close Out Completed Evaluation Report to NRC I,V,RG RM 1RM- Re-211/Re- 0 - Based on visual The valve is located The item has been walked down 36 7 3200 212 Monitor inspection, the building in a climate control for the IPEEE only. Subsequent 12/28/98 - EWR 96-044 complete.

SQ-001987 resolves 3/10/98 8 Supply the RMs are located in is hut that has no to the walkdown, it has been ID'd the anchorage. this outlier not anchored. Need to visible base screened out using the Seismic S&L completed check any drawings. 1 anchorage. PSA screening criteria. calc. Calculation OF 4 ANCHOR BOLTS resolves outlier.

MISSING. Need to determine which ISRS would be applicable 38 A, I 7 sc 1SC- Rhr Loop 0 -Valve is only The AOV body is This valve is normally closed EWR - 6/20/96 - SQ-001771 1/14/00 959 Sample restrained by 2 U-bolts mounted to a and is required to stay closed in EWR Submitted, resolves Isolation in friction. The valve is support shelf by 2 U- the event of an SSE. The U-bolt MR 96-035 this outlier on a 3/8" sample line. bolts in friction. The support will be analyzed and if assigned to install Should have operator valve is mounted on required a valve operator operator support.

support or analysis on a 3/8" line. If the U- support will be installed. (DNC) WO load bearing capacity of bolts slip, the 9817131.

U-bolts potential exists for Installation the line to be complete.

overstress.

A,I,V 7 Sl 1SI- T-34a Si 0 - The Shot in concrete The Shot in concrete The support frame anchorage Fixed, MR 93-047. SQ-001641 9/29/95 39 839A Accum Outlet nails used for anchorage nails used for was modified during the same Accepted 4/29/94 resolves To Si Test of the valve support anchorage of the U1 R21 refueling outage under outlier, Line Isolation frame are not covered in valve support frame MR 93-047 completed the GIP. They are are not covered in considered to be the GIP. They are seismically operable by considered to be inspection. Anchorage seismically operable evaluation will be done. by inspection.

7/25/94- Support frame modified during U1 R21.

MR 93-047 A,I,V 7 Sl 1SI- Si A Cold Leg 0 - The Shot in concrete The Shot in concrete The support frame anchorage Fixed, MR 93-047. SQ-001642 9/29/95 41 8398 To Si Test nails used for anchorage nails used for was modified during the same Accepted 4/29/94 resolves Line Isolation of the valve support anchorage of the U1 R21 refueling outage under outlier.

frame are not covered in valve support frame MR 93-047 the GIP. They are are not covered in considered to be the GIP. They are seismically operable by considered to be inspection. Anchorage seismically operable evaluation will be done. by inspection.

7/25/94- Support frame modified during U1 R21.

MR 93-047

POINT BEACH NUCLEAR PLANT, UNIT 1 1200114-R-001 REVISION 0 B-21 Outlier Program Equip System Equip Noun Name Status at Time of SRT Outlier Description Interim Resolution Documented Status I Final Required Date No. Class ID Walkdown in 1993 in the USI A-46 Seismic Resolution Close Out Completed Evaluation Report to NRC A,I,V 7 Sl 1SI- T-34b Si 0 - The Shot in concrete The Shot in concrete The support frame anchorage Fixed, MR 93-047. SQ-001643 9/29/95 43 839C Accum Outlet nails used for anchorage nails used for was modified during the same Accepted 4/29/94 resolves To Si Test of the valve support anchorage of the U1 R21 refueling outage under outlier.

Line Isolation frame are not covered in valve support frame MR 93-047 Completed the GIP. They are are not covered in considered to be the GIP. They are seismically operable by considered to be inspection. Anchorage seismically operable evaluation will be done. by inspection.

7/25/94- Support frame modified during U1 R21.

MR 93-047 A,I,V 7 Sl 1SI- SiB Cold Leg 0 - The Shot in concrete The Shot in concrete The support frame anchorage Fixed, MR 93-047. SQ-001644 9/29/95 45 839D To Si Test nails used for anchorage nails used for was modified during the same Accepted 4/29/94 resolves Line Isolation of the valve support anchorage of the U1 R21 refueling outage under outlier.

frame are not covered in valve support frame MR 93-047 Completed the GIP. They are are not covered in considered to be the GIP. They are seismically operable by considered to be inspection. Anchorage seismically operable evaluation will be done. by inspection.

7/25/94- Support frame modified during U1 R21.

MR 93-047 I,V 7 Sl 1SI- T-34a Si 0 -Within 1/2" of The valve is within An operator support was Fixed, MR 94-031 - SQ-001645 11/18/94 47 844A Accumulator concrete wall. Valve on 1/2" of concrete wall. installed during the same Accepted 4/25/94 resolves Drain To T-16 1" line. Recommend Valve on 1" line. U1 R21 refueling outage under outlier.

Rcdt brace on yoke. 7/25/94 modification MR 94-031. Completed

- Added operator support during U1 R21 MR 94-031 I,V 7 Sl 1SI- T-34b Si 0- Valve operator The valve operator The valve support was mounted Fixed, MR 94-031 - SQ-001646 11/18/94 48 8448 Accumulator support is not anchored support is not during the same U1 R21 under Accepted 4/25/94 resolves Drain To T-16 to the floor. 7/25/94- anchored to the MR 94-031 outlier.

Rcdt Modified operator floor. Completed support during U1 R21 MR 94-031

POINT BEACH NUCLEAR PLANT, UNIT 1 1200114-R-001 REVISION 0 B-22 Outlier Program Equip System Equip Noun Name Status at Time of SRT Outlier Description Interim Resolution Documented Status I Final Required Date No. Class ID Walkdown in 1993 in the USI A-46 Seismic Resolution Close Out Completed Evaluation Report to NRC I,V,RG 7 Sl 1SI- T-34a/B Si 0 - 36" offset on 1.25" 49 846 Accum line. Because of pipe The AOV offset of 36" < 45" allowable The item has been walked down for the IPEEE only. Subsequent (MR 94-066*8 is incorrect) MR 95-SQ-001951 completed 4/30/96 Nitrogen Inlet support configuration, offset for a 1" line. to the walkdown, it has been 059 installed a Control potential for pipe However, because screened out using the Seismic check valve, relief overstress. of the pipe support PSA screening criteria. valve and regulator configuration, there Modification request MR 94- in the line during is a potential for pipe 066*B is initiated to upgrade the U1R23. S&L overstress. support of the 1" line. analysis WE-100165. Stresses are above allowable but below operability. CR 98-2401 created.

2/8/99: CR action (MAW) to do an analysis. MR 00-009 removed existing support and added two new supports.

I,RG 7 WG 1WG T-16 Rcdt 0 - Even though 24" Even though 24" The item has been walked down 52 -1786 Vent offset< 45" GIP offset < 45" GIP for the IPEEE only. Subsequent EWR 96-049 assigned - valves SQ-001775 resolves 1/14/00 allowable for a 1" there allowable for a 1" to the walkdown, it has been have been as-built, this outlier is a potential for pipe there is a potential screened out using the Seismic 9/3/98. Need to overstress in line 1"-WD- for pipe overstress in PSA screening criteria. draft sketch for 151R-1 becauseofhow line 1"-WD-151R-1 valve supports.

the 1" line is supported. because of how the 4/1/99- MR 96-035 1" line is supported. will install operator support. WO 9904473.

Installation complete.

I,RG 7 WG 1WG T-16 Rcdt 0 - Even though 24" Even though 24" The item has been walked down EWR 96-049 54 -1787 Vent offset < 45" GIP offset< 45" GIP for the IPEEE only. Subsequent assigned - valves SQ-001776 resolves 1/14/00 allowable for a 1" there allowable for a 1" to the walkdown, it has been have been as-built, this outlier is a potential for pipe there is a potential screened out using the Seismic 9/3/98. Need to overstress in line 1"-WD- for pipe overstress in PSA screening criteria. draft sketch for 151 R-1 because of how line 1"-WD-151R-1 valve supports.

the 1" line is supported. because of how the 4/1/99- MR 96-035 1" line is supported. will install operator support. WO 9904473.

Installation complete.

POINT BEACH NUCLEAR PLANT, UNIT 1 1200114-R-001 ' REVISION 0 B-23 Outlier Program Equip System Equip Noun Name Status at Time of SRT Outlier Description Interim Resolution Documented Status I Final Required Date No. Class ID Walkdown in 1993 in the USI A-46 Seismic Resolution Close Out Completed Evaluation Report to NRC A, I 8 Sl 1SI- P-15b Si 0 ~ SRT review of pipe The valve was The pipe analysis, Accession #- EWR 96-045 SQ-001647 3/27/97 56 878A Pump R-1 analysis Evaluated - supported by the WE-1 00104, shows that the assigned to resolves Reactor Stress report Accession valve operator but valve will not be overstressed. document outlier.

Vessel #- WE-100104 not the valve body. resolution. NRC Injection In addition, the gap RAI asked for between the valve piping analysis.

body and the gravity Resolved.

support stanchion is not properly shimmed A, I 8 Sl 1SI- P-15a Si 0 - SRT review of pipe The valve was The pipe analysis, Accession # - EWR 96-045 SQ-001648 3/27/97 58 878B Pump Loop B analysis Evaluated - supported by the WE-100104, shows that the assigned to resolves Injection Stress report Accession valve operator but valve will not be overstressed. document outlier.

1. -WE-100104 not the valve body. resolution. NRC In addition, the gap RAI asked for between the valve piping analysis.

body and the gravity Resolved.

support stanchion is not properly shimmed A, I 8 Sl 1SI- P-15b Si 0 - SRT review of pipe The valve was The pipe analysis, Accession # - EWR 96-045 SQ-001649 3/27/97 60 878C Pump R-1 analysis Evaluated - supported by the WE-100104, shows that the assigned to resolves Reactor Stress report Accession valve operator but valve will not be overstressed. document outlier.

Vessel #- WE-100104 not the valve body. resolution. NRC Injection In addition, the gap RAI asked for between the valve piping analysis.

body and the gravity Resolved.

support stanchion is not properly shimmed A, I 8 Sl 1SI- P-15a Si 0 - SRT review of pipe The valve was The pipe analysis, Accession #- EWR96-045 SQ-001650 3/27/97 62 878D Pump Loop A analysis Evaluated - supported by the WE-1 00104, shows that the assigned to resolves Injection Stress report Accession valve operator but valve will not be overstressed. document outlier.

1. - WE-100104 not the valve body. resolution. NRC In addition, the gap RAI asked for between the valve piping analysis.

body and the gravity Resolved.

support stanchion is not properly shimmed

POINT BEACH NUCLEAR PLANT, UNIT 1 1200114-R-001 REVISION 0 B-24 Outlier Program Equip System Equip Noun Name Status at Time of SRT Outlier Description Interim Resolution Documented Status I Final Required Date No. Class ID Walkdown in 1993 in the USI A-46 Seismic Resolution Close Out Completed Evaluation Report to NRC A, I 10 VNAFW HX- Auxiliary Feed 0 - Rubber isolators fail. The air handling unit HX-66 is on the SSEL to EWR 96-046 SQ-001672. 5/15/99 64 66 Pump Area They do not have is mounted on maintain SW system integrity. assigned. MR 97- Outlier is Cooler sufficient shear and rubber vibration The air handling and air cooling 104 installed resolved.

tension capacity to isolators. The function is not required. The SW replacement transfer the anchor anchorage system engineer judged that a vibration isolators.

loads to the concrete calculation break in the attached 2" SW line Accepted 2/28/98.

expansion anchors. concluded that the would not significantly impact rubber isolators had service water to other essential insufficient capacity loads. The function of the air to transfer the handling unit will be evaluated anchorage loads to to determine if an anchorage the concrete upgrade is required.

expansion anchors.

A, I 10 VNAFW HX- Auxiliary Feed 0 -The Spring isolator The air handling unit HX-66A is on the SSEL to EWR 96-047 SQ-001888 12/14/00 65 66A Pump Area base plate yields. is mounted on spring maintain SW system integrity. assigned. MR 98- Outlier is Cooler vibration isolators. The air handling and air cooling 127 initiated. (RE: resolved.

The anchorage function is not required. The SW DNC) 2/11/99 -

calculation system engineer judged that a NeedWO. WO determined that the break in the attached 2" SW line 9808637is spring isolator base would not significantly impact replacing HX-66A plate will yield. service water to other essential cooling coils. Work loads. The function of the air complete.

handling unit will be evaluated to determine if an anchorage upgrade is required.

66 A, I 10 sw HX- Residual Heat 0 - Mounted on The air handling unit HX-98 is on the SSEL to EWR 96-048 SQ-001841. 9/19/00 98 Removal Neoprene pads. Pads is mounted on maintain SW system integrity. assigned. MR 97- Outlier is Pump Area need further eva I per rubber vibration The air handling and air cooling 105 installed. WO resolved.

Cooling Coil GIP Section 4.4. isolators. The function is not required. The SW 9807185 replaced Evaluation by S&A? anchorage system engineer judged that a HX-98 cooling 5/22/95 - During the bolt calculation break in the attached 2 1/2" SW coils.

tightness check on concluded that the line would not significantly 2/20/95, the concrete rubber isolators had impact service water to other expansion anchors for insufficient capacity essential loads. The function of the left rear rubber to transfer the the air handling unit will be vibration isolator were anchorage loads to evaluated to determine if an found to be never the concrete anchorage upgrade is required.

installed expansion anchors.

A, I 10 VNRC 1W- Containment 0 - No anchorage The air handling unit The unit was anchored during Fixed, MR 94-032 SQ-001651 9/29/94 67 4A Cavity Cooling Anchored during U1 R21 was found that same U1 R21 outage under installed new resolves Fan by TCM and ARB. unanchored.O- No modification MR 94-032. anchorage- outlier.

MR 94-032. anchorage 4/25/94.

Anchored during U1 R21 by TCM and ARB. MR 94-032.

POINT BEACH NUCLEAR PLANT, UNIT 1 12Q0114-R-001 ' REVISION 0 B-25 Outlier Program Equip System Equip Noun Name Status at Time of SRT Outlier Description Interim Resolution Documented Status I Final Required Date No. Class ID Walkdown in 1993 in the USI A-46 Seismic Resolution Close Out Completed Evaluation Report to NRC A, I 10 VNRC 1W- Containment 0 - No anchorage The air handling unit 68 4B Cavity Cooling Anchored during U1 R21 was found The unit was anchored during that same U1 R21 outage under Fixed, MR 94-032 installed new SQ-001652 resolves 9/29/94 Fan by TCM and ARB. unanchored.O- No modification MR 94-032. anchorage- outlier.

MR 94-032. anchorage 4/25/94.

Anchored during U1 R21 by TCM and ARB. MR 94-032.

A,I,H 11 VNCSR HX- Cable 0 - No Anchorage, The chiller unit is not The chiller is on the SSEL to 69 38A1 Spreading Motor on steel isolation anchored, the maintain SW integrity. A leak in EWR 96-052 assigned. Chiller SQ-001957 Outlier is 5/19/02

,A2,A Room Air springs. ISRS exceeds compressor motors the SW pipe would not HX-038A replaced. resolved.

3 Conditioning RS. New component are on springs, and significantly affect SW flow to MR 97-049*B Unit 7/13/94. It is the parent the seismic demand other essential loads. The installed new heat component of HX-38A 1, exceeds 1.5 x BS at HVAC room is designed to exchangers.

HX-38A2 and HX-38A3. the low frequency handle that flooding from a SW Equipment class peak. break. The chill water cooling changed from 21 to 11 function of the unit is not required. The function of the chiller unit will be evaluated to determine if an anchorage upgrade is required.

A,I,H 11 VNCR HX- Control Room 0 - No Anchorage, The chiller unit is not The chiller is on the SSEL to 70 38B1 Air Motor on steel isolation anchored, the maintain SW integrity. A leak in EWR 96-051 assigned. Chiller SQ-001962 Outlier is 8/15/02

,B2,B Conditioning springs. ISRS exceeds compressor motors the SW pipe would not HX-038B replaced. resolved.

3,B4 Unit RS. New component are on springs, and significantly affect SW flow to MR 97-049*C 7/13/94. It is the parent the seismic demand other essential loads. The installed new heat component of HX-38B1, exceeds 1.5 x BS at HVAC room is designed to exchangers.

HX-38B2, HX-38B3 and the low frequency handle that flooding from a SW HX-38B4. Equipment peak. break. The chill water cooling class changed from 21 function of the unit is not to 11 required. The function of the chiller unit will be evaluated to determine if an anchorage upgrade is required.

A, I 12 DA K-4B G-02 Edg 0 - Loose hand crank A loose hand crank Hand crank installed on a 71 Starting Air resting against it which was resting against bracket on the wall adjacent to Hand crank installed on a SQ-001822 Outlier is 4/21/95 Compressor may pose an interaction the air compressor the air compressor bracket on the wall resolved.

Motor Or hazard. 4/21/95- a posing an adjacent to the air Diesel hand crank mount has interaction hazard. compressor been installed on the wall adjacent to the compressor

POINT BEACH NUCLEAR PLANT, UNIT 1 1200114-R-001 REVISION 0 B-26 Outlier Program Equip System Equip Noun Name Status at Time of SRT Outlier Description Interim Resolution Documented Status I Final Required Date No. Class ID Walkdown in 1993 in the USI A-46 Seismic Resolution Close Out Completed Evaluation Report to NRC A, I 16 125V D-07 Station 0 - Interaction, The battery charger The battery charger does not 72 Battery CABINET IS NOT TIED is not attached to the contain essential relays, and MR 94-048 bolted D-07 to the old 2A-SQ-001938 Outlier is 12/13/00 Charger TO ADJACENT adjacent switchgear. there are 3 switchgear cubicles 05. wo 9904504. resolved.

CABINET, ALSO between the battery charger and BLOCK WALL MAY switchgear cubicle that contains GOVERN HCLPF. the essential relays. Therefore, EWR submitted 2/4/94 the battery charger and the for CSE to bolt battery switchgear are considered charger to adjacent seismically operable.

switchgear. MR 94-048 Modification Request MR 94-048 has be initiated to bolt these toQether.

A, I 16 125V D-08 Station 0- Interaction, The battery charger The battery charger does not MR 94-048 bolted 73 Battery CABINET IS NOT TIED is not attached to the contain essential relays, and D-08 to 1A-05.

SQ-001939 Outlier is 12/18/00 Charger TO ADJACENT adjacent switchgear. there are 3 switchgear cubicles wo 9504505. resolved.

CABINET, ALSO between the battery charger and BLOCK WALL MAY switchgear cubicle that contains GOVERN HCLPF. the essential relays. Therefore, EWR submitted 2/4/94 the battery charger and the for CSE to bolt battery switchgear are considered charger to adjacent seismically operable.

switchgear. MR94- Modification Request MR 94-048 048 has be initiated to bolt these together.

A, I 16 y DY- Red 125v 0- Interaction; The outlier is an The inverter does not contain MR 96-037 SQ-001867 74 OA Dc/120v Ac Mounted directly interaction. DY-OA any essential relays. It is IEEE assigned to move Outlier is 5/25/00 Alternate adjacent to 1C-167. The is mounted directly 344-1975 qualified. It is inverter to create a resolved.

Inverter cabinets are not adjacent to 1C-167. considered seismically operable gap between fastened together. P- The cabinets are not based on there being no inverter and relay REPORT fastened together. instances of inverter failure due cabinet. wo to impact in the earthquake 9805184.

experience database. The Installation inverter will be fastened to the complete.

adjacent cabinet.

A, I 16 y DY- Blue 125v 0 - Interaction; The outlier is an The inverter does not contain MR 96-037*A SQ-001868 75 OB Dc/120v Ac Mounted directly interaction. DY-OB any essential relays. It is IEEE assigned to move Outlier is 5/25/00 Alternate adjacent to 2C-156. The is mounted directly 344-1975 qualified. It is inverter to create a resolved.

Inverter cabinets are not adjacent to 2C-157. considered seismically operable gap between fastened together. P- The cabinets are not based on there being no inverter and relay REPORT fastened together. instances of inverter failure due cabinet. WO to impact in the earthquake 9805185.

experience database. The Installation inverter will be fastened to the complete adjacent cabinet.

POINT BEACH NUCLEAR PLANT, UNIT 1 1200114-R-001 ' REVISION 0 8-27 Outlier Program Equip System Equip Noun Name Status at Time of SRT Outlier Description Interim Resolution Documented Status I Final Required Date No. Class ID Walkdown in 1993 in the USI A-46 Seismic Resolution Close Out Completed Evaluation Report to NRC I 19 RH 1TE- Hx-11a Rhr 0 - Interaction. Pinned The outlier concern 78 622 Hx Outlet against pipe support. is interaction. The The piping analysis shows that the maximum expected pipe MR 96-036 assigned. MR 96-SQ-001823 Outlier is 7/21/97 Temperature Support has a 2" gap so TE is pinned against displacement at the TE is .13". 036 was cancelled. resolved.

Rtd pipe could move and a pipe support. The Therefore only slight bending of wo 9607885 shear or bend element. support has a 2" gap the TE is expected and it is repositioned the TE Needs EWR. so pipe could move considered seismically and conduit and and shear or bend operable. The temperature secured w/ Loctite.

element. element will be rotated to (RE: Andy Hoy) removed the interaction Completed 7/21/97 concern. The item has been walked down for the IPEEE only. Subsequent to the walkdown, it has been screened out using the Seismic PSA screeninQ criteria.

A,I,RG 20 MMS C Main Control 0- Interaction, adjacent An adjacent supply The supply cabinet was 79 1(2)C Boards supply cabinets not cabinet posed a attached to the back of 2C-03 Fixed, MR 94-021 bolted supply SQ-001824 Outlier is 8/24/94

-04 secured. EWR spatial interaction under modification MR 94-021. cabinets to the resolved.

submitted. 7/25/94- hazard. back of 1C-03 and Supply cabinets 2C-03.

secured. 1/18/95- MR 94-021 installed 6/9/94 resolves interaction concern. Item identified during MCB walkdown 12/90 - Overhead lights and duct above control room restrained by chains or light metal straps that are sometimes hooked with open ended hooks.

SRT not concerned that duct or lights pose a structural hazard, however, they may pose an operator (human iniurY) hazard.

POINT BEACH NUCLEAR PLANT, UNIT 1 1200114-R-001 REVISION 0 B-28 Outlier Program Equip System Equip. Noun Name Status at Time of SRT Outlier Description Interim Resolution Documented Status I Final Required Date No. Class ID Walkdown in 1993 in the USI A-46 Seismic Resolution Close Out Completed Evaluation Report to NRC 80 A, I 20 lOPS 1C- Turbine lops 0 - Doors are not 0 - Doors are not The cabinet does not contain wo 9607849 SQ-001825 1/20/97 75 Main Trip positively latched. T. positively latched. any essential relays, and the installed new Outlier is Panel Dykstra to submit MWR doors are fairly light weight handle - completed resolved.

after inspection. 6/19/95 therefore, significant damage is 1/20/97

- Need to discuss with not expected to occur. I & C will Steve Bowe to see if he be contacted to determine if the would rather install existing door latch can be used different handles or have or whether a new handle would I&C start using the key be preferred.

lock to latch the door.

9/23/96 - wo 9607849 A, I 20 MMS 1C- Plant Process 0 -1C-105 door binding, 82 105- I&C Cabinets not secured. Interaction The door on 1C-1 05 was identified as The cabinet was bolted to the back of 1C-03 under MR 94-Fixed, MR 94-021 bolted supply SQ-001827 completed.

8/24/94 114 - Supply cabinet binding and not 021. The door binding was cabinet to the back interference EWR being secured, checked by an I&C technician. of 1C-03. Checked submitted. 1/18/95- allowing it to impact The door does bind, but the door binding with MR 94-021 installed the cabinet.door binding does not prevent the I&C technician.

6/9/94 resolves binding, A adjacent door from closing. Technicians The door does interaction concern. supply cabinet must use an extra effort to bind, but the poses and ensure the door is shut. binding does not interaction concern. prevent the door from closing.

Technicians must use an extra effort to ensure the door is shut.

A, I 20 RP 1C- Plant Process 0- Interaction -Table in An adjacent supply The supply cabinet was 84 115- I&C Cabinets SE corner should be cabinet posed a attached to the back of 1C-03 Fixed, MR 94-021 bolted supply SQ-001831 completed.

8/24/94 133 secured or moved. spatial interaction under modification MR 94-021. cabinet to the back EWR submitted. hazard. of 1C-03.

1/18/95- MR 94-021 Accepted 7/28/94 installed 6/9/94 resolves interaction concern.

A, I 20 RP 1C- RpTrain A 0- ANCHOR DETAIL The anchor detail for Since the cabinet has 85 151- Relay Unknown. No specific the grout pad and anchorage as originally MR 95-007 upgraded the SQ-001832 Outlier is 12/2/97 155 Cabinets information on the grout the perimeter designed, it is considered anchorage- resolved.

pad to concrete floor channel is unknown. seismically operable. accepted 4/15/96 anchorage. Needs Modification request MR 95-007 EWR will upgrade the anchorage.

A, I 20 ESF 1C- Safeguards 0- ANCHOR DETAIL The anchor detail for Since the cabinet has MR 95-011 87 156- Train A Relay Unknown. No specific the grout pad and anchorage as originally cancelled, work SQ-001524 completed.

12/2/97 157 Cabinets information on the grout the perimeter designed, it is considered combined with MR pad to concrete floor channel is unknown. seismically operable.95-007. MR 95-anchorage. Modification request MR 95-011 007 upgraded the will upgrade the anchorage. anchorage-accepted 4/15/96

POINT BEACH NUCLEAR PLANT, UNIT 1 1200114-R-001 REVISION 0 B-29 Outlier Program Equip System Equip Noun Name Status at Time of SRT Outlier Description Interim Resolution Documented Status I Final Required Date No. Class ID Walkdown in 1993 in the USI A-46 Seismic Resolution Close Out Completed Evaluation Report to NRC A, I ESF 1C- Safeguards 0- Interaction; The outlier is an No "bad actor" relays are MR 96-037 SQ-001869 5/25/00 89 20 158/1 Train BAnd Mounted directly Interaction. The located in the cabinets. The assigned to move Outlier is 66/16 Mise Relay adjacent to inverter DY- cabinets are relays in the cabinets have a inverter to create a resolved.

7 Cabinets OA. The cabinets are mounted directly seismic capacity of at least 4 gap between not fastened together. adjacent to inverter g's. Therefore, they are inverter and relay P-REPORT Provide DY-OA. The considered seismically cabinet. WO Mod Package cabinets are not operable. The cabinet will be 9805185.

fastened together. fastened to the adjacent Installation inverter. complete A, I 20 RP 1C- RpTrain B 0- ANCHOR DETAIL The anchor detail for Since the cabinet has MR 95-009 SQ-001843 12/2/97 90 161- Relay Logic Unknown. No specific the grout pad and anchorage as originally cancelled, work Outlier is 165 Cabinet (Red) information on the grout the perimeter designed, it is considered combined with MR resolved.

pad to concrete floor channel is unknown. seismically operable.95-007. MR 95-007 anchorage. Needs Modification request MR 95-009 upgraded the EWR will upgrade the anchorage. anchorage-accepted 4/15/96 A, I 20 COMP C- Computer 0 - Line Printer adjacent Line Printer, LP-300, C-178-179 are computer 12/30/98 - Have SQ-001834 12/30/98 93 178- Input Mux to cabinet is kept on the floor cabinets contain primarily solid inspected the Outlier is 179 adjacent to the state and circuit board Computer Room on resolved.

cabinet. components. There are no numerous essential relays in the cabinets. occasions since the The cabinets are considered USI A-46 seismically operable. I&C will walkdown. The store the printer in a different printer has been location and have it adjacent to relocated. No the cabinets only when being interaction hazards used. were identified.

95 A,I,C 21 cc 1T- Component 0 - Oversized anchor The saddle There are large washers MR 94-091*C SQ-001836 8/5/96 12 Cooling Surge bolt holes (2.25" x 1.18") anchorage on both between the anchorage nut and installed 1/2" steel Outlier is Tank identified from WEST ends of the tank has the oval holes. Therefore, some plate under each of resolved.

685J114. Anchor bolts oversized anchor load will be transferred to all of the nuts on the are 1" diameter. Too bolt holes (2.25" x the anchor bolts. In addition, the south side of the much clearance to say 1.18") identified from attached piping will help in tank. The plate is seismic load is WEST 685J114. The restraining the tank. Therefore, welded to the transferred to enough anchor bolts are 1" the tanks are considered saddle. The anchor bolts. diameter. Therefore, seismically operable. The installation was there is too much anchorage will be upgraded with checked 12/3/97 clearance to say a structural member between seismic load is the tank base and the anchor transferred evenly to bolt.

enough anchor bolts

POINT BEACH NUCLEAR PLANT, UNIT 1 1200114-R-001 ' REVISION 0 B-30 Outlier Program Equip System Equip Noun Name Status at Time of SRT Outlier Description Interim Resolution Documented Status I Final Required Date No. Class ID Walkdown in 1993 in the USI A-46 Seismic Resolution Close Out Completed Evaluation Report to NRC A, I 21 Sl 1T- Refueling 0- The tank does not The tank has been analyzed In WE NRC RAI SQ-001999 6/6/02 97 13 Water Storage ANALYSIS/REINFORC pass the screening using a finite element analysis response NPL 97- resolves TankW/6 EMENT 7/25/94- criteria of Section 7 [23]. 0450, page 5 of 22, this outlier Immersion Received DRAFT of the GIP. WE stated that the Htrs analysis from S& A design margin from showing RWST has the A-46 analysis is sufficient capacity. not sufficient.

EWR 97-169 assigned. MR 99-040 upgraded the RWST.

A, I 21 DA T- G-02 Edg 0 - Anchor - cracked The grout under the An inspection subsequent to the WO- 9501221 SQ-001838 5/23/97 99 61F Starting Air grout foot of one of the air seismic verification walkdown completed 5/23/97 resolves the Receiver receiver tank legs is found a steel spacer plate under - installed new outlier cracked. the leg of the tank. Therefore grout the grout is not structural and the tank is considered seismically operable. The leg will be re-grouted.

A, I 22 AUX Pab 8' Cable LAR 9 is an Work completed SQ-001714 8/1/00 100 8FTA & Conduit OUTLIER because under MR 96-022. resolves the REA Raceways it does not meet the Post installation outlier requirements of walkdown Section 8.0 of the complete. WO GIP. See S&A's 9808941 LAR - Cable Tray and Conduit Supports Report, 91C2696-C-018.

A, I 22 SPR Csr Cable & LAR 3 & LAR 4 are MR 96-080 created SQ-001881 9/25/00 101 EADI Conduit OUTLIER(s) to upgrade cable Outlier is NGR Raceways because it does not tray supports in the resolved.

M meet the CSR (RE: DNC).

requirements of Installation Section 8.0 of the complete GIP. See S&A's LAR - Cable Tray and Conduit Supports Report, 91 C2696-C-O 18.

POINT BEACH NUCLEAR PLANT, UNIT 1 1200114-R-001 REVISION 0 B-31 Outlier Program Equip System Equip Noun Name Status at Time of SRT Outlier Description Interim Resolution Documented Status I Final Required Date No. Class ID Walkdown in 1993 in the USI A-46 Seismic Resolution Close Out Completed Evaluation Report to NRC A, I 22 U1C2 U1c 21' Cable 0 - Loose base clip One outlier was DNC & TJD1 SQ-001388 6/4/98 102 1FTA & Conduit angle noted on the floor-to- inspected & resolves REA Raceways ceiling hanger east tightened the base outlier of the access hatch clip angle 6/4/98.

near location 8 (as The CEA turned in marked on liner < 1/4 turn and wall). The base clip satisfied the angle on one side is requirements of a loose and should be tightness check.

tiQhtened.

A, I 22 U1C4 U1c 46' Cable 0 - Cables not tied to (1) Vertical trays Resolved during SQ-001549 6/4/98 103 6FTA & Conduit tray 1VR01 and 1VQ01 U1 R24. Verified resolves REA Raceways had larges cable during walkdown. outlier bundles (aka wo 9808624 "pigtails") from wall penetrations that were not tied to vertical tray and are free to swing, see figure 12.

A, I 22 U1C4 U1c46' Cable 0 - Cables not tied to (2) Horizontal tray Resolved during SQ-001549 6/4/98 104 6FTA & Conduit tray 1VA04 at U1 R24. Verified resolves REA Raceways penetration has during walkdown. outlier cable pigtail hanging wo 9808624 out of tray and not restrained to or within the tray.

There appears to be other tray bundles with similar problems behind it, see figure 13.

POINT BEACH NUCLEAR PLANT, UNIT 1 1200114-R-001 REVISION 0 B-32 Outlier Program Equip System Equip Noun Name Status at Time of SRT Outlier Description Interim Resolution Documented Status I Final Required Date No. Class ID Walkdown in 1993 in the USI A-46 Seismic Resolution Close Out Completed Evaluation Report to NRC A, I 1 480V 18- 480v Motor SAT End cabinet on 4/20/95 - Attempt NOT AN 4/20/95 106 32 Control Center right hand side, base to turn the nut OUTLIER-Pab channel CEA fastening during the bolt Resolved in Safeguards nuts are loose. Need to tightness test was the be tightened. T. Dykstra unsuccessful. anchorage to develop CEA torque Application of analysis on tightness procedure, AI torque >installation the original Bayer to review. Then torque was not SEWS submit WO to do torque desirable due to tightness check. WO possibility of 9411729. Maintenance breaking the bolt.

Since the bolt is loaded in shear only, this is considered acceptable A,I,RG 3 4.16KV 1A- 4.16 KvBus SAT WELD Weld inspection NOT AN 7/3/02 107 05 Switchgear QUALITY IN completed, used OUTLIER-(Safeguards) QUESTION, results to adjust resolved w/

Recommend thorough anchorage capacity weld weld inspection. T. in the anchorage inspection Dykstra to check with calculation and QA about weld 91 C2696-C-016. anchorage inspections calc.

A,I,RG 3 4.16KV 1A- 4.16 KvBus PO - Not fastened to MR 94-048 SQ-001939 12/18/00 109 06 Switchgear adjacent D-08 battery connected cabinets Outlier is (old) (Safeguards) charger. WELD together. WO resolved.

QUALITY IN 9904505.

QUESTION, Recommend thorough weld inspection. T.

Dykstra to check with QA about weld inspections. 11/7/94-Renamed to 1A-06 (old).

The old 1A-05 and old 1A-06 will be hard tied t~g_ether

POINT BEACH NUCLEAR PLANT, UNIT 1 1200114-R-001 REVISION 0 B-33 Outlier Program Equip System Equip Noun Name Status at Time of SRT Outlier Description Interim Resolution Documented Status I Final Required Date No. Class ID Walkdown in 1993 in the USI A-46 Seismic Resolution Close Out Completed Evaluation Report to NRC 111 I,RG 7 sc 1SC- Pzr Steam PO- Valve on 3/8" The AOV body is This valve was not declared an MR 96-035 SQ-001772 1/14/00 966A Sample tubing. Valve body mounted to a outlier. This valve is normally installed operator resolves Containment clamped to support shelf support shelf by 2 U- closed and is required to stay supports. this issue Isolation by 2 U-bolts. May not bolts in friction. The closed in the event of an SSE.

be able to resist valve is mounted on Rather than analyzing the U-bolt moment. Need material a 3/8" line. If the U- support's capacity, the SRT 11/11/94 Update- bolts slip, the recommended installing an Material info provided to potential exists for operator support as a prudent S&A. Valve status the line to be fix. The U changed to Outlier overstress.

based on walkdown 7/26/94. SRT recommends operator support 112 I,RG 7 sc 1SC- Pzr Liquid PO- Valve on 3/8" The AOV body is This valve was not declared an MR 96-035 SQ-001773 1/14/00 9668 Sample tubing. Valve body mounted to a outlier. This valve is normally installed operator resolves Containment clamped to support shelf support shelf by 2 U- closed and is required to stay supports. this issue Isolation by 2 U-bolts. May not bolts in friction. The closed in the event of an SSE.

be able to resist valve is mounted on Rather than analyzing the U-bolt moment. Need material a 3/8" line. If the U- support's capacity, the SRT 11/11/94 Update- bolts slip, the recommended installing an Material info provided to potential exists for operator support as a prudent S&A. Valve status the line to be fix. The U changed to Outlier overstress.

based on walkdown 7/26/94. SRT recommends operator support 113 A,l,RG 7 sc 1SC- Rc Hot Leg PO -Valve on 3/8" The AOV body is This valve was not declared an MR 96-035 SQ-001774 1/14/00 966C Sample tubing. Valve body mounted to a outlier. This valve is normally installed operator resolves clamped to support shelf support shelf by 2 U- open and is required to close in supports. this issue by 2 U-bolts. May not bolts in friction. The the event of an SSE. Rather be able to resist valve is mounted on than analyzing the U-bolt moment. Need material a 3/8" line. If the U- support's capacity, the SRT 11/11/94 Update- bolts slip, the recommended installing an Material info provided to potential exists for operator support as a prudent S&A. Valve status the line to be fix. The U1 configuration changed to Outlier overstress.

based on walkdown 7/26/94. SRT recommends operator support

POINT BEACH NUCLEAR PLANT, UNIT 1 1200114-R-001 REVISION 0 B-34 Outlier Program Equip System Equip Noun Name Status at Time of SRT Outlier Description Interim Resolution Documented Status I Final Required Date No. Class ID Walkdown in 1993 in the USI A-46 Seismic Resolution Close Out Completed Evaluation Report to NRC 115 A,I,C 8 cc 1CC- T-12 Cc Surge PO- pipe has NOT AN OUTLIER NOT AN 3/30/01 815 Tank insufficient supports - - CCW Upgrade OUTLIER-Emergency 11/11/94 update- identified these Resolved Makeup Water STATUS changed to valves as having on original Inlet outlier. Valves also insufficient support. SEWS identified as having - MR 94-091 insufficient pipe support installed valve adjacent to valve during support. Verified the CCW Upgrade installation 12/3/97 piping walkdowns. PO -

3g required to qualify valve yoke. Trapeze supports may allow valve yoke to swing resulting in possible pipe failure 117 A, I 8 sw SW- K-3a Sa SAT Attached Resolved NOT AN 10/26/94 2832 Compressor conduit is very flexible OUTLIER-A-S Inlet Solenoid and should be Resolved restrained. Check with on original Frank Mueller about SW SEWS piping replacement.

Rewalked 10/26/94 by SR StAmour and W Djordjevic. Determined flexibility was not a problem.

A, I 15 125V D-05 125v De SAT- 0-SPACER, Need Resolved NOT AN 118 Station battery cell type OUTLIER-1/18/95 Battery information. EWR Resolved submitted 2/4/94 for on original ESE to install styrofoam SEWS bead spacers. 7/25/94-EWR cancelled. T.

Dykstra to submit MWR to install spacers.

1/18/95 - Qual report shows batteries shake table tested in same

POINT BEACH NUCLEAR PLANT, UNIT 1 1200114-R-001 REVISION 0 B-35 Outlier Program Equip System Equip Noun Name Status at Time of SRT Outlier Description Interim Resolution Documented Status I Final Required Date No. Class ID Walkdown in 1993 in the USI A-46 Seismic Resolution Close Out Completed Evaluation Report to NRC A, I 15 125V D-06 125v De SAT- 0-SPACER.

119 Station EWR submitted 2/4/94 Resolved NOT AN OUTLIER-1/18/95 Battery for ESE to install Resolved styrofoam bead spacers. on original 7/25/94 - EWR SEWS cancelled. T. Dykstra to submit MWR to install spacers. 1/18/95- Qual report shows batteries shake table tested in same configuration at PBNP. No addition A, I 15 125V D- Swing Station SAT- 0-SPACER. Resolved NOT AN 1/18/95 120 305 Battery EWR submitted 2/4/94 OUTLIER-for ESE to install Resolved styrofoam bead spacers. on original 7/25/94 - EWR SEWS cancelled. T. Dykstra to submit MWR to install spacers. 1/18/95- Qual report shows batteries shake table tested in same configuration at PBNP. No addition 121 A,l,C 18 cc Fl- K-1a Waste SAT Anchor Bolted Resolved NOT AN 7/94 643 Gas CompCc to Block Wall- no thru OUTLIER-Return Flow bolts T. Dykstra to Resolved Indicator check scope of block on original wall program. Tug tested SEWS by B.O. Sasman & W.

Djordjevic 7/94 OK.

122 A,I,C 18 cc Fl- K-1b Waste SAT Anchor Bolted Resolved NOT AN 7/94 645 Gas Comp Cc to Block Wall - no thru OUTLIER-Return Flow bolts T. Dykstra to Resolved Indicator check scope of block on original wall program. Tug SEWS tested by B.O. Sasman

& W. Djordjevic 7/94

.- OK .

POINT BEACH NUCLEAR PLANT, UNIT 1 1200114-R-001 REVISION 0 B-36 Outlier Program Equip System Equip Noun Name Status at Time of SRT Outlier Description Interim Resolution Documented Status I Final Required Date No. Class ID Walkdown in 1993 in the USI A-46 Seismic Resolution Close Out Completed Evaluation Report to NRC I,RG 18 AF LT- T-24b Cst 0 - Interaction, D Deleted from SSEL Deleted 1/18/95 123 4039 Level POTENTIAL FOR from SSEL Transmitter BLOCK WALL TO FALL ON COMPONENT. T.

Dykstra to evaluate function of LT. 1/18/95

- LTs removed from A-46 list. Still IPEEE and RG 1.97.

I,RG 18 AF LT- T-24a Cst 0 - Interaction, Deleted from SSEL Deleted 1/18/95 124 4040 Level POTENTIAL FOR from SSEL Transmitter BLOCK WALL TO FALL ON COMPONENT. T.

Dykstra to evaluate function of LT. 1/18/95

- LTs removed from A-46 list. StiiiiPEEE and RG 1.97.

I,RG 18 AF LT- T-24b Cst 0- Interaction, Deleted from SSEL Deleted 1/18/95 125 4041 Level POTENTIAL FOR from SSEL Transmitter BLOCK WALL TO FALL ON COMPONENT. T.

Dykstra to evaluate function of LT. 1/18/95

- LTs removed from A-46 list. StiiiiPEEE and RG 1.97.

I,RG 18 AF LT- T-24a Cst 0 - Interaction, Deleted from SSEL Deleted 1/18/95 126 4038 Level POTENTIAL FOR from SSEL Transmitter BLOCK WALL TO FALL ON COMPONENT. T.

Dykstra to evaluate function of LT. 1/18/95-LTs removed from A-46 list. Still IPEEE and RG 1.97.

I,RG 18 Sl 1PT- T-34b Si SAT- resolved using Resolved on NOT AN 6/28/95 129 936 Accumulator Unistrut deflection calc. SEWS using a OUTLIER-Pressure 0 - Cable tray support Unistrut deflection Resolved Transmitter within 3/4" of PT calc. on original SEWS

POINT BEACH NUCLEAR PLANT, UNIT 1 1200114-R-001 ' REVISION 0 B-37 Outlier Program Equip System Equip Noun Name Status at Time of SRT Outlier Description Interim Resolution Documented Status I Final Required Date No. Class ID Walkdown in 1993 in the USI A-46 Seismic Resolution Close Out Completed Evaluation Report to NRC 130 A,I,C 18 sc 1RK- Primary Plant SAT Interim outlier 4/25/95 - phone NOT AN 4/25/95 20 Sample Room until anchorage is conversation with OUTLIER-Rack checked. Interaction - Wally Djordjevic - Resolved adjacent sample sink determined that on original has no visible since the only SEWS anchorage function of the rack was to support flow indicator and that the sample tubing is isolated upstream of rack and there is no requirement to operate the valves on the rack.

POINT BEACH NUCLEAR PLANT, UNIT 1 1200114-R-001, REVISION 0 B-38 ATTACHMENT A Seismic Walkdown Eauioment List Unit 1 & SFP (SWEL)

SWEL RISK N UNIT SYS EQUIP WALK EQUIP# EQUIP NAME 1 2 3 4 5 TRN IPEEE LOCATION DESC E CODE CLASS BY Equip.

w AREA Enhanced SWEL 1-1 y 1 AF 5 1 1P-029 AUX FEEDWATER TURBINE-DRIVEN PUMP X X X A S/CB/AFP RM 1P-29 CUB SWEL 1-1 0 AF 5 1 P-03SA AUX FEEDWATER MOTOR-DRIVEN PUMP X X X A S/CB/AFP RM P-3SA CUB SWEL 1-1 y 1 AF 7 1AF-04002 1P-29 AFP MINI RECIRC CONTROL X X X A S/CB/AFP RM 1P-29 CUB 1

SWEL 1-1 0 AF 7 1 AF-04007 P-3SA SSGP MINI RECIRC CONTROL X X X A S/CB/AFP RM P-3SA CUB SWEL 1-1 0 AF 7 1 AF-04012 P-3SA SSGP DISCHARGE CONTROL X X X A S/CB/AFP RM P-3SA CUB SWEL 1-1 y 0 125V 14 D-63 125V DC DISTRIBUTION PANEL X X X X X A S/CB/AFP RM 1P-29 CUB 1

1RK-S9 SWEL 1-1 0 AF 1S 1 RK-25A P-3SA SSGP INSTRUMENTATION RACK X X X A S/CB/AFP RM P-3SA CUB SWEL 1-1 y 1 AF 21a 1T-212 1P-29 AFP MINI RECIRC lA 1AF-4002 BACKUP X X X A S/CB/AFP RM 1

ACCUMULATOR SWEL 1-1 1 AF Sa 1AF-04000 1P-29 AFP DISCHARGE 1HX-1B SG INLET X X X A S/CB/AFP RM 1P-29 CUB 1

ISOLATION MOV SWEL 1-1 1 AF Sa 1AF-04001 1P-29 AFP DISCHARGE 1HX-1A SG INLET X X X A S/CB/AFP RM 1P-29 CUB 1

ISOLATION MOV SWEL 1-1 1 AF Sa 1 1AF-04006 1P-29 AFP SUCTION FROM SERVICE WATER X X X A S/CB/AFP RM 1P-29 CUB SWEL1-1 0 AF Sa AF-04009 P-3SA SSGP SUCTION FROM SERVICE X X X A S/CB/AFP RM P-3SA CUB 1

WATER SWEL 1-1 y 0 AF Sa AF-04023 P-3SA SSGP DISCHARGE TO 1HX-1A STEAM X X X A S/CB/AFP RM P-3SA CUB 1

GENERATOR SWEL 1-1 1 MS Sb 1 1MS-02090 1P-29 AFP BEARING COOLING INLET X X X A S/CB/AFP RM SWEL 1-1 y 1 4SOV 2 9 1B-03 4SOV SAFEGUARDS LOAD CENTER X X X X X A X 26/CB/CSR SWEL 1-1 y 1 4SOV 2 9 1B-04 4SOV SAFEGUARDS LOAD CENTER X X X X X B X 26/CB/CSR SWEL 1-1 y 1 4SOV 4 9 1X-13 1B-03 STATION SERVICE TRANSFORMER X X X X X A X 26/CB/CSR SWEL 1-1 y 1 4SOV 4 9 1X-14 1B-04 STATION SERVICE TRANSFORMER X X X X X B X 26/CB/CSR SWEL 1-1 1 y 14 1Y-203 WHITE 120V INVERTER DISTRIBUTION X X X X X A 26/CB/CSR WEST WALL 9

PANEL SWEL 1-1 y 0 125V 14 9 D-12 125V DC DISTRIBUTION PANEL X X X X X A 26/CB/CSR EAST SWEL 1-1 y y 0 125V 14 9 D-14 125V DC DISTRIBUTION PANEL X X X X X B 26/CB/CSR EAST SWEL 1-1 1 y 16 9 1DY-01 RED 125V DC/120V AC INVERTER X X X X X A 26/CB/CSR SWEL 1-1 0 y 16 DY-OB BLUE 125V DC/120V AC ALTERNATE X X X X X B X 26/CB/CSR 9

INVERTER SWEL 1-1 y 1 sw 7 s SW-00012A HX-12A CC HX OUTLET TEMPERATURE X 0 46/PAB/CC HX AREA CONTROL

POINT BEACH NUCLEAR PLANT, UNIT 1 1200114-R-001, REVISION 0 B-39 SWEL RISK N UNIT SYS EQUIP WALK EQUIP# EQUIP NAME 1 2 3 4 5 TRN IPEEE LOCATION DESC E CODE CLASS BY Equip.

w AREA Enhanced SWEL 1-1 y 0 sw 7 s SW-00012B HX-12B CC HX OUTLET TEMPERATURE X 0 46/PAB/CC HX AREA CONTROL SWEL 1-1 y y 0 sw 7 s SW- HX-12C CC HX OUTLET TEMPERATURE X 0 46/PAB/CC HX AREA 00012C CONTROL SWEL 1-1 1 cc 19 s 1TE-00621 HX-12A/B CC HX OUTLET HEADER X X X 0 46/PAB/CC HX AREA TEMPERATURE RTD SWEL 1-1 y 1 cc 21a s 1T-012 COMPONENT COOLING SURGE TANK X X X 0 46/PAB/CC HX AREA SWEL 1-1 y 1 cc 21b s 1HX-012A COMPONENT COOLING WATER HEAT X X X 0 46/PAB/CC HX AREA EXCHANGER SWEL 1-1 1 MS Sa 1MS-02019 HX-1B SG HEADER P-29 AFP STEAM SUPPLY X X X X A 46/PAB/BAST AREA S s MOV SWEL 1-1 1 MS Sa 1MS-02020 HX-1A SG HEADER P-29 AFP STEAM SUPPLY X X X X A 46/PAB/BAST AREA S s MOV SWEL 1-1 1 y 14 1-43/Y-01 1Y-01 RED 120V AC VITAL INST PNL PWR X X X X X A 44/CB/CR WEST 10 SUP TRANSFER SW SWEL 1-1 1 y 14 1-43/Y-02 1Y-02 BLUE 120V AC VITAL INST PNL PWR X X X X X B 44/CB/CR WEST 10 SUP TRANSFER SW SWEL 1-1 y 0 125V 14 10 D-16 125V DC DISTRIBUTION PANEL X X X X X B 44/CB/CR SOUTH SWEL 1-1 y y 0 125V 14 D-17 125V DC DISTRIBUTION PANEL X X X X X A 44/CB/CR SOUTH 10 SWEL 1-1 y 0 125V 14 10 D-1S 125V DC DISTRIBUTION PANEL X X X X X B 44/CB/CR NORTH SWEL 1-1 1 MMS 20 1 C-105 SECONDARY SYSTEM POWER SUPPLIES X X X 0 44/CB/CR 10 PANEL SWEL 1-1 y 0 FO 5 26 P-206A G-01 EDG FUEL OIL TRANSFER PUMP X X X X X A 2S/DGB/G-01/2 FOTP RM SWEL 1-1 y 0 DG 9 33 W-1S1A1 G-03 EDG HX-265A RADIATOR FAN X X X X X B 50/DGB/G-03 RADTR RM SWEL 1-1 y 0 DG 9 W-1S1A2 G-03 EDG HX-265A RADIATOR FAN X X X X X B 50/DGB/G-03 RADTR RM 33 SWEL 1-1 y y 0 VNDG 9 W-1S3B G-03 EDG RM SMALL CAPACITY EXHAUST X X X X X B 50/DGB/G-03 FAN RM 34 FAN SWEL 1-1 y y 0 VNDG 9 W-1S3C G-03 EDG RM LARGE CAPACITY EXHAUST X X X X X B 50/DGB/G-03 FAN RM 34 FAN SWEL 1-1 y 0 125V 14 37 D-2S G-03 EDG DC DISTRIBUTION PANEL X X X X X B 2S/DGB/G-03 SWGR RM SWEL 1-1 y y 0 DG 17 3S G-03 EMERGENCY DIESEL GENERATOR X X X X X B 2S/DGB/G-03 RM SWEL 1-1 y 0 DG 20 37 C-OS1 G-03 EDG CONTROL PANEL X X X X X B 2S/DGB/G-03 SWGR RM SWEL 1-1 y 0 DA 21a 3S T-170A G-03 EDG STARTING AIR RECEIVER X X X X X B 2S/DGB/G-03 RM SWEL 1-1 y 0 DG 17 42 G-01 EMERGENCY DIESEL GENERATOR X X X X X A S/CB/G-01 RM SWEL 1-1 0 VNDG 20 42 C-032 G-01 EDG EXHAUST FAN CONTROL PANEL X X X X X A S/CB/G-01 RM S WALL SWEL 1-1 0 DG 20 42 C-034 G-01 EDG ALARM AND ELECTRICAL PANEL X X X X X A S/CB/G-01 RM W WALL SWEL 1-1 0 DG 20 42 C-034A G-01 EDG LOCAL TRANSFER PANEL X X X X X A S/CB/G-01 RM W WALL

POINT BEACH NUCLEAR PLANT, UNIT 1 1200114-R-001, REVISION 0 B-40 SWEL RISK N UNIT SYS EQUIP WALK EQUIP# EQUIP NAME 1 2 3 4 5 TRN IPEEE LOCATION DESC E CODE CLASS BY Equip.

w AREA Enhanced SWEL 1-1 0 DG 20 C-07S G-01 EDG DC POWER TRANSFER CONTROL X X X X X A S/CB/G-01 RM W WALL 42 PANEL SWEL 1-1 0 FO 21a 42 T-031A G-01 DIESEL GENERATOR DAY TANK X X X X X A S/CB/G-01 RM SWEL 1-1 0 DA 21a T-060B G-01 EDG STARTING AIR RECEIVER (RIGHT X X X X X A S/CB/G-01 RM 42 BANK)

SWEL 1-1 0 DA 21a T-060C G-01 EDG STARTING AIR RECEIVER (RIGHT X X X X X A S/CB/G-01 RM 42 BANf9_

SWEL 1-1 0 DA 21a T-060E G-01 EDG STARTING AIR RECEIVER (LEFT X X X X X A S/CB/G-01 RM 42 BANK)_

SWEL 1-1 0 DA 21a T-060F G-01 EDG STARTING AIR RECEIVER (LEFT X X X X X A S/CB/G-01 RM 42 BANK)

SWEL 1-1 0 FO Sa F0-03930 T-31A G-01 EDG DAY TANK INLET SECOND X X X X X A S/CB/G-01 RM 42 OFF ISOLATION SWEL 1-1 y 2 4SOV 1 2B42- 2B4212B-BS11M (D-109) CHGR NRM/ALT XFR X X X X X B 26/PAB/INVERT RM WEST 47 4212B SWITCH CONTACTOR SWEL 1-1 0 VNBI 10 W-OS5 PAB BATTERY AND INVERTER ROOM VENT X X X X X A 35/PAB/D-106 ROOF 4

FAN SWEL 1-1 1 y 14 1-S3/DY-03 1DY-03 WHITE INVERTER STATIC X X X X X A 26/PAB/INVERT RM WEST 7

TRANSFER SWITCH SWEL 1-1 0 125V 14 7 D-03 125V DC DISTRIBUTION PANEL X X X X X A 26/PAB/INVERT RM WEST SWEL 1-1 y 1 4.16K 3 1A-05 4.16 KV BUS SWITCHGEAR (SAFEGUARDS) X X X X X A S/CBNSG RM 21 v

SWEL 1-1 y 0 125V 15 6 D-105 125V DC STATION BATTERY X X X X X A 35/PAB/D-1 05 BATT RM SWEL 1-1 1 y 16 7 1DY-03 WHITE 125V DC/120V AC INVERTER X X X X X A 26/PAB/INVERT RM WEST SWEL 1-1 0 125V 16 7 D-107 D-105 DC STATION BATTERY CHARGER X X X X X A 26/PAB/INVERT RM WEST SWEL 1-1 0 y 16 DY-OC WHITE 125V DC/120V AC INVERTER X X X X X A 26/PAB/INVERT RM WEST 7

SWEL 1-1 0 VNBI 20 5 C-022 BATTERY ROOM HVAC CONTROL PANEL X X X X X A 26/PAB/NORTH SWEL 1-1 y 1 4SOV 1 1B312A- 1P-1 OA RHR PUMP NORMAUALT TRANSFER X X X X X A S/PAB/COL P-11 14 BS55B SWITCH SWEL 1-1 y 1 cc 5 20 1P-011A COMPONENT COOLING WATER PUMP X X X A S/PAB/CC PUMP AREA SWEL1-1 1 Sl 5 19 1P-014A CONTAINMENT SPRAY PUMP X A S/PAB/SPRAY PUMP AREA SWEL 1-1 1 Sl 5 19 1P-014B CONTAINMENT SPRAY PUMP X B S/PAB/SPRAY PUMP AREA SWEL 1-1 y 1 Sl 5 19 1P-015A SAFETY INJECTION PUMP X X X X X A S/PAB/SI PUMP AREA SWEL 1-1 y y 1 AF 5 1P-053 UNIT 1 AUX FEEDWATER MOTOR-DRIVEN X X X B S/PAB/1P-53 AFP RM 41 PUMP SWEL 1-1 y 1 AF 21a T-224B 1AF-4073B/1AF-4074B AFP RECIRC X X X B S/PAB/1P-53AFP RM 41 ISOLATION lA ACCUMULATOR SWEL 1-1 y 1 AF Sa 1AF-04067 1P-53 AFP SERVICE WATER SUPPLY X X X B S/PAB/1P-53 AFP RM 41 ISOLATION

POINT BEACH NUCLEAR PLANT, UNIT 1 1200114-R-001, REVISION 0 8-41 SWEL RISK N UNIT SYS EQUIP WALK EQUIP# EQUIP NAME 1 2 3 4 5 TRN IPEEE LOCATION DESC E CODE CLASS BY Equip.

w AREA Enhanced SWEL 1-1 1 Sl 8a 19 1SI-00825A T-13 RWST OUTLET TO P-15AIB Sl PUMP X X X X X A 8/PAB/SPRAY PUMP AREA SWEL 1-1 1 Sl 8a 19 1SI-00825B T-13 RWST OUTLET TO P-15AIB Sl PUMP X X X X X B 8/PAB/SPRAY PUMP AREA SWEL 1-1 y 1 Sl 8a 1SI-00857A HX-11A RHR HXOUTLETTO P-15A Sl PUMP X X X X X A 8/PAB/SI PUMP AREA 19 SUCTION SWEL 1-1 y 1 Sl 8a 19 1SI-00896A P-15A Sl PUMP SUCTION X X X X X A 8/PAB/SI PUMP AREA SWEL 1-1 y 1 AF 8b 41 AF-04073B 1P-53 AFP RECIRCULATION ISOLATION X X X B 8/PAB/1P-53 AFP RM SWEL 1-1 y 1 cv 5 17 1P-002A CHARGING PUMP (Pump Only as Pressure X X X A 8/PAB/U1 CHG PUMP RM Boundary)

SWEL 1-1 1 cv 7 13 1CV-00142 CHARGING LINE FLOW CONTROL X X X 0 8/PAB/PIPEWAY #1 SWEL 1-1 y 1 cv 8a 18 1CV- 1P-2A-C CHARGING PUMP REFUELING X X X A 8/PAB/U1 CHG PUMP AREA 00112B WATER SUCTION SWEL 1-1 y 1 Sl 8a 13 1SI-00866A COLD LEG INJECTION LINE ISOLATION X X X X X A 8/PAB/PIPEWAY #1 SWEL 1-1 y 1 Sl 8a 13 1SI-00866B CORE DELUGE INJECTION LINE ISOLATION X X X X X B 8/PAB/PIPEWAY #1 SWEL 1-1 y 1 RH 5 2 1P-010A RESIDUAL HEAT REMOVAL PUMP X X X X X A X -19/PAB SWEL 1-1 y 1 RH 5 43 1P-010B RESIDUAL HEAT REMOVAL PUMP X X X X X B X -19/PAB SWEL 1-1 1 RH 7 3 1RH-00624 HX-11A RHR HX OUTLET CONTROL X X X X X A -5/PAB/EAST WALL OVHD SWEL 1-1 1 RH 7 3 1RH-00625 HX-11B RHR HX OUTLET CONTROL X X X X X B -5/PAB/EAST WALL OVHD SWEL 1-1 1 VNCC 9 W-001A1 CONTAINMENT ACCIDENT RECIRCATION X A 66/U1 C/NORTH 53 FAN SWEL 1-1 1 PACV 19 54 TE-03292 EL 66' U1C TEMPERATURE ELEMENT X 0 66/U1C/NE QTR SWEL 1-1 1 Sl 21a 55,56 T-034A SAFETY INJECTION ACCUMULATOR X X X A 21/U1C/SW QTR SWEL 1-1 1 cv 21b 57 HX-004 EXCESS LETDOWN HEAT EXCHANGER X 0 21/U1C SWEL 1-1 y 0 sw 6 27 P-032A SERVICE WATER PUMP X X A X 8/CWPH/SW BLDG SWEL1-1 1 Sl 8a 58 SI-00852A LOW HEAD Sl CORE DELUGE ISOLATION X A 46/U1C/SEAL TABLE SWEL2 0 SF 5 24 P-012B SPENTFUELCOOLINGPUMP B 46/PAB/SFP HX AREA SWEL2 0 SF 5 24 P-012A SPENT FUEL COOLING PUMP A 46/PAB/SFP HX AREA SWEL2 0 SF 21b 24 HX-013B SPENT FUEL POOL HEAT EXCHANGER B 46/PAB/SFP HX AREA SWEL2 0 SF 21b 24 HX-013A SPENT FUEL POOL HEAT EXCHANGER A 46/PAB/SFP HX AREA SWEL2 0 sw 8a 24 SW-02930B HX-13B SFP HX OUTLET B 46/PAB/SFP HX AREA SWEL2 0 sw 8a 24 SW-02930A HX-13A SFP HX OUTLET A 46/PAB/SFP HX AREA SWEL2 0 sw 8a 24 SW-02927B HX-13B SFP HX INLET B 46/PAB/SFP HXAREA SWEL2 0 sw 8a 24 SW-02927A HX-13A SFP HX INLET A 46/PAB/SFP HX AREA

POINT BEACH NUCLEAR PLANT, UNIT 1 1200114-R-001, REVISION 0 B-42 SWEL RISK N UNIT SYS EQUIP WALK EQUIP# EQUIP NAME 1 2 3 4 5 TRN IPEEE LOCATION DESC E CODE CLASS BY Equip.

w AREA Enhanced SWEL2 0 sw 0 14 SF-007858 P-9 HUT RECIRC PUMP SUCTION FROM 8 8/PAB/P-9 HUT AREA WEST TRANSFER CANAL

POINT BEACH NUCLEAR PLANT, UNIT 1 12Q0114-R-001, REVISION 0 B-43 ATTACHMENT B Classes of Equipment Unit 1 and SFP SWEL1 Classes of Equipment SWEL2 Unit 1 0 Other 0 1 1 MCCs and wall-mounted contactors 2 0 2 Low voltage switchgear and break panels 2 0 3 Medium voltage, metal-clad switchQear 1 0 4 Transformers 2 0 5 Horizontal pumps 11 2 6 Vertical pumps 1 0 7 Fluid-operated valves 9 0 8a MOVs 17 4 8b SOVs 2 0 9 Fans 5 0 10 Air handlers 1 0 11 Chiller 0 0 12 Air Compressors 0 0 13 Motor Generators 0 0 Distribution panels and Auto Transfer 14 12 0 Switches 15 Batteries and Racks 1 0 16 Battery charQers and inverters 5 0 17 EnQine Generators 2 0 18 Instrument Racks 1 0 19 Temperature sensors 2 0 20 Instrumentation and Controi_Q_anels 7 0 21a Tanks 10 0 21b Heat exchanQers 2 2 TOTAL 95 9 Note: There are no Chillers, Air Compressors and Motor Generators at Point Beach Unit 1 which are Seismic Category I. Therefore, none of these classes of equipment were included in the SWEL.

POINT BEACH NUCLEAR PLANT, UNIT 1 12Q0114-R-001, REVISION 0 B-44 Attachment C Selected Equipment List Unit 1 and SFP SWEL RISK NEW UNIT SYS EQUIP EQUIP EQUIPMENT NAME 1 2 3 4 5 LOCATION DESC SEISMIC CODE CLASS NUMBER CAT D-03 26/PAB/INVERT RM I SWEL 1-1 0 125V 14 125V DC DISTRIBUTION PANEL X X X X X WEST D-105 35/PAB/D-1 05 BATT I SWEL1-1 y 0 125V 15 125V DC STATION BATTERY X X X X X RM D-107 26/PAB/INVERT RM I SWEL 1-1 0 125V 16 D-105 DC STATION BATTERY CHARGER X X X X X WEST SWEL 1-1 y 0 125V 14 D-12 125V DC DISTRIBUTION PANEL X X X X X 26/CB/CSR EAST I SWEL 1-1 y y 0 125V 14 D-14 125V DC DISTRIBUTION PANEL X X X X X 26/CB/CSR EAST I SWEL1-1 y 0 125V 14 D-16 125V DC DISTRIBUTION PANEL X X X X X 44/CB/CR SOUTH I SWEL 1-1 y y 0 125V 14 D-17 125V DC DISTRIBUTION PANEL X X X X X 44/CB/CR SOUTH I SWEL1-1 y 0 125V 14 D-1S 125V DC DISTRIBUTION PANEL X X X X X 44/CB/CR NORTH I D-2S 2S/DGB/G-03 SWGR I SWEL1-1 y 0 125V 14 G-03 EDG DC DISTRIBUTION PANEL X X X X X RM D-63 S/CB/AFP RM 1P-29 I SWEL1-1 y 0 125V 14 125V DC DISTRIBUTION PANEL X X X X X CUB 1RK-S9 SWEL1-1 y 1 4.16KV 3 1A-05 4.16 KV BUS SWITCHGEAR (SAFEGUARDS) X X X X X S/CBNSG RM I SWEL1-1 y 1 4SOV 2 1B-03 4SOV SAFEGUARDS LOAD CENTER X X X X X 26/CB/CSR I SWEL 1-1 y 1 4SOV 2 1B-04 4SOV SAFEGUARDS LOAD CENTER X X X X X 26/CB/CSR I SWEL1-1 y 1 4SOV 4 1X-13 1B-03 STATION SERVICE TRANSFORMER X X X X X 26/CB/CSR I SWEL 1-1 y 1 4SOV 4 1X-14 1 B-04 STATION SERVICE TRANSFORMER X X X X X 26/CB/CSR I B312A- P-10A RHR PUMP NORMALIALT TRANSFER I SWEL1-1 y 1 4SOV 1 BS55B SWITCH X X X X X S/PAB/COL P-11 B42- 2B4212B-BS11M (D-109) CHGR NRM/ALT 26/PAB/C-59 AREA I SWEL 1-1 y 2 4SOV 1 4212B XFR SWITCH CONTACTOR X X X X X 2B-42 1AF- 1P-29 AFP DISCHARGE 1HX-1 B SG INLET S/CB/AFP RM 1P-29 I SWEL1-1 1 AF Sa 04000 ISOLATION MOV X X X CUB 1AF- 1P-29 AFP DISCHARGE 1HX-1A SG INLET S/CB/AFP RM 1P-29 I SWEL 1-1 1 AF Sa 04001 ISOLATION MOV X X X CUB 1AF- S/CB/AFP RM 1P-29 I SWEL 1-1 y 1 AF 7 04002 1P-29 AFP MINI RECIRC CONTROL X X X CUB 1AF- 1 P-29 AFP SUCTION FROM SERVICE S/CB/AFP RM 1P-29 I SWEL 1-1 1 AF Sa 04006 WATER X X X CUB 1P-029 S/CB/AFP RM 1P-29 I SWEL 1-1 y 1 AF 5 AUX FEEDWATER TURBINE-DRIVEN PUMP X X X CUB 1P-053 UNIT 1 AUX FEEDWATER MOTOR-DRIVEN I SWEL1-1 y y 1 AF 5 PUMP X X X S/PAB/1 P-53 AFP RM

POINT BEACH NUCLEAR PLANT, UNIT 1 12Q0114-R-001 REVISION 0 B-45 SWEL RISK NEW UNIT SYS EQUIP EQUIP EQUIPMENT NAME 1 2 3 4 5 LOCATION DESC SEISMIC CODE CLASS NUMBER CAT 1T-212 1P-29 AFP MINI RECIRC lA 1AF-4002 I SWEL1-1 y 1 AF 21a BACKUP ACCUMULATOR X X X 8/CB/AFP RM AF-04007 8/CB/AFP RM P-38A I SWEL 1-1 0 AF 7 P-38A SSGP MINI RECIRC CONTROL X X X CUB AF-04009 P-38A SSGP SUCTION FROM SERVICE 8/CB/AFP RM P-38A I SWEL1-1 0 AF 8a WATER X X X CUB AF-04012 8/CB/AFP RM P-38A I SWEL 1-1 0 AF 7 P-38A SSGP DISCHARGE CONTROL X X X CUB AF-04023 P-38A SSGP DISCHARGE TO 1HX-1A 8/CB/AFP RM P-38A I SWEL1-1 y 0 AF 8a STEAM GENERATOR X X X CUB AF-04067 1 P-53 AFP SERVICE WATER SUPPLY I SWEL 1-1 y 1 AF 8a ISOLATION X X X 8/PAB/1 P-53 AFP RM AF- I SWEL 1-1 y 1 AF 8b 04073B 1P-53 AFP RECIRCULATION ISOLATION X X X 8/PAB/1 P-53 AFP RM P-038A 8/CB/AFP RM P-38A I SWEL1-1 0 AF 5 AUX FEEDWATER MOTOR-DRIVEN PUMP X X X CUB RK-25A 8/CB/AFP RM P-38A I SWEL 1-1 0 AF 18 P-38A SSGP INSTRUMENTATION RACK X X X CUB T-224B 1AF-4073B/1AF-4074B AFP RECIRC I SWEL1-1 y 1 AF 21a ISOLATION lA ACCUMULATOR X X X 8/PAB/1 P-53 AFP RM 1HX-012A COMPONENT COOLING WATER HEAT I SWEL1-1 y y 1 cc 21b EXCHANGER X X X 46/PAB/CC HX AREA 1P-011A 8/PAB/CC PUMP I SWEL1-1 y 1 cc 5 COMPONENT COOLING WATER PUMP X X X AREA SWEL1-1 y 1 cc 21a 1T-012 COMPONENT COOLING SURGE TANK X X X 46/PAB/CC HX AREA I TE-00621 HX-12A/B CC HX OUTLET HEADER I SWEL 1-1 1 cc 19 TEMPERATURE RTD X X X 46/PAB/CC HX AREA SWEL 1-1 1 cv 21b HX-004 EXCESS LETDOWN HEAT EXCHANGER X 21/U1C I 1CV- 1P-2A-C CHARGING PUMP REFUELING 8/PAB/U1 CHG PUMP I SWEL 1-1 y 1 cv 8a 00112B WATER SUCTION X X X AREA 1CV- I SWEL1-1 1 cv 7 00142 CHARGING LINE FLOW CONTROL X X X 8/PAB/PIPEWAY #1 1P-002A CHARGING PUMP (Pump Only as Pressure 8/PAB/U1 CHG PUMP I SWEL 1-1 y 1 cv 5 Boundary) X X X RM T-060B G-01 EDG STARTING AIR RECEIVER I SWEL1-1 0 DA 21a (RIGHT BANK) X X X X X 8/CB/G-01 RM T-060C G-01 EDG STARTING AIR RECEIVER I SWEL 1-1 0 DA 21a {RIGHT BANK) X X X X X 8/CB/G-01 RM T-060E G-01 EDG STARTING AIR RECEIVER (LEFT I SWEL1-1 0 DA 21a BANK) X X X X X 8/CB/G-01 RM

POINT BEACH NUCLEAR PLANT, UNIT 1 12Q0114-R-001 REVISION 0 B-46 SWEL RISK NEW UNIT SYS EQUIP EQUIP EQUIPMENT NAME 1 2 3 4 5 LOCATION DESC SEISMIC CODE CLASS NUMBER CAT T-060F G-01 EDG STARTING AIR RECEIVER (LEFT I SWEL 1-1 0 DA 21a BANK) X X X X X 8/CB/G-01 RM SWEL 1-1 y 0 DA 21a T-170A G-03 EDG STARTING AIR RECEIVER X X X X X 28/DGB/G-03 RM I C-034 8/CB/G-01 RM W I SWEL 1-1 0 DG 20 G-01 EDG ALARM AND ELECTRICAL PANEL X X X X X WALL C-034A 8/CB/G-01 RM W I SWEL1-1 0 DG 20 G-01 EDG LOCAL TRANSFER PANEL X X X X X WALL C-078 G-01 EDG DC POWER TRANSFER 8/CB/G-01 RM W I SWEL 1-1 0 DG 20 CONTROL PANEL X X X X X WALL C-081 28/DGB/G-03 SWGR I SWEL 1-1 y 0 DG 20 G-03 EDG CONTROL PANEL X X X X X RM SWEL1-1 y 0 DG 17 G-01 EMERGENCY DIESEL GENERATOR X X X X X 8/CB/G-01 RM I SWEL 1-1 y y 0 DG 17 G-03 EMERGENCY DIESEL GENERATOR X X X X X 28/DGB/G-03 RM I W-181A1 50/DGB/G-03 RADTR I SWEL 1-1 y 0 DG 9 G-03 EDG HX-265A RADIATOR FAN X X X X X RM W-181A2 50/DGB/G-03 RADTR I SWEL 1-1 y 0 DG 9 G-03 EDG HX-265A RADIATOR FAN X X X X X RM F0-03930 T-31A G-01 EDG DAY TANK INLET SECOND I SWEL 1-1 0 FO 8a OFF ISOLATION X X X X X 8/CB/G-01 RM P-206A G-01 EDG FUEL OIL TRANSFER PUMP 28/DGB/G-01/2 FOTP I SWEL 1-1 y 0 FO 5 X X X X X RM SWEL1-1 0 FO 21a T-031A G-01 DIESEL GENERATOR DAY TANK X X X X X 8/CB/G-01 RM I 1C-105 SECONDARY SYSTEM POWER SUPPLIES I SWEL 1-1 1 MMS 20 PANEL X X X 44/CB/CR 1MS- HX-1 B SG HEADER P-29 AFP STEAM I SWEL1-1 1 MS 8a 02019 SUPPLY MOV X X X X 46/PAB/BAST AREA S 1MS- HX-1A SG HEADER P-29 AFP STEAM I SWEL 1-1 1 MS 8a 02020 SUPPLY MOV X X X X 46/PAB/BAST AREAS 1MS- I SWEL 1-1 1 MS 8b 02090 P-29 AFP BEARING COOLING INLET X X X 8/CB/AFP RM SWEL 1-1 1 PACV 19 TE-03292 EL 66' U1C TEMPERATURE ELEMENT X 66/U1C/NE QTR I SWEL1-1 y 1 RH 5 1P-010A RESIDUAL HEAT REMOVAL PUMP X X X X X -19/PAB I SWEL 1-1 y 1 RH 5 1 P-010B RESIDUAL HEAT REMOVAL PUMP X X X X X -19/PAB I 1RH- -5/PAB/EAST WALL I SWEL1-1 1 RH 7 00624 HX-11A RHR HX OUTLET CONTROL X X X X X OVHD 1RH- -5/PAB/EAST WALL I SWEL 1-1 1 RH 7 00625 HX-11 B RHR HX OUTLET CONTROL X X X X X OVHD SWEL 1-1 1 Sl 8a SI-00852A LOW HEAD Sl CORE DELUGE ISOLATION X 46/U1C/SEAL TABLE I SWEL 1-1 1 Sl 21a T-034A SAFETY INJECTION ACCUMULATOR X X X 21/U1 C/SW QTR I

POINT BEACH NUCLEAR PLANT, UNIT 1 12Q0114-R-001 REVISION 0 B-47 SWEL RISK NEW UNIT SYS EQUIP EQUIP EQUIPMENT NAME 1 2 3 4 5 LOCATION DESC SEISMIC CODE CLASS NUMBER CAT 1P-014A 8/PAB/SPRAY PUMP I SWEL 1-1 1 SI 5 CONTAINMENT SPRAY PUMP X AREA 1P-014B 8/PAB/SPRAY PUMP I SWEL1-1 1 Sl 5 CONTAINMENT SPRAY PUMP X AREA SWEL1-1 y 1 Sl 5 1P-015A SAFETY INJECTION PUMP X X X X X 8/PAB/SI PUMP AREA I 1SI- 8/PAB/SPRAY PUMP I SWEL1-1 1 Sl 8a 00825A T-13 RWST OUTLET TO P-15A/B Sl PUMP X X X X X AREA 1SI- 8/PAB/SPRAY PUMP I SWEL 1-1 1 Sl 8a 00825B T-13 RWST OUTLET TO P-15A/B Sl PUMP X X X X X AREA 1SI- HX-11A RHR HX OUTLET TO P-15A Sl I SWEL 1-1 y 1 SI 8a 00857A PUMP SUCTION X X X X X 8/PAB/SI PUMP AREA 1SI- I SWEL 1-1 y 1 Sl 8a 00866A COLD LEG INJECTION LINE ISOLATION X X X X X 8/PAB/PIPEWAY #1 1SI- CORE DELUGE INJECTION LINE I SWEL1-1 y 1 Sl 8a 00866B ISOLATION X X X X X 8/PAB/PIPEWAY#1 1SI- I SWEL1-1 y 1 Sl 8a 00896A P-15A Sl PUMP SUCTION X X X X X 8/PAB/SI PUMP AREA 1SW- HX-12A CC HX OUTLET TEMPERATURE I SWEL 1-1 y 1 sw 7 00012A CONTROL X 46/PAB/CC HX AREA SWEL 1-1 y 0 sw 6 P-032A SERVICE WATER PUMP X X 8/CWPH/SW BLDG I SW- HX-12B CC HX OUTLET TEMPERATURE I SWEL1-1 y 0 sw 7 00012B CONTROL X 46/PAB/CC HX AREA SW- HX-12C CC HX OUTLET TEMPERATURE I SWEL 1-1 y y 0 sw 7 00012C CONTROL X 46/PAB/CC HX AREA SWEL 1-1 0 VNBI 20 C-022 BATTERY ROOM HVAC CONTROL PANEL X X X X X 26/PAB/NORTH . I W-085 PAB BATTERY AND INVERTER ROOM I SWEL 1-1 0 VNBI 10 VENT FAN X X X X X 35/PAB/D-106 ROOF W-001B1 CONTAINMENT ACCIDENT I SWEL 1-1 1 VNCC 9 RECIRCULATION FAN X X X X X 46/U1 C/SOUTH C-032 8/CB/G-01 RM S I SWEL 1-1 0 VNDG 20 G-01 EDG EXHAUST FAN CONTROL PANEL X X X X X WALL W-183B G-03 EDG RM SMALL CAPACITY EXHAUST I SWEL1-1 y y 0 VNDG 9 FAN X X X X X 50/DGB/G-03 FAN RM W-183C G-03 EDG RM LARGE CAPACITY EXHAUST I SWEL 1-1 y y 0 VNDG 9 FAN X X X X X 50/DGB/G-03 FAN RM SWEL 1-1 1 y 16 1 DY-01 RED 125V DC/120V AC INVERTER X X X X X 26/CB/CSR I 1DY-03 26/PAB/INVERT RM I SWEL 1-1 1 y 16 WHITE 125V DC/120V AC INVERTER X X X X X WEST 1Y-203 WHITE 120V INVERTER DISTRIBUTION 26/CB/CSR WEST I SWEL 1-1 1 y 14 PANEL X X X X X WALL

POINT BEACH NUCLEAR PLANT, UNIT 1 12Q0114-R-001 REVISION 0 B-48 SWEL RISK NEW UNIT SYS EQUIP EQUIP EQUIPMENT NAME 1 2 3 4 5 LOCATION DESC SEISMIC CODE CLASS NUMBER CAT 43/Y-01 1Y-01 RED 120V AC VITAL INST PNL PWR I SWEL1-1 1 y 14 SUP TRANSFER SW X X X X X 44/CB/CR WEST 43/Y-02 1Y-02 BLUE 120V AC VITAL INST PNL PWR I SWEL 1-1 1 y 14 SUP TRANSFER SW X X X X X 44/CB/CR WEST 83/DY-03 1DY-03 WHITE INVERTER STATIC 26/PAB/INVERT RM I SWEL 1-1 1 y 14 TRANSFER SWITCH X X X X X WEST DY-OB BLUE 125V DC/120V AC ALTERNATE I SWEL 1-1 0 y 16 INVERTER X X X X X 26/CB/CSR DY-OC 26/PAB/INVERT RM I SWEL 1-1 0 y 16 WHITE 125V DC/120V AC INVERTER X X X X X WEST 1SAF- 1P-29 AFP DISCH 1 HX-1 B SG INLET ISOL I PB 1 125V 2 04000 MOV STARTER X X X 8/CBNSG EQUIP RM 1SAF- 1P-29 AFP DISCH 1HX-1A SG INLET ISOL I PB 1 125V 2 04001 MOVSTARTER X X X 8/CBNSG EQUIP RM 1SMS- HX-1 B SG HDR P-29 AFP STEAM SUPPLY I PB 1 125V 2 02019 MOVSTARTER X X X 8/CBNSG EQUIP RM 1SMS- HX-1A SG HDR P-29 AFP STEAM SUPPLY I PB 1 125V 2 02020 MOV STARTER X X X 8/CBNSG EQUIP RM 1SMS- 8/CB/AFP RM 1P-29 I PB 1 125V 2 02082 P-29 AFP OVERSPEED TRIP STARTER X X X CUB PB 0 125V 14 D-01 125V DC DISTRIBUTION PANEL X X X X X 8/CBNSG RM I PB 0 125V 15 D-05 125V DC STATION BATTERY X X X X X 8/CB/D-05 BATT RM I PB y 0 125V 16 D-09 SWING STATION BATTERY CHARGER X X X X X 8/CBNSG RM I PB y 0 125V 14 D-19 125V DC DISTRIBUTION PANEL X X X X X 44/CB/CR NORTH I PB y y 0 125V 14 D-21 125V DC DISTRIBUTION PANEL X X X X X 44/CB/CR SOUTH I D-302 26/PAB/INVERT RM I PB y 0 125V 14 SWING BATTERY DISTRIBUTION PANEL X X X X X WEST 1B-32 480V MOTOR CONTROL CENTER PAB 8/PAB/U1 CHG PUMP I PB 1 480V 1 SAFEGUARDS X X X X X AREA 1B-39 480V MOTOR CONTROL CENTER TRAIN A I PB 1 480V 1 BATTERY CHARGER SUPPLY X X X X X 8/CBNSG RM 1B-49 480V MOTOR CONTROL CENTER TRAIN B I PB 1 480V 1 BATTERY CHARGER SUPPLY X X X X X 8/CBNSG RM B311C- P-32B SERVICE WATER PUMP I PB 1 480V 1 B854D NORMAL!ALT TRANSFER SW X X 8/CB/G-01 RM B334B- P-32F SERVICE WATER PUMP I PB 2 480V 1 B854D NORMAL/ALT TRANSFER SW X X 8/CB/G-01 RM B421A- P-10B RHR PUMP NORMALIALT TRANSFER I PB 1 480V 1 B855B SWITCH X X X X X 8/PAB/COL P-12

POINT BEACH NUCLEAR PLANT, UNIT 1 12Q0114-R-001 ' REVISION 0 -

B 49 SWEL RISK NEW UNIT SYS EQUIP EQUIP EQUIPMENT NAME 1 2 3 4 5 LOCATION DESC SEISMIC CODE CLASS NUMBER CAT B42- 1B42-3212H D-109 SWING STN BATT CHGR 8/PAB/U1 CHG PUMP I PB 1 480V 1 3212H TRAIN A CONTACTOR X X X X X AREA 1B-32 B42-391 D-07 STATION BATTERY CHARGER TRAIN I PB 1 480V 1 ACONTACTOR X X X X X 8/CBNSG RM 1B-39 B42-491 D-09 SWING STN BATTERY CHARGER I PB 1 480V 1 TRAIN B CONTACTOR X X X X X 8/CBNSG RM 1B-49 B42-494 D-108 STATION BATTERY CHARGER TRAIN 26/PAB/INVERT RM I PB 1 480V 1 B CONTACTOR X X X X X EAST 1RK-35 1P-29 AUX FEEDWATER PUMP 8/CB/AFP RM 1P-29 I PB 1 AF 18 INSTRUMENTATION RACK X X X CUB AF- 8/CB/AFP RM P-38A I PB 0 AF 8b 04007A-S P-38A SSGP COOLING WATER SOLENOID X X X CUB AF-04022 P-38A SSGP DISCHARGE TO 2HX-1A 8/CB/AFP RM P-38A I PB 0 AF 8a STEAM GENERATOR X X X CUB 1CC- CONT EQUIP CC SUPPLY HEADER I PB 1 cc 8a 00719 OUTBOARD ISOLATION X X X 8/PAB/PIPEWAY #2 1CC- I PB 1 cc 8a 00738A 1HX-11A RHR HX SHELL SIDE INLET X X X 8/PAB/PIPEWAY #2 1CC- I PB 1 cc 8a 00738B 1HX-11 B RHR HX SHELL SIDE INLET X X X 8/PAB/PIPEWAY #2 1CC- I PB 1 cc 8a 00754A 1P-1A RCP CC INLET MOV X X X 8/PAB/PIPEWAY#2 1CC- I PB 1 cc 8a 00754B 1P-1B RCP CC INLET MOV X X X 8/PAB/PIPEWAY #2 1CC- I PB 1 cc 8a 00759A 1P-1A RCP CC OUTLET MOV X X X 8/PAB/PIPEWAY #2 1CC- I PB 1 cc 8a 00759B 1P-1 B RCP CC OUTLET MOV X X X 8/PAB/PIPEWAY #2 1P-011B 8/PAB/CC PUMP I PB 1 cc 5 COMPONENT COOLING WATER PUMP X X X AREA 2CC- CONT EQUIP CC SUPPLY HEADER I PB 2 cc 8a 00719 OUTBOARD ISOLATION X X X 8/PAB/PIPEWAY #3 2CC- I PB 2 cc 8a 00754A 2P-1A RCP CC INLET MOV X X X 8/PAB/PIPEWAY#3 2CC- I PB 2 cc 8a 00754B 2P-1 B RCP CC INLET MOV X X X 8/PAB/PIPEWAY#3 2CC- I PB 2 cc 8a 00759B 2P-1B RCP CC OUTLET MOV X X X 8/PAB/PIPEWAY #3 1P-002B CHARGING PUMP (Pump Only as Pressure 8/PAB/U1 CHG PUMP I PB y 1 cv 5 Boundary) X X X RM PB 1 lA 7 11A-03047 U1C lA HEADER INLET CONTROL X 26/PAB/PIPEWAY #2 I

POINT BEACH NUCLEAR PLANT, UNIT 1 12Q0114-R-001 , REVISION 0 B-50 SWEL RISK NEW UNIT SYS EQUIP EQUIP EQUIPMENT NAME 1 2 3 4 5 LOCATION DESC SEISMIC CODE CLASS NUMBER CAT PB 1 lA 7 11A-0304S U1C lA HEADER INLET CONTROL X 26/PAB/PIPEWAY #2 I 1MS- HX-1 B SG HDR ATMOSPHERIC STEAM I PB 1 MS 7 02015 DUMP CONTROL X X X S5/U1 F 1MS- HX-1A SG HDRATMOSPHERIC STEAM I PB 1 MS 7 02016 DUMP CONTROL X X X S5/U1F 1HX-011A RESIDUAL HEAT REMOVAL HEAT I PB 1 RH 21b EXCHANGER X X X X X -5/PAB/RHR HX CUB 1HX-011 B RESIDUAL HEAT REMOVAL HEAT I PB 1 RH 21b EXCHANGER X X X X X -5/PAB/RHR HX CUB PB 1 Sl 5 1P-015B SAFETY INJECTION PUMP X X X X X S/PAB/Sl PUMP AREA I 1SI- P-10B RHR PUMP SUMP B SUCTION I PB 1 Sl Sa OOS50B-M MOTOR/PUMP X X X X X S/PAB/PIPEWAY#2 1SI- P-10A RHR PUMP SUCTION FROM -5/PAB/RHR I PB 1 Sl Sa OOS51A CONTAINMENT SUMP B X X X X X PIPEWAY 1SI- P-10B RHR PUMP SUCTION FROM -5/PAB/RHR I PB 1 Sl Sa OOS51B CONTAINMENT SUMP B X X X X X PIPEWAY 1SI- T-13 RWST OUTLET TO P-10A RHR PUMP I PB 1 Sl Sa OOS56A SUCTION HEADER X X X X X S/PAB/PIPEWAY #2 1SI- T-13 RWST OUTLET TO P-10B RHR PUMP I PB 1 Sl Sa OOS56B SUCTION HEADER X X X X X S/PAB/PIPEWAY#2 1SI- HX-11B RHR HX OUTLET TO P-15B Sl I PB 1 Sl Sa OOS57B PUMP SUCTION X X X X X S/PAB/Sl PUMP AREA 1SI- I PB 1 Sl Sa OOS96B P-15B Sl PUMP SUCTION X X X X X S/PAB/Sl PUMP AREA 1T-013 REFUELING WATER STORAGE TANK W/6 I PB 1 Sl 21a IMMERSION HTRS X X X X X U1F 2SI- T-13 RWST OUTLET TO P-10A RHR PUMP I PB 2 Sl Sa OOS56A SUCTION HEADER X X X X X S/PAB/PIPEWAY#3 2SI- T-13 RWST OUTLET TO P-10B RHR PUMP I PB 2 Sl Sa OOS56B SUCTION HEADER X X X X X S/PAB/PIPEWAY #3 PB 1 y 16 1DY-02 BLUE 125V DC/120V AC INVERTER X X X X X 26/CB/CSR I 1DY-04 26/PAB/INVERT RM I PB 1 y 16 YELLOW 125V DC/120V AC INVERTER X X X X X EAST PB 1 y 14 1Y-01 RED 120V VITAL INSTRUMENT PANEL X X X X X 44/CB/CR WEST I PB 1 y 14 1Y-02 BLUE 120V VITAL INSTRUMENT PANEL X X X X X 44/CB/CR WEST I PB 1 y 14 1Y-104 YELLOW 120V VITAL INSTRUMENT PANEL X X X X X 60/CB/COMP RM I 1Y-204 YELLOW 120V INVERTER DISTRIBUTION 26/CB/CSR WEST I PB 1 y 14 PANEL X X X X X WALL PB 0 y 14 S3/DY-OC DY-OC WHITE INVERTER STATIC X X X X X 26/PAB/NORTH I

POINT BEACH NUCLEAR PLANT, UNIT 1 12Q0114-R-001 , REVISION 0 B-51 SWEL RISK NEW UNIT SYS EQUIP EQUIP EQUIPMENT NAME 1 2 3 4 5 LOCATION DESC SEISMIC CODE CLASS NUMBER CAT TRANSFER SWITCH DY-OD 26/PAB/INVERT RM I PB 0 y 16 YELLOW 125V DC/120V AC INVERTER X X X X X EAST AF- 8/CB/AFP RM P-38B I PB 0 AF 8b 04014A-S P-38B SSGP COOLING WATER SOLENOID X X X CUB AF-04021 P-38B SSGP DISCHARGE TO 1HX-1 B 8/CB/AFP RM P-38B I PB 0 AF 8a STEAM GENERATOR X X X CUB 1P-002C CHARGING PUMP (Pump Only as Pressure 8/PAB/U1 CHG PUMP I PB y 1 cv 5 Boundary) X X X RM 1SI- P-10A RHR PUMP SUMP B SUCTION I PB y 1 SI 8a 00850A-M MOTOR/PUMP X X X X X 8/PAB/PIPEWAY#2 SWEL2 0 SF 21b HX-013A SPENT FUEL POOL HEAT EXCHANGER 46/PAB/SFP HX AREA I SWEL2 0 SF 21b HX-013B SPENT FUEL POOL HEAT EXCHANGER 46/PAB/SFP HX AREA I SWEL2 0 SF 5 P-012A SPENT FUEL COOLING PUMP 46/PAB/SFP HX AREA I SWEL2 0 SF 5 P-012B SPENT FUEL COOLING PUMP 46/PAB/SFP HX AREA I SF- P-9 HUT RECIRC PUMP SUCTION FROM 8/PAB/P-9 HUT AREA I SWEL2 0 SF 0 00785B TRANSFER CANAL WEST SW- I SWEL2 0 SW 8a 02927A HX-13A SFP HX INLET 46/PAB/SFP HX AREA SW- I SWEL2 0 sw 8a 02927B HX-13B SFP HX INLET 46/PAB/SFP HX AREA SW- I SWEL2 0 SW 8a 02930A HX-13A SFP HX OUTLET 46/PAB/SFP HX AREA SW- I SWEL2 0 SW 8a 02930B HX-13B SFP HX OUTLET 46/PAB/SFP HX AREA PB 0 SF 21a SFP SPENT FUEL POOL 46/PAB/SFP HX AREA I Y-204 YELLOW 120V INVERTER DISTRIBUTION 26/CB/CSR WEST I PB 0 y 14 PANEL X X X X X WALL

Point Beach Nuclear Plant, Unit 1 Sheet 1 of 2 1200114-R-001, Revision 0 Status: [YJ N U Seismic Walkdown Checklist (SWC)

Equipment ID No.: _..:...:1P_-..=..01.:....:0:.:..A~--------------------

Equlpment Class: {5) Horizontal Pumps Equipment

Description:

RESIDUAL HEAT REMOVAL PUMP Project: Point Beach 1 SWEL 1 Location (Bldg; Elev, Room/Area): _P:...:A...::B=.~.,_-1.:..:9:..:..:.0:..::0c...:.ft::LA:...:L=L=-----------------

Manufacturer/Model:

Instructions for Completing Checklist This checklist may be used to document the results of the Seismic Walkdown of an Item of equipment on the SWEL. The space below each of the following questions may be used to record the results of judgments and findings. Additional space Is provided at the end of this checklist for documenting other comments.

Anchorage

1. Is anchorage configuration verification required {I.e., Is the Item one of the 50% Yes of SWEL Items requiring such verification)?

2. Is the anchorage free of bent, broken, missing or loose hardware? Yes

3. Is the anchorage free of corrosion that Is more than mild surface oxidation? Yes

4. Is the anchorage free of visible cracks In the concrete near the anchors? Yes

5. Is the anchorage configuration consistent with plant documentation? {Note: Yes This question only applies If the Item Is one of the 50% for which an anchorage configuration verification Is required.)

Anchorage verified per drawings C-250,Rev.8, C-243, Rev. 5 and C-240 Rev. 6.

6. Based on the above anchorage evaluations, Is the anchorage free of Yes potentially adverse seismic conditions?

Interaction Effects

7. Are soft targets free from Impact by nearby equipment or structures? Yes C-49

Point Beach Nuclear Plant, Unit 1 Sheet 2 of2 1200114-R-001, Revision 0 status: [Y] N u Seismic Walkdown Checklist (SWC)

Equipment ID No.: _1.!.!.P_-0=..1.:....:4::...:A~-------------------

Equlpment Class: (5) Horizontal Pumps Equipment

Description:

CONTAINMENT SPRAY PUMP Interaction Effects

7. Are soft targets free from Impact by nearby equipment or structures? Yes Tube In contact with CC pipe and judged to be acceptable.

8. Are overhead equipment, distribution systems, ceiling Illes and lighting, and Yes masonry bloc!< walls not likely to collapse onto the equipment?

Overhead HVAC, conduits, and pipes are judged to be acceptable.

Light above has chain tie wrapped to lift up. Chain Is continuous. Tie wraps should be removed. This issue has been entered into the corrective action process.

9. Do attached lines have adequate flexibility to avoid damage'/ Yes Attached conduit Is flexible.

10. Based on the above seismic Interaction evaluations, Is equipment free of Yes potentially adverse seismic Interaction effects?

other Adverse Conditions

11. Have you looked for and found no adverse seismic conditions that could Yes adversely affect the safety functions of the equipment?

Comments Seismic Walkdown Team: M. Nielsen & D. Carter- 9/18/2012 Detailed signed records of the checklists are available at Evaluated by: _.::clh:.::e..::s::.:.ite::..:*~---------------- Date: - - - - - - - -

C-56

Point Beach Nuclear Plant, Unit 1 Sheet 1 of2 1200114-R-001, Revision 0 Status: [Y] N U Seismic Walkdown Checklist (SWC)

Equipment ID No.: _T..:....-..::.0.:::..31.:.:..A.:...-----------------------

Equlpment Class: (21) Tanks and Heat Exchangers Equipment

Description:

G-01 DIESEL GENERATOR DAY TANK Project: Point Beach 1 SWEL 1 Location (Bldg, Elev, Room/Area): _C::. :B: . !,--=Bc:. :.O:. .: O. .:. ft:L-.=G_,-0:. . :1. .:.R.o:.M:. :. ___ _ _ _ _ _ _ _ _ _ _ _ _ _ __

Manufacturer/Model:

Instructions for Completing Checklist This checklist may be used to document the results of the Seismic Walkdown of an item of equipment on the SWEL. The space below each of the following questions may be used to record the results of judgments and findings. Additional space Is provided at the end of this checklist for documenting other comments.

Anchorage

1. Is anchorage configuration verification required (I.e., Is the Item one of the 50% Yes of SWEL items requiring such verification)?

2. Is the anchorage free of bent, broken, missing or loose hardware? Yes

3. Is the anchorage free of corrosion that Is more than mild surface oxidation? Yes

4. Is the a~chorage free of visible cracks In the concrete near the anchors? Yes

5. Is the anchorage configuration consistent with plant documentation? (Note: Yes This question only applies If the Item Is one of the 50% for which an anchorage configuration verification Is required.)

Tank Is mounted to steel frame with 5/8" diameter bolts and the frame Is mounted with 1" thru bolts and one anchorage welded to tan embed plate.

Calculation N-90-043, Rev. 0 Attachment 2 shows analysis for 5/8" mounting bolts for tan!< and 1" thru bolts for the attachment of the frame to the wall.

Therefore, the plant documentation Is confirmed.

6. Based on the above anchorage evaluations, Is the anchorage free of Yes potentially adverse seismic conditions?

C-179

Point Beach Nuclear Plant, Unit 1 Sheet 2 of2 1200114-R-001, Revision 0

• Status: [YJ N U Area Walk-By Checklist (AWC)

Location (Bldg, Elev, Room/Area): Area Walk-by 19 PAB EL 8' BY Sf & CS PUMPS

5. Does It appear that the area Is free of potentially adverse seismic Interactions Yes that could cause flooding or spray In the area?

Fire protection lines In area are threaded and well supporled. Judged to be acceptable.

6. Does It appear that the area is free of potentially adverse seismic Interactions Yes that could cause a fire In the area?

No sources.

7. Does It appear that the area Is free of potentially adverse seismic Interactions Yes associated with housel<eeping practices, storage of portable equipment, and temporary Installations (e.g., scaffolding, lead shielding)?

Scaffold above 2P-14B /ool<s to be well built and fled off.

8. Have you looked for and found no other seismic conditions that could Yes adversely affect the safely functions of the equipment In the area?

Two lights In corridor area are attached to steel with magnets. Appear to be strongly attached. This issue has been entered into the station conective action process.

Comments Seismic Walkdown Team: M. Nielsen & D. Carter- 9/20/2012 Detailed signed records of the checldlsts are available at Evaluated by: the site. Date:

Point Beach Nuclear Plant, Unit 1 Sheet 1 of 2 1200114-R-001, Revision 0 Status: W N U Area Walk-By Checklist (AWC)

Location (Bldg, Elev, Room/Area): Area Walk-by 24: PAB EL. 46' SFP HX AREA Instructions for Completing Checklist This checklist may be used to document the results of the Area Walk-By near one or more SWEL items. The space below each of the following questions may be used to record the results of judgments and findings.

Additional space is provided at the end of this checklist for documenting other comments.

1. Does anchorage of equipment in the area appear to be free of potentially Yes adverse seismic conditions (if visible without necessarily opening cabinets)?

2. Does anchorage of equipment in the area appear to be free of significant Yes degraded conditions?

Anchorage on tank support for T-161A are small. East anchors are in oversized holes. Northwest anchors seem to have more surface rust. Appears to be OK now, but should be cleaned and evaluated. This issue has been entered into the station corrective action process.

3. Based on a visual inspection from the floor, do the cable/conduit raceways and Yes HVAC ducting appear to be free of potentially adverse seismic conditions (e.g.,

condition of supports is adequate and fill conditions of cable trays appear to be inside acceptable limits)?

Drain tube attached to cable with clamps and oriented incorrectly. No seismic interaction concerns since there is no soft targets in the vicinity.

4. Does it appear that the area is free of potentially adverse seismic spatial Yes interactions with other equipment in the area (e.g., ceiling tiles and lighting)?

Abandoned support in SW corner of room. Will not cause damage to adjacent pipe and is judged to be acceptable.

This issue has been entered into the corrective action program.

5. Does it appear that the area is free of potentially adverse seismic interactions Yes that could cause flooding or spray in the area?

Welded pipe supports. No concerns.

6. Does it appear that the area is free of potentially adverse seismic interactions Yes that could cause a fire in the area?

7. Does it appear that the area is free of potentially adverse seismic interactions Yes associated with housekeeping practices, storage of portable equipment, and temporary installations (e.g., scaffolding, lead shielding)?

Scaffold at west end screw jacked to steel above and close to several pipes.

Sufficiently braced with no interaction concerns.

Scaffold fence is tied off at HX-138 base and tied to pipe support base and is judged to be acceptable.

D-40

Point Beach Nuclear Plant, Unit 1 1200114-R-001, Revision 0 E

Plan for Future Seismic Walkdown of Inaccessible Equipment Completion of the walkdowns for nine (9) items must be deferred due to accessibility. Four items require opening energized equipment and five items require a refueling outage. Table E-1 summarizes the reasons each item is inaccessible during normal plant operation. PBNP CRs have been written to identify these deferred components and to provide a schedule the future Seismic Walkdowns for these items.

Table E -1. Summary of Inaccessible Equipment Scheduled Location Reason for Component ID Description Completion Inaccessibility W-001A1 Unit 1 Containment Access to containment is Complete Containment Accident restricted during plant Recirculation Fan operation.

TE-03292 Unit 1 EL 66' U1C Access to containment is Complete Containment Temperature restricted during plant Element operation.

T-034A Unit 1 Safety Injection Access to containment is *Complete Containment Accumulator restricted during plant operation.

HX-004 Unit 1 Excess Letdown Access to containment is Complete Containment Heat Exchanger restricted during plant operation.

SI-00852A Unit 1 Low Head Si Core Access to containment is Complete Containment Deluge Isolation restricted during plant operation.

C-022 26/PAB/North Battery Room Hvac Equipment energized Complete Control Panel 1B312A-B855B 8/PAB/Col P-11 P-10A RHR Pump Equipment energized Complete Normai/ALT Transfer Switch C-081 28/DGB/G-03 G-03 EDG Control Equipment energized 41h Qtr. 2013 SWGRRm PANEL 51 C-032 8/CB/G-01 Rm G-01 EDG Exhaust Equipment energized 1 Qtr. 2014 South Wall Fan Control Panel

Point Beach Nuclear Plant, Unit 1 12QO 114-R-001, Revision 0

3. PEER REVIEW TEAM &PROCESS The Point Beach (PBN) Peer Review Team consisted of Individuals from PBN operations, civil engineering, licensing, and PRA as well as structural/seismic engineers from Stevenson & Associates. These Individuals participated In phases of preparation, performance, and peer review of the seismic walkdowns. This section documents the peer review process and how the Peer Review Team Interacted with the Seismic Walkdown Engineering Teams.

3.1 Peer Review Team The affiliation, role, and qualifications for each Peer Review Team member are summarized In the following table.

Name Group Role* Qualifications **

Rick Merkes PBN Operations SWEL co-preparer (e)(f)

Douglas P. Brown PBN Civil Engineering Peer Review Team Leader (b) (c) (g)

SWE SWEL co-preparer David N. Carter Stevenson &Assoc. SWE Team #1 Leader (b) (c) (g)

(consultant eng.) SWEPR Nabll Juraydlni Stevenson &Assoc. SWE Team #2 Leader (b) (c) (g)

(consultant eng.) SWE PR Stanley E. Guokas PBN PRA Group PRTeam (d)

PBN - SWEL Preparer Russ Severson DAEC PRA Group SWELPR (d)

T.l<. Ram Stevenson &Assoc. SWELPR (d) (e)

(consultant eng.)

Jeffery Buboltz PBN Civil Engineering SWE Team Member (b) (c) (g)

SWEPR Scott l<ahi SWE Team Member (b) (c),(g)

SWEPR Richard l. LaPlante SWE Team Member (b) (c) (g)

SWE PR Coreen A. McDonald SWE Team Member (b) (c) (g)

SWEPR Mark c. Nielsen SWE Team Member (b) (c) (g)

SWEPR License Basis PR Dave J. Nuttall SWE Team Member (b) (c) (g)

SWEPR License Basis PR Notes:

• Role: PR (peer review), SWEL (seismic walkdown equipment list), SWE (seismic walkdown engineer)

• • Qualifications:

(a) Completed EPRI NTTF 2.3 Seismic Walkdown Training (b) Seismic engineering experience (c) Degree In mechanical engineering or civil/structural engineering (d) Seismic PRA /IPEEE experience F-3

Point Beach Nuclear Plant, Unit 1 1200114-R-001, Revision 0 (e) Knowledge of plant operations, documentation (f) Plant Operations member (g) Completed SQUG Walkdown Screening and Seismic Evaluation Training Course 3.2 Peer Review Process PRTeam Lead Doug Brown served as the Peer Review Team Lead. In that role, he was responsible for coordinating the peer review and assembling this report. As described below, he also performed some additional roles as part of the wali<down team and checklist PR. He also participated In the SWEL preparation, so he was not part of that PR process. That Is, even though he was a SWEL co-preparer, the SWEL was Independently reviewed and he did not partake In any of the SWEL PR. Therefore, performing as the lead peer review Is considered acceptable.

SWEL Preparation The SWEL was prepared by S. Guokas, who Is a PBN PRA engineer, with familiarity with the PBN IPEEE Report and the PBN PRA model. Additional Input Into the SWEL was provided by a plant staff structural/seismic engineer (D. P.

Brown), and a Plant Operations representative (R. Markes).

The SWEL was Peer Reviewed by a team that Included a PRA engineer {R.

Severson)and a Seismic PRAIIPEEE engineer (T.K. Ram).

Seismic Walkdown The primary seismic walkdown was conducted with two teams, each with two qualified structural/seismic engineers. A contractor engineer severed as Team Leader of each team. The second team member was an available PBN SWE or the two contract engineers worked together as ~me team.

The Peer Review of the walkdowns consisted of a Peer Review Team Lead with Operations and PRA knowledge, and structural/seismic engineers. The structural/seismic engineers made up the SWE teams, but also served to peer review each other's work. The Peer Review Team Lead also participated In a few of the walkdowns for logistical support. The ultimate judgments regarding licensing basis were made by qualified Point Beach structural engineers.

• Seismic Walkdown Engineers (SWE):

- SWE Team #1- D. N. Carter (team lead),

- SWE Team #2- N. Juraydinl (team lead),

- SWE Team member- D.P. Brown

- SWE Team member- J. Buboltz

ENCLOSURE 2 NEXTERA ENERGY POINT BEACH, LLC POINT BEACH NUCLEAR PLANT, UNITS 1 AND 2 UPDATE TO NEXTERA ENERGY POINT BEACH, LLC RESPONSE TO 10 CFR 50.54(F)

REQUEST FOR INFORMATION REGARDING NEAR-TERM TASK FORCE RECOMMENDATION 2.3, SEISMIC SEISMIC WALKDOWN REPORT POINT BEACH NUCLEAR PLANT, UNIT 2 1200114-R-002 REVISION 0 56 pages follow

Updates to Seismic Walkdown Report Point Beach Nuclear Plant, Unit 2 1200114-R-002 Revision 0 Executive Summary No ChanQes Section 1 No Changes Section 2 No Changes Section 3 No ChanQes Section 4 No Changes Section 5 Additional items were added to Table 5.2 (P-032F, 2P-015B). A correction was made to Table 5.3 {AWB 28, W-002A should have been W-002B).

Section 6 No Changes Section 7 No Changes Section 8 No Changes Section 9 No Changes Appendix A No Changes Appendix B Table 3, IPEEE and A-46 Outlier Resolution, is updated to only include the equipment for Unit

2. Resolution dates were also added.

Attachment A was updated to include the equipment from the spent fuel pool (SFP).

This information had been included on only the Unit 1 report.

Attachment B was updated to include the equipment from the SFP. This information had been included on only the Unit 1 report.

Attachment C was added to provide the selected equipment list. The enclosed pages, B-12 through B-48, replace pages B-12 through B-36 of the original report.

Appendix C Administrative changes made on pages C-66, C-86, C-116, C-146, C-162, and C-172.

Appendix D Administrative change made on page D-30.

Appendix E Table E-1 has been updated Appendix F Administrative changes made on pages F-3 and F-4.

Table 5-2: Table of Actions Resulting from Seismic Walkdown lnsQection C) "0 "0 s::: Q)

Q) N "0 E >o Action Taken to Equipment I 10 Potentially Adverse Seismic Condition ...

co C) s::: ...

0 0 z-s:::

iU s:::

Address the Current Status Q) co Condition c 0

(.)

s:::

J NextEra Engineering Closed.

evaluated the corrosion Will be tracked and determined minor through P-0320 Corrosion observed on the base plate. X and would not affect structures the design function of monitoring the pump. CR initiated. program.

NextEra Engineering Closed.

evaluated the corrosion Will be tracked and determined minor through P-032E Corrosion observed on the base plate. X and would not affect structures the design function of monitoring the pump. CR initiated program.

P-032F NextEra Engineering Closed.

evaluated the corrosion Will be tracked and determined minor through Corrosion observed on the baseplate. X and would not affect structures the design function of monitoring the pump. CR initiated. program.

NextEra Engineering determined from P&ID A section of tubing is supporting the solenoid and drawings that a loss of attached flexible conduit fitting. The solenoid and the Being tracked in 2MS-02090 X air to the valve results fitting are relatively heavy compared to the capacity of the CAP.

in the valve going to a the tubing supporting them.

safe position. Initiated CR.

Table 5-2: Table of Actions Resulting from Seismic Walkdown lns(;!ection Cl '0

'0 s:::: Q)

Q) N

'0 E ~

Action Taken to Equipment n:s I

s:::: ....

ID Potentially Adverse Seismic Condition .... 0 0 n:s Address the Current Status Cl Q) z-s:::: s::::

n:s Condition c 0 u

s::::

J Cast in place anchors have greater capacity The pump is anchored with eight 1" cast in place bolts.

than Wejit expansion The Drawing C-240 shows the anchors as 1" Wejit type anchors. Based on Being tracked in 2P-002C expansion anchor. The SQUG SEWS prepared for the X this, the as installed the CAP.

USI A-46 program also indicates that the anchors are 1" condition is not a Wejit type.

seismic concern. CR initiated.

The walkdown team determined that the missing bolt does not adversely affect the Work request seismic capability of 2B-03 Rear bottom panel is missing a mounting bolt. X initiated to install the equipment. The bolt the bolt.

is one of many that attach the rear panel to the frame. Initiated CR.

NextEra Engineering Two crank handles in vicinity are loosely hung from determined that the D26 X Closed bolts in the concrete wall. panel contains no sensitive items.

2P-015B The as-installed Wej-it type anchors were The anchor bolt type shown on drawing C-242 conflicts evaluated on with the as-installed anchor bolt type. Drawing C-242 SQ-000077. Since the Being tracked in X

states the anchor bolt type is cast-in-place. The condition was CAP.

installed anchor bolts are Wej-its. previously evaluated, this is a documentation discrepancy issue.

Table 5-3: Table of Actions Resulting from Area Walk*b~ lns~ections

, C'l ,

,ca (I) c:

. *e c: ...

(I)

N

.2' Action Taken to Area Potentially Adverse Seismic Condition ...C'l 0 z-c:

0 ca c:

Address the Current Status (I) ca Condition c 0 c:

(J ~

In the judgment of the walkdown team, the light fixture would not An S-Hook supporting a light fixture was observed to Work request AWB9 X fall and interact with be opened. initiated to repair.

any seismically qualified equipment.

Initiated CR.

NextEra Engineering performed a walkdown and determined that The G-02 diesel room contains threaded fire protection much of the area is piping that is supported from threaded rod hangers.

not susceptible to The fire protections system is only laterally supported issues do to spray. A at a connection to a fire protection header which preliminary evaluation comes into the room through a wall. The lines are was performed for the supported off various lengths threaded rods that are piping at the west end typically attached to a shell type anchor in the of the room and it was Being tracked in AWB 11 concrete ceiling. On the west end, the fire protection X determined that the the CAP.

line and a sprinkler head are relatively close to the piping is within code room fans. The Seismic Walkdown Team was unable allowable stresses and to conclude that the fire protection pipe and sprinkler will not leak. This head would not move and interaction with the fans. In preliminary evaluation addition, the team could not conclude that the fire was considered a protection line would not deflect in a manner that bounding case and would cause the threaded fittings to leak.

thus the remaining piping will not leak.

Initiated CR.

Table 5-3: Table of Actions Resulting from Area Walk*b~ lnsQections O'l "C "C c: Q)

Q)

"C . *e c: ...

N

>- Action Taken to Area Potentially Adverse Seismic Condition ...O'l

!tl 0 0 z-c:

iO c:

Address the Current Status Q) !tl c:

Condition c 0 0  ::J The walkdown team judged that the tube was not an interaction hazard and would deflect but not break in A 3/8" tube for valve 1SI-881A has a long span (-1 0') Work request AWB 19 X a seismic event. A and is very flexible. initiated to repair.

preliminary calculation of the tubing spans showed that the tubing will not overstress.

Initiated CR.

The walkdown team determined that the On the west wall there is a flexible pipe from Sl-917A condition was not a AWB 19 that appears to bearing on some conduit clamps. The Work request X seismic concern.

hose could dislodge from the clamps and interact with initiated to repair.

There were no soft items below.

targets immediately below. Initiated CR.

The conduit is A conduit for valve 2SI-825C is attached to the flange attached to nearby AWB 19 of a vertical hanger with clamps oriented such that Work request X cable tray JG08 and they are resisting dead load with friction. Clamps initiated to repair.

will not fall. Initiated should be re-orientated.

CR.

The bottom support of the pipe is oriented correctly. There is a A copper instrument air pipe is attached to a vertical support in the AWB 19 hanger with clamps oriented such that they are Work Request X horizontal run at the resisting dead load with friction. The clamps should initiated to repair.

top of the riser. Based be reoriented.

on this the pipe is judged not to fall.

Initiated CR.

Table 5-3: Table of Actions Resulting from Area Walk-bY: lnsQections C'l "C "C  !: Cl)

Cl)

"C I "E N

>- Action Taken to Area Potentially Adverse Seismic Condition ~ 0 0 iii Address the Current Status C'l Cl) z-!:  !:

co Condition c 0 CJ

J The lights were tug There are two lights in the area that are attached to tested and determined AWB 19 structural steel with magnets. It is suggested that the X to be adequately Closed magnets be backed up with lanyards to assure they supported. Initiated will not fall.

CR.

A pipe support in the north west corner of the room was observed to have potential deficiencies. The support is a structural member (W shape) with the The walkdown team weak axis resisting dead load welded to a four bolt judged it to be Being tracked in AWB20 anchor plate at each end. One of the anchors on the X acceptable since the the CAP.

south plate is missing. The west flange of the support support is lightly and about % of the web are notched in three places. loaded. CR initiated.

There is a shackle on the south west anchor on the north plate.

There is a missing anchor bolt on the pipe support Previously identified Work Request AWB27 X west of P-31 A and evaluated in CR. initiated to repair.

There is a missing anchor bolt on the base plate north Previously identified Work Request AWB27 X west of P-31A for a chlorination line. and evaluated in CR. initiated to repair.

Corrosion evaluated by NextEra Closed.

Engineering and Will be tracked AWB27 There is corrosion on P-31A and P-31 B base plates. X determined to minor through structures surface corrosion and monitoring not a concern. CR program.

initiated.

Determined not to be a seismic concern due There is a missing anchor bolt on the base plate Work Request AWB28 X to ruggedness of the northwest of P-35A. initiated to repair.

overall assembly. CR initiated.

Table 5-3: Table of Actions Resulting from Area Walk*b~ lnsQections C'l "0 "0

Q) c Q)

N "0 I'§ ~

Action Taken to c ...

Area Potentially Adverse Seismic Condition ...

!1:1 C'l 0

z-c 0 !1:1 c Address the Current Status Q) !1:1 Condition c 0 c

()  ::J AW828 NextEra Engineering evaluated the condition and determined that the fan is not required to be seismically qualified. The The bottom anchor bolt for W-0028 is not fully Work Request X remaining anchorage engaged. initiated to repair.

was determined to be sufficient anchorage to prevent seismic interaction with seismically qualified equipment. CR initiated.

Determined to have no adverse affect on the design function of the There is loose grout at the northeast corner below Work Request AW828 X support since it is not SW-13. initiated to repair.

in the bearing area of the base plate. CR initiated.

Due to the light load on the support and the A conduit support on the southwest corner of K-38 has remaining anchorage Work Request AW829 X one missing bolt and one loose nut. it was determined to initiated to repair.

be acceptable. CR initiated.

Table 5-3: Table of Actions Resulting from Area Walk-by lnsQections Cl "C "C s::::: Q)

Q) N "C I E >. Action Taken to Area Potentially Adverse Seismic Condition ...cu Cl s:::::

0 0

z-s:::::

iii s:::::

Address the Current Status Q) cu Condition c 0

(.)

s:::::

J It was determined that there is sufficient grout AWB29 There are is a 1" gap in the grout pad on T -33A. X for the bases to Closed perform their design function. CR initiated.

The top of the bolt is about 2 to3 three threads below the top The west nut on T-033A does not have full thread of the nut. The AWB29 X Closed engagement. seismic walkdown team judged that this is sufficient to carry the required loads.

The permanent platform just south of the elevator shaft will prevent the platform The platform just east of the Main Steam Safety Valve from overturning is not anchored to the slab. In some cases there are Work Request AWB39 X during a seismic anchor with no nuts, in other cases there are no initiated to repair.

event. Other anchors at all.

components in the area will prevent the platform from moving.

CR initiated.

Due to the location of the valve stem One of the four anchor bolts on a support for the valve extender and the Work Request AWB44 stem extender is missing. Three of the four bolts are X presences of the three initiated to repair.

installed. remain bolts, it is not a seismic interaction concern. CR initiated.

POINT BEACH NUCLEAR PLANT, UNIT 2 1200114-R-002, REVISION 0 B-12 Table 3 IPEEE and A-46 Outlier Resolution - Unit 2 Outlier Program Equip System Equip Noun Name Status at Time of SRT Outlier Description Interim Resolution Documented Status I Final Required Date No. Class ID Walkdown in 1993 in the USI A-46 Seismic Resolution Close Out Completed Evaluation Report to NRC I 0 cv 2F- Rep Seal 0 - Anchor nuts are not The.nuts for the This is not an operability wo 9815435 SQ-001530 11/6/98 1 39A Water seated. Not an caste in place concern because the attached completed 11/6/98. completed Injection operability concern. anchors are not fully pipe has sufficient flexibility to Removed existing Filter EWR, 6/20/96 - EWR seated. accommodate the displacement nuts, added washers96-040 assigned of the filter. The nuts will be and torqued down seated or washers installed to new nuts on all 4 close up the gaps. The item anchors.

has been walked down for the IPEEE only. Subsequent to the walkdown, it has been screened out using the Seismic PSA screeninq criteria.

A, I 1 480V 2B-42 480v Motor 0 - The connecting bolt The connecting bolt The MCC is considered wo 9606365, SQ-001250 11/13/96 2 Control that connects the that connects the seismically operable because completed 11/13/96 resolves the Center Pab double P1 000 to the double P1 000 to the the other top supports are checked the outlier.

Safeguards strut that is anchored to strut that is sufficient to resist overturning. connecting bolts the wall has either anchored to the wall The bolts will be check tight and tight and replaced loose or missing has either loose or any missing hardware replaced. any missing fastening nuts. T. missing fastening hardware.

Dykstra to submit nuts.

MWR to check tightness, tighten &

replace hardware. WO 9411729. Maintenance to assist with bolt tightness checks 2/20/95. wo submitted to replace missing hardware.

POINT BEACH NUCLEAR PLANT, UNIT 2 1200114-R-002, REVISION 0 B-13 Outlier Program Equip System Equip Noun Name Status at Time of SRT Outlier Description Interim Resolution Documented Status I Final Required Date No. Class ID Walkdown in 1993 in the USI A-46 Seismic Resolution Close Out Completed Evaluation Report to NRC A, I 2 480V 28-03 480v 0- ANCHORAGE 4 Safeguards INSUFFICIENT, Weld The anchorage weld spacing is to large, There is sufficient anchorage capacity in the existing welds to MR 95-006 installed new anchorage (WO SQ-001588, SQ-001532 7/6/99 Load Center spacing is to large. every 3rd cabinet in carry the seismic anchorage 9705903). EWR completed Every 3rd cabinet in some cases. The loads. However, the switchgear 96-042 evaluated some cases. TROLLEY trolley hoist that was declared an outlier because breaker handling HOIST needs to be rides along the top it is not good engineering trolley. EWR closed.

clamped in place. T. of the switchgear practice to transfer the seismic MR 98-095 installed Dykstra to submit poses an interaction loading through the switchgear trolley stops.

separate EWRs for hazard. structure. The switchgear is weld and trolley hoist. considered seismically operable. Modification MR 95-005 is initiated to install new anchorage. The trolley hoist will be evaluated.

A, I 2 480V 28-04 480v 0 - ANCHORAGE The anchorage weld There is sufficient anchorage 6 Safeguards INSUFFICI_ENT, Weld spacing is to large, capacity in the existing welds to MR 95-006 installed new anchorage.

SQ-001589, SQ-001536 7/6/99 Load Center spacing is to large. every 3rd cabinet in carry the seismic anchorage EWR 96-042 completed Every 3rd cabinet in some cases. The loads. However, the switchgear assigned to some cases. TROLLEY trolley hoist that was declared an outlier because evaluated breaker HOIST needs to be rides along the top it is not good engineering handling trolley.

clamped in place, Cub of the switchgear practice to transfer the seismic EWR closed. MR 28-00-328-28-04 has poses an interaction loading through the switchgear 98-095 installed loose material , should hazard. structure. The switchgear is trolley stops.

remove it. T. Dykstra considered seismically to submit separate operable. Modification MR 95-EWRs for weld and 005 is initiated to install new trolley hoist. anchorage. The trolley hoist will be evaluated.

A, I 3 RP 2C-41 Rod Ctl 0 - NOT ANCHORED. The cabinet is not The relay review showed that 7 Mg/Reactor MR in process. MR anchored. there were no essential Reactor MR 94-045 installed new anchorage.

SQ-001537 completed 8/23/96 Trip 8kr 94-045. Candice Curtis Protection System relays Accepted 11/7/95.

Switchgear located in the cabinet. Any Ctl Panel failure of 2C-41 is expected to cause the reactor trip breakers to open, therefore in the safe direction. Modification request MR 94-045 will install new anchorage.

A, I 4 4.16KV 2X-13 8-03 Station 0- ANCHORED WITH The transformer The friction clips provide MR 94-013 installed 9 Service FRICTION CLIPS. MR anchorage uses adequate capacity to withstand new anchorage -

SQ-001800 completed 8/1/97 Transformer in process MR 94-013 friction clips which is the P8NP SSE, because the accepted 11/3/95.

not covered by the friction coefficient exceeds the GIP. seismic demand level. The anchorage will be upgrade under modification MR 94-012.

POINT BEACH NUCLEAR PLANT, UNIT 2 1200114-R-002, REVISION 0 B-14 Outlier Program Equip System Equip Noun Name Status at Time of SRT Outlier Description Interim Resolution Documented Status I Final Required Date No. Class ID Walkdown in 1993 in the USI A-46 Seismic Resolution Close Out Completed Evaluation Report to NRC A,l 4 4.16KV 2X-14 B-04 Station 0- ANCHORED WITH The transformer The friction clips provide MR 94-013 installed SQ-001801 8/1/97 11 Service FRICTION CLIPS. MR anchorage uses adequate capacity to withstand new anchorage - completed Transformer in process. MR 94-013 friction clips which is the PBNP SSE, because the accepted 11/3/95.

not covered by the friction coefficient exceeds the GIP. seismic demand level. The anchorage will be upgrade under modification MR 94-012.

A, I 5 Sl 2P- Containment 0 - Failed Anchorage The anchor J-bolts A calculation per ACI 318-63 S&A Calc 91C2696- SQ-1807 11/12/02 17 14A Spray Pump Calc PIPE LOAD ON have an embedment and ACI 349-80 Appendix B C-019 uses the completed.

SUCTION NOZZLES < 16D as required by shows that the pump anchorage guidelines from ACI the GIP. has sufficient capacity. 318-63 and ACI 349-80 Appendix B to show that the pump anchorage has sufficient capacity.

A, I 5 Sl 2P- Containment 0- Failed Anchorage The anchor J-bolts A calculation per ACI 318-63 S&A Calc 91 C2696- SQ-1828 11/12/02 19 148 Spray Pump Calc PIPE LOAD ON have an embedment and ACI 349-80 Appendix B C-019 uses the completed.

SUCTION NOZZLES < 16D as required by shows that the pump anchorage guidelines from ACI the GIP. has sufficient capacity. 318-63 and ACI 349-80 Appendix B to show that the pump anchorage has sufficient capacity.

20 A, I 6 sw P-32A Service 0 - Anchorage/capacity The pump extending The pump is considered S&A Calc 91 C2696- SQ-1808 6/15/99 Water Pump check on bolts & studs, casing is 34' long > operable based on original C-012 shows pump completed.

restraint of overhead the 20' allowable. design calculations. S&A shaft stresses within trolley, The overhead crane calculation 91C2696-C-012 limits. EWR 96-041 poses an interaction shows that the pump shaft evaluated the hazard. stress is within allowable limits. overhead hoist.

Concluded that the existing configuration does not present an interaction hazard to the SW pumps -

completed 12/5/96.

POINT BEACH NUCLEAR PLANT, UNIT 2 1200114-R-002, REVISION 0 B-15 Outlier Program Equip System Equip Noun Name Status at Time of SRT Outlier Description Interim Resolution Documented Status I Final Required Date No. Class ID Walkdown in 1993 in the USI A-46 Seismic Resolution Close Out Completed Evaluation Report to NRC A, I 6 sw P-328 Service 0 -Anchorage/capacity The pump extending The pump is considered S&A Calc 91C2696- SQ-1809 6/15/99 21 Water Pump check on bolts & studs, casing is 34' long > operable based on original C-012 shows pump completed.

restraint of overhead the 20' allowable. design calculations. S&A shaft stresses within trolley, The overhead crane calculation 91 C2696-C-012 limits. EWR 96-041 poses an interaction shows that the pump shaft evaluated the hazard. stress is within allowable limits. overhead hoist.

Concluded that the existing configuration does not present an interaction hazard to the SW pumps -

completed 12/5/96.

A, I 6 sw P-32C Service 0 - Anchorage/capacity The pump extending The pump is considered S&A Calc 91 C2696- SQ-1810 6/15/99 22 Water Pump check on bolts & studs, casing is 34' long > operable based on original C-012 shows pump completed.

restraint of overhead the 20' allowable. design calculations. S&A shaft stresses within trolley, The overhead crane calculation 91 C2696-C-O 12 limits. EWR 96-041 poses an interaction shows that the pump shaft evaluated the hazard. stress is within allowable limits. overhead hoist.

Concluded that the existing configuration does not present an interaction hazard to the SW pumps -

completed 12/5/96.

A, I 6 sw P-32D Service 0 - Anchorage/capacity The pump extending The pump is considered S&A Calc 91C2696- SQ-1811 6/15/99 23 Water Pump check on bolts & studs, casing is 34' long > operable based on original C-012 shows pump completed.

restraint of overhead the 20' allowable. design calculations. S&A shaft stresses within trolley, The overhead crane calculation 91C2696-C-012 limits. EWR 96-041 poses an interaction shows that the pump shaft evaluated the hazard. stress is within allowable limits. overhead hoist.

Concluded that the existing configuration does not present an interaction hazard to the SW pumps -

completed 12/5/96.

POINT BEACH NUCLEAR PLANT, UNIT 2 1200114-R-002, REVISION 0 B-16 Outlier Program Equip System Equip Noun Name Status at Time of SRT Outlier Description Interim Resolution Documented Status I Final Required Date No. Class ID Walkdown in 1993 in the USI A-46 Seismic Resolution Close Out Completed Evaluation Report to NRC 24 A, I 6 sw P-32E Service 0 - Anchorage/capacity The pump extending The pump is considered S&A Calc 91 C2696- SQ-1812 6/15/99 Water Pump check on bolts & studs, casing is 34' long > operable based on original C-012 shows pump completed.

restraint of overhead the 20' allowable. design calculations. S&A shaft stresses within trolley, The overhead crane calculation 91 C2696-C-012 limits. EWR 96-041 poses an interaction shows that the pump shaft evaluated the hazard. stress is within allowable limits. overhead hoist.

Concluded that the existing configuration does not present an interaction hazard to the SW pumps -

completed 12/5/96.

25 A, I 6 sw P-32F Service 0 - Anchorage/capacity The pump extending The pump is considered S&A Calc 91C2696- SQ-1813 6/15/99 Water Pump check on bolts & studs, casing is 34' long > operable based on original C-012 shows pump completed.

restraint of overhead the 20' allowable. design calculations. S&A shaft stresses within trolley, The overhead crane calculation 91 C2696-C-012 limits. EWR 96-041 poses an interaction shows that the pump shaft evaluated the hazard. stress is within allowable limits. overhead hoist.

Concluded that the existing configuration does not present an interaction hazard to the SW pumps -

completed 12/5/96.

27 A,I,V 7 cs 2CS- Hx-1a Sg 0- Block Wall The valves are The function of the valve is to EWR - Functional Nowalkdown 8/30/00 466 Feedwater interaction adjacent to a large close to isolate feed to the S/Gs. Evaluation. 6/20/96 required, Regulator unanalyzed block The valve is not required to shut - EWR 96-043 SQ-001815 Control wall. The block wall during the 30 second period of assigned to update poses an interaction strong motion. However, it is document complete.

hazard for the valve desired to have it shut during evaluation.

and it sub- the 72 hour8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> recovery period. As Evaluation components. a back up to the valve failing to concluded that this close, the operators can turn off valve is not required the feed pumps and condensate to be on the SSEL.

pumps.

POINT BEACH NUCLEAR PLANT, UNIT 2 1200114-R-002, REVISION 0 B-17 Outlier Program Equip System Equip Noun Name Status at Time of SRT Outlier Description Interim Resolution Documented Status I Final Required Date No. Class ID Walkdown in 1993 in the USI A-46 Seismic Resolution Close Out Completed Evaluation Report to NRC 29 A,I,V 7 cs 2CS- Hx-1b Sg 0- Block Wall The valves are The function of the valve is to EWR- Functional Nowalkdown 8/30/00 476 Feedwater interaction adjacent to a large close to isolate feed to the S/Gs. Evaluation. 6/20/96 required, Regulator unanalyzed block The valve is not required to shut - EWR 96-043 SQ-001817 Control wall. The block wall during the 30 second period of assigned to update poses an interaction strong motion. However, it is document complete.

hazard for the valve desired to have it shut during evaluation.

and it sub- the 72 hour8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> recovery period. As Evaluation components. a back up to the valve failing to concluded that this close, the operators can turn off valve is not required the feed pumps and condensate to be on the SSEL.

pumps.

31 A,I,V 7 cs 2CS- Hx-1a Sg 0- Block Wall The valves are The valve is normally close and EWR - Functional Nowalkdown 8/30/00 480 Regulator interaction adjacent to a large must remain closed to isolate Evaluation. 6/20/96 required, Control unanalyzed block feed to the S/Gs. Therefore, - EWR 96-043 SQ-001819 Bypass wall. The block wall during the 30 second period of assigned to update poses an interaction strong motion, the valve is not document complete.

hazard for the valve required to change state. It is evaluation.

and it sub- not likely, that the block wall Evaluation components. interaction would cause the concluded that this valve to open. As a back up to valve is not required the valve inadvertently opening, to be on the SSEL.

the operators can turn off the feed pumps and condensate pumps.

33 A,I,V 7 cs 2CS- Hx-1b Sg 0- Block Wall The valves are The valve is normally close and EWR - Functional Nowalkdown 8/30/00 481 Regulator interaction adjacent to a large must remain closed to isolate Evaluation. 6/20/96 required, Control unanalyzed block feed to the S/Gs. Therefore, - EWR 96-043 SQ-001821 Bypass wall. The block wall during the 30 second period of assigned to update poses an interaction strong motion, the valve is not document complete.

hazard for the valve required to change state. It is evaluation.

and it sub- not likely, that the block wall Evaluation components. interaction would cause the concluded that this valve to open. As a back up to valve is not required the valve inadvertently opening, to be on the SSEL.

the operators can turn off the feed pumps and condensate pumps.

POINT BEACH NUCLEAR PLANT, UNIT 2 1200114-R-002, REVISION 0 B-18 Outlier Program Equip System Equip Noun Name Status at Time of SRT Outlier Description Interim Resolution Documented Status I Final Required Date No. Class ID Walkdown in 1993 in the USI A-46 Seismic Resolution Close Out Completed Evaluation Report to NRC I,V,RG 7 RM 2RM- Re-211/Re- 0 - Based on visual The valve is located The item has been walked down 12/28/98 - EWR 96- SQ-001986 3/10/98 35 3200A 212 Monitor inspection, the building in a climate control for the IPEEE only. Subsequent 044 complete. ID'd resolves this Return the RMs are located in hut that has no to the walkdown, it has been the anchorage. S&L outlier is not anchored. Need visible base screened out using the Seismic completed calc.

to check any drawings. anchorage. PSA screening criteria. Calculation resolves outlier.

I,V,RG 7 RM 2RM- Re-211/Re- 0 - Based on visual The valve is located The item has been walked down 12/28/98 - EWR 96- SQ-001988 3/10/98 37 3200B 212 Monitor inspection, the building in a climate control for the IPEEE only. Subsequent 044 complete. ID'd resolves this Supply the RMs are located in hut that has no to the walkdown, it has been the anchorage. S&L outlier is not anchored. Need visible base screened out using the Seismic completed calc.

to check any drawings. anchorage. PSA screening criteria. Calculation resolves outlier.

A,I,V 7 Sl 2SI- T-34a Si 0 - UNSUPPORTED TheAOVwas The valve was determined to be Fixed, MWR 935398 SQ-001631 10/22/93 40 839A Accum OPERATOR- mounted on a 3/4" seismically inoperable. The -completed resolves Outlet To Si MODIFIED U2R19- line with the valve operator was supported that 10/22/93 outlier, Test Line Supported operators operator same refueling out under MWR completed Isolation MWR 935398 unsupported 935398 A,I,V 7 Sl 2SI- SiACold 0 - UNSUPPORTED TheAOVwas The valve was determined to be Fixed, MWR 935398 SQ-001632 10/22/93 42 839B Leg To Si OPERATOR- mounted on a 3/4" seismically inoperable. The -completed resolves Test Line MODIFIED U2R19- line with the valve operator was supported that 10/22/93 outlier.

Isolation Supported operators operator same refueling out under MWR Completed MWR935398 unsupported 935398 A,I,V 7 Sl 2SI- T-34b Si 0 - UNSUPPORTED TheAOVwas The valve was determined to be Fixed, MWR 935398 SQ-001633 10/22/93 44 839C Accum OPERATOR- mounted on a 3/4" seismically inoperable. The -completed resolves Outlet To Si MODIFIED U2R19- line with the valve operator was supported that 10/22/93 outlier.

Test Line Supported operators operator same refueling out under MWR completed Isolation MWR935398 unsupported 935398 A,I,V 7 Sl 2SI- SiB Cold 0- UNSUPPORTED TheAOVwas The valve was determined to be Fixed, MWR 935398 SQ-001634 10/22/93 46 839D Leg To Si OPERATOR- mounted on a 3/4" seismically inoperable. The -completed resolves Test Line MODIFIED U2R19- line with the valve operator was supported that 10/22/93 outlier.

Isolation Supported operators operator same refueling out under MWR Completed MWR 935398 unsupported 935398

POINT BEACH NUCLEAR PLANT, UNIT 2 1200114-R-002, REVISION 0 B-19 Outlier Program Equip System Equip Noun Name Status at Time of SRT Outlier Description Interim Resolution Documented Status I Final Required Date No. Class ID Walkdown in 1993 in the USI A-46 Seismic Resolution Close Out Completed Evaluation Report to NRC I,V,RG 7 Sl 281- T-34a/B Si 0 - 36" offset on 1.25" 50 846 Accum line. Because of pipe The AOV offset of 36" < 45" allowable The item has been walked down for the IPEEE only. Subsequent MR 94-066 was installed during SQ-001829 completed 2/6/96 Nitrogen Inlet support configuration, offset for a 1" line. to the walkdown, it has been U2R21. The pipe Control potential for pipe However, because screened out using the Seismic was moved to overstress. Valve is of the pipe support PSA screening criteria. eliminated rubbing considered operable - configuration, there Modification request MR 94- on adjacent pipe.

attached conduit will is a potential for pipe 066*B is initiated to upgrade the New supports were stabflize valve. overstress. support of the 1" line. installed on the valve operator and on each side of the valve. S&L analysis WE-200118, Rev. 0 I,V 7 Sl 2SI- T-34a/B Si 0- Yoke U-bolt The valve operator 51 957 Accum missing, MWR yoke U-bolt was The valve was considered seismically operable based on a Fixed, WO 935298 installed a new U-SQ-001635 resolves 10/10/94 Nitrogen submitted 7/25/94- U- missing. calculation that showed the pipe bolt. Completed outlier.

Header Vent bolt to be installed stress was< 2Sy. The valve 10/10/94 Completed Control U2R20 10/18/94 - U- operator U-bolt was installed Bolt installed 10/7/94 during the next refueling outage W0935298 under Word Order 935298 I,RG 7 WG 2WG- T-16 Rcdt 0- Even though 15" The AOV offset of The item has been walked down 53 1786 Vent offset < 45" GIP 15" < 45" allowable for the IPEEE only. Subsequent EWR 96-050 assigned - valves SQ-001777 resolves this 1/14/00 allowable for a 1" there offset for a 1" line. to the walkdown, it has been have been as-built, outlier is a potential for pipe However, because screened out using the Seismic 9/3/98. Need to overstress in line 1"- of the pipe support PSA screening criteria. draft sketch for valve WD-151R-1 because of configuration, there supports. 4/1/99-how the 1" line is is a potential for pipe MR 96-035will supported. Check overstress. install operator offset, 1WG-1786 support. WO offset measured at 24" 9904476.

EWR Installation complete.

I,RG 7 WG 2WG- T-16 Rcdt 0 - Even though 15" The AOV offset of The item has been walked down 55 1787 Vent offset< 45" GIP 15" < 45" allowable for the IPEEE only. Subsequent EWR 96-050 assigned - valves SQ-001778 resolves this 1/14/00 allowable for a 1" there offset for a 1" line. to the walkdown, it has been have been as-built, outlier is a potential for pipe However, because screened out using the Seismic 9/3/98. Need to overstress in line 1"- of the pipe support PSA screening criteria. draft sketch for valve WD-151R-1 because of configuration, there supports. 4/1/99-how the 1" line is is a potential for pipe MR 96-035 will supported. Check overstress. install operator offset, 1WG-1787 support. WO offset measured at 24" 9904476.

EWR Installation complete.

POINT BEACH NUCLEAR PLANT, UNIT 2 1200114-R-002, REVISION 0 B-20 Outlier Program Equip System Equip Noun Name Status at Time of SRT Outlier Description Interim Resolution Documented Status I Final Required Date No. Class ID Walkdown in 1993 in the USI A-46 Seismic Resolution Close Out Completed Evaluation Report to NRC A, I 8 Sl 2SI- P-15b Si 0 - Valve body not The valve was The piping analysis, Accession EWR 96-045 SQ-001636 3/27/97 57 878A Pump R-1 shimmed. MSA supported by the # - WE-200084, shows that the assigned to resolves Reactor evaluated. Considered valve operator but valve will not be overstressed. document resolution. outlier.

Vessel acceptable. Accession not the valve body. NRC RAI asked for Injection # - WE-200084 In addition, the gap piping analysis.

between the valve Resolved.

body and the gravity support stanchion is not properly shimmed A, I 8 Sl 2SI- P-15a Si 0 - Valve body not The valve was The piping analysis, Accession EWR 96-045 SQ-001637 3/27/97 59 8788 Pump Loop shimmed. MSA supported by the #- WE-200084, shows that the assigned to resolves B Injection evaluated. Considered valve operator but valve will not be overstressed. document resolution. outlier.

acceptable. Accession not the valve body. NRC RAI asked for

1. - WE-200084 In addition, the gap piping analysis.

between the valve Resolved.

body and the gravity support stanchion is not properly shimmed A, I 8 Sl 2SI- P-15b Si 0 - Valve body not The valve was The piping analysis, Accession EWR 96-045 SQ-001638 3/27/97 61 878C Pump R-1 shimmed. MSA supported by the #- WE-200084, shows that the assigned to resolves Reactor evaluated. Considered valve operator but valve will not be overstressed. document resolution. outlier.

Vessel acceptable. Accession not the valve body. NRC RAI asked for Injection #- WE-200084 In addition, the gap piping analysis.

between the valve Resolved.

body and the gravity support stanchion is not properly shimmed A, I 8 Sl 2SI- P-15a Si 0- Valve body not The valve was The piping analysis, Accession EWR 96-045 SQ-001639 3/27/97 63 878D Pump Loop shimmed. MSA supported by the # - WE-200084, shows that the assigned to resolves A Injection evaluated. Considered valve operator but valve will not be overstressed. document resolution. outlier.

acceptable. Accession not the valve body. NRC RAI asked for

1. - WE-200084 In addition, the gap piping analysis.

between the valve Resolved.

body and the gravity support stanchion is not properly shimmed

POINT BEACH NUCLEAR PLANT, UNIT 2 1200114-R-002, REVISION 0 B-21 Outlier Program Equip System Equip Noun Name Status at Time of SRT Outlier Description Interim Resolution Documented Status I Final Required Date No. Class ID Walkdown in 1993 in the USI A-46 Seismic Resolution Close Out Completed Evaluation Report to NRC A, I 10 VNAFW HX-66 Auxiliary 0 - Rubber isolators The air handling unit HX-66 is on the SSEL to EWR 96-046 SQ-001672. 6/18/99 64 Feed Pump fail. They do not have is mounted on maintain SW system integrity. assigned. MR 97- Outlier is Area Cooler sufficient shear and rubber vibration The air handling and air cooling 104 installed resolved.

tension capacity to isolators. The function is not required. The SW replacement transfer the anchor anchorage system engineer judged that a vibration isolators.

loads to the concrete calculation break in the attached 2" SW Accepted 2/28/98.

expansion anchors. concluded that the line would not significantly rubber isolators had impact service water to other insufficient capacity essential loads. The function of to transfer the the air handling unit will be anchorage loads to evaluated to determine if an the concrete anchorage upgrade is required.

expansion anchors.

A, I 10 VNAFW HX- Auxiliary 0 - The Spring isolator The air handling unit HX-66A is on the SSEL to EWR 96-047 SQ-001888 12/14/00 65 66A Feed Pump base plate yields. is mounted on spring maintain SW system integrity. assigned. MR 98- Outlier is Area Cooler vibration isolators. The air handling and air cooling 127 initiated. (RE: resolved.

The anchorage function is not required. The SW DNC) 2/11/99 -

calculation system engineer judged that a NeedWO. WO determined that the break in the attached 2" SW 9808637 is replacing spring isolator base line would not significantly HX-66A cooling plate will yield. impact service water to other coils. Work essential loads. The function of complete.

the air handling unit will be evaluated to determine if an anchorage upgrade is required.

66 A, I 10 sw HX-98 Residual 0 - Mounted on The air handling unit HX-98 is on the SSEL to EWR 96-048 SQ-001841. 9/19/00 Heat Neoprene pads. Pads is mounted on maintain SW system integrity. assigned. MR 97- Outlier is Removal need further eval per rubber vibration The air handling and air cooling 105 installed. WO resolved.

Pump Area GIP Section 4.4. isolators. The function is not required. The SW 9807185 replaced Cooling Coil Evaluation by S&A? anchorage system engineer judged that a HX-98 cooling coils.

5/22/95 - During the calculation break in the attached 2 1/2" SW bolt tightness check on concluded that the line would not significantly 2/20/95, the concrete rubber isolators had impact service water to other expansion anchors for insufficient capacity essential loads. The function of the left rear rubber to transfer the the air handling unit will be vibration isolator were anchorage loads to evaluated to determine if an found to be never the concrete anchorage upgrade is required.

installed expansion anchors.

POINT BEACH NUCLEAR PLANT, UNIT 2 1200114-R-002, REVISION 0 B-22 Outlier Program Equip System Equip Noun Name Status at Time of SRT Outlier Description Interim Resolution Documented Status I Final Required Date No. Class ID Walkdown in 1993 in the USI A-46 Seismic Resolution Close Out Completed Evaluation Report to NRC A,I,H 11 VNCSR HX- Cable 0 - No Anchorage, The chiller unit is not The chiller is on the SSEL to EWR 96-052 SQ-001957 5/19/02 69 38A1, Spreading Motor on steel isolation anchored, the maintain SW integrity. A leak in assigned. Chiller Outlier is A2,A3 Room Air springs. ISRS exceeds compressor motors the SW pipe would not HX-038A replaced. resolved.

Conditioning RS. New component are on springs, and significantly affect SW flow to MR 97-049*8 Unit 7/13/94. It is the the seismic demand other essential loads. The installed new heat parent component of exceeds 1.5 x 8S at HVAC room is designed to exchangers.

HX-38A 1, HX-38A2 the low frequency handle that flooding from a SW and HX-38A3. peak. break. The chill water cooling Equipment class function of the unit is not changed from 21 to 11 required. The function of the chiller unit will be evaluated to determine if an anchorage upgrade is required.

A,I,H 11 VNCR HX- Control 0 - No Anchorage, The chiller unit is not The chiller is on the SSEL to EWR 96-051 SQ-001962 8/15/02 70 3881, Room Air Motor on steel isolation anchored, the maintain SW integrity. A leak in assigned. Chiller Outlier is 82,83, Conditioning springs. ISRS exceeds compressor motors the SW pipe would not HX-0388 replaced. resolved.

84 Unit RS. New component are on springs, and significantly affect SW flow to MR 97-049*C 7/13/94. It is the the seismic demand other essential loads. The installed new heat parent component of exceeds 1.5 x 8S at HVAC room is designed to exchangers.

HX-3881, HX-3882, the low frequency handle that flooding from a SW HX-3883 and HX- peak. break. The chill water cooling 3884. Equipment function of the unit is not class changed from 21 required. The function of the to 11 chiller unit will be evaluated to determine if an anchorage upgrade is required.

A, I 12 DA K-48 G-02 EDG 0 - Loose hand crank A loose hand crank Hand crank installed on a Hand crank installed SQ-001822 4/21/95 71 Starting Air resting against it which was resting against bracket on the wall adjacent to on a bracket on the Outlier is Compressor may pose an the air compressor the air compressor wall adjacent to the resolved.

Motor Or interaction hazard. posing an air compressor Diesel 4/21/95- a hand crank interaction hazard.

mount has been installed on the wall adjacent to the compressor

POINT BEACH NUCLEAR PLANT, UNIT 2 1200114-R-002, REVISION 0 B-23 Outlier Program Equip System Equip Noun Name Status at Time of S RT Outlier Description Interim Resolution Documented Status I Final Required Date No. Class ID Walkdown in 1993 in the USI A-46 Seismic Resolution Close Out Completed Evaluation Report to NRC A, I 16 125V D-07 Station 0- Interaction, The battery charger 72 Battery CABINET IS NOT is not attached to the The battery charger does not contain essential relays, and MR 94-048 bolted D-07 to the old 2A-05.

SQ-001938 Outlier is 12/13/00 Charger TIED TO ADJACENT adjacent switchgear. there are 3 switchgear cubicles WO 9904504. resolved.

CABINET, ALSO between the battery charger and BLOCK WALL MAY switchgear cubicle that contains GOVERN HCLPF. the essential relays. Therefore, EWR submitted 2/4/94 the battery charger and the for CSE to bolt battery switchgear are considered charger to adjacent seismically operable.

switchgear. MR 94- Modification Request MR 94-048 048 has be initiated to bolt these t~ether.

A, I 16 125V D-08 Station 0- Interaction, The battery charger The battery charger does not 73 Battery CABINET IS NOT is not attached to the contain essential relays, and MR 94-048 bolted D-08 to 1A-05. wo SQ-001939 Outlier is 12/13/00 Charger TIED TO ADJACENT adjacent switchgear. there are 3 switchgear cubicles 9504505. resolved.

CABINET, ALSO between the battery charger and BLOCK WALL MAY switchgear cubicle that contains GOVERN HCLPF. the essential relays. Therefore, EWR submitted 2/4/94 the battery charger and the for CSE to bolt battery switchgear are considered charger to adjacent seismically operable.

switchgear. MR 94- Modification Request MR 94-048 048 has be initiated to bolt these together.

A, I 16 y DY-OA Red 125v 0 - Interaction; The outlier is an The inverter does not contain 74 Dc/120v Ac Mounted directly interaction. DY-OA any essential relays. It is IEEE MR 96-037 assigned to move inverter to SQ-001867 Outlier is 5/25/00 Alternate adjacent to 1C-167. is mounted directly 344-1975 qualified. It is create a gap resolved.

Inverter The cabinets are not adjacent to 1C-167. considered seismically operable between inverter fastened together. P- The cabinets are not based on there being no and relay cabinet.

REPORT fastened together. instances of inverter failure due wo 9805184.

to impact in the earthquake Installation experience database. The complete.

inverter will be fastened to the acfjacent cabinet.

A, I 16 y DY-OB Blue 125v 0- Interaction; The outlier is an The inverter does not contain 75 Dc/120v Ac Mounted directly interaction. DY-OB any essential relays. It is IEEE MR 96-037*A assigned to move SQ-001868 Outlier is 5/25/00 Alternate adjacent to 2C-156. is mounted directly 344-1975 qualified. It is inverter to create a resolved.

Inverter The cabinets are not adjacent to 2C-157. considered seismically operable gap between fastened together. P- The cabinets are not based on there being no inverter and relay REPORT fastened together. instances of inverter failure due cabinet. WO to impact in the earthquake 9805185.

experience database. The Installation complete inverter will be fastened to the adjacent cabinet.

POINT BEACH NUCLEAR PLANT, UNIT 2 1200114-R-002, REVISION 0 B-24 Outlier Program Equip System Equip Noun Name Status at Time of SRT Outlier Description Interim Resolution Documented Status I Final Required Date No. Class ID Walkdown in 1993 in the USI A-46 Seismic Resolution Close Out Completed Evaluation Report to NRC A,I,RG 19 RC 2TE- Rc Loop A 0 - Impinging on The temperature An engineering evaluation MR 95-021 initiated SQ-001570 2/24/99 76 4508 Hot Leg insulation. Does element is impinging showed that thermal expansion to replace TE with a Outlier is Temperature thermal expansion on insulation. It must did not accommodate the bent unit. resolved.

Rtd while hot be determined if expected seismic Scheduled for accommodate seismic thermal expansion displacements. Modification U2R23 (RE: PHB) displacements? EWR while hot request MR 95-021 is initiated to Replacement TE submitted for MSA accommodate replace TE with a shorter one. installed U2R23 inspection/evaluation seismic EWR 94-056. EWR displacements.

determined that interaction was a problem, Calc N 168. MR 95-021 initiated to replace TE.

A,I,RG 19 RC 2TE- Rc Loop A 0 - Impinging on The temperature An engineering evaluation MR 95-021 initiated SQ-001571 2/24/99 77 450D Hot Leg insulation. Does element is impinging showed that thermal expansion to replace TE with a Outlier is Temperature thermal expansion on insulation. It must did not accommodate the bent unit. resolved.

Rtd while hot be determined if expected seismic Scheduled for accommodate seismic thermal expansion displacements. Modification U2R23 (RE: PHS) displacements? EWR while hot request MR 95-021 is initiated to Replacement TE submitted for MSA accommodate replace TE with a shorter one. installed U2R23 inspection/evaluation. seismic EWR 94-056 EWR displacements.

determined that interaction was a problem, Calc N 168. MR 95-021 initiated to replace TE.

POINT BEACH NUCLEAR PLANT, UNIT 2 1200114-R-002, REVISION 0 B-25 Outlier Program Equip System Equip Noun Name Status at Time of SRT Outlier Description Interim Resolution Documented Status I Final Required Date No. Class ID Walkdown in 1993 in the USI A-46 Seismic Resolution Close Out Completed Evaluation Report to NRC A,I,RG 20 MMS C Main Control 0- Interaction, An adjacent supply The supply cabinet was 79 1(2)C- Boards adjacent supply cabinet posed a attached to the back of 2C-03 Fixed, MR 94-021 bolted supply SQ-001824 Outlier is 8/24/94 04 cabinets not secured. spatial interaction under modification MR 94-021. cabinets to the back resolved.

EWR submitted. hazard. of 1C-03 and 2C-03.

7/25/94- Supply cabinets secured.

1/18/95- MR 94-021 installed 6/9/94 resolves interaction concern. Item identified during MCB walkdown 12/90-Overhead lights and duct above control room restrained by chains or light metal straps that are sometimes hooked with open ended hooks.

SRT not concerned that duct or lights pose a structural hazard, however, they may pose an operator (human injury) hazard.

81 A, I 20 lOPS 2C-75 Turbine lops 0 - Doors are not The doors are not The cabinet does not contain wo 9607850 SQ-001826 12/796 Main Trip positively latched. T. positively latched. any essential relays, and the installed new handle Outlier is Panel Dykstra to submit doors are fairly light weight -completed 12/7/96 resolved.

MWR after inspection. therefore, significant damage is 6/19/95 - Need to not expected to occur. I & C will discuss with Steve be contacted to determine if the Bowe to see if he existing door latch can be used would rather install or whether a new handle would different handles or be preferred.

have I&C start using the key lock to latch the door. 9/23/96- wo 9607849 A, I 20 MMS 2C- Plant 0 - Interaction- Supply An adjacent supply The supply cabinet was Fixed, MR 94-021 83 105- Process I&C cabinet interference cabinet posed a attached to the back of 2C-03 bolted supply SQ-001830 completed.

8/24/94 114 Cabinets EWR submitted. spatial interaction under modification MR 94-021. cabinet to the back 1/18/95- MR 94-021 hazard. of 2C-03. Accepted installed 6/9/94 7/28/94 resolves interaction concern.

POINT BEACH NUCLEAR PLANT, UNIT 2 1200114-R-002, REVISION 0 B-26 Outlier Program Equip System Equip Noun Name Status at Time of SRT Outlier Description Interim Resolution Documented Status I Final Required Date No. Class ID Walkdown in 1993 in the USI A-46 Seismic Resolution Close Out Completed Evaluation Report to NRC A, I 20 RP 2C- Rp Train A 0- ANCHOR DETAIL The anchor detail for Since the cabinet has MR 95-008 SQ-001604 12/2/97 86 151- Relay Unknown. No specific the grout pad and anchorage as originally upgraded the Outlier is 155 Cabinets information on the the perimeter designed, it is considered anchorage. Outlier resolved.

grout pad to concrete channel is unknown. seismically operable. Resolved floor anchorage. Modification request MR 95-008 Needs EWR will upQrade the anchoraQe.

A, I 20 ESF 2C- Safeguards 0- Interaction; The outlier is an No "bad actor" relays are MR 96-037*A SQ-001870 5/25/00 88 156- Train A Mounted directly Interaction. The located in the cabinets. The assigned to move Outlier is 158 Relay adjacent to inverter cabinets are relays in the cabinets have a inverter to create a resolved.

Cabinets DY-OB. The cabinets mounted directly seismic capacity of at least 4 gap between are not fastened adjacent to inverter g's. Therefore, they are inverter and relay together. P-REPORT DY-OB. The considered seismically cabinet. WO Provide Mod Package cabinets are not operable. The cabinet will be 9805184.

fastened together. fastened to the adjacent Installation inverter. complete.

A, I 20 RP 2C- Rp Train B 0- ANCHOR DETAIL The anchor detail for Since the cabinet has MR 95-010 SQ-001605 12/2/97 91 161- Relay Unknown. No specific the grout pad and anchorage as originally cancelled, work Outlier is 165 Cabinets information on the the perimeter designed, it is considered combined with MR resolved.

grout pad to concrete channel is unknown. seismically operable.95-008. MR 95-008 floor anchorage. Modification request MR 95-010 upgraded the Needs EWR will upgrade the anchorage. anchorage. Outlier Resolved.

A, I 20 ESF 2C- Safeguards 0- ANCHOR DETAIL The anchor detail for Since the cabinet has MR 95-012 SQ-001833 12/2/97 92 166- Train BAnd Unknown. No specific the grout pad and anchorage as originally cancelled - work Outlier is 167 Mise Relay information on the the perimeter designed, it is considered transferred to MR resolved.

Cabinets grout pad to concrete channel is unknown. seismically operable.95-008. MR 95-008 floor anchorage. Modification request MR 95-012 upgrade the Overhead light S-clamp will upgrade the anchorage. anchorage, needs to be clamped accepted 10/25/95.

down. Needs EWR W096-0001 (completed 5/3/96) inspected for open S-hooks on lighting in the CSR.

5 open S-hooks found and all were closed.

POINT BEACH NUCLEAR PLANT, UNIT 2 1200114-R-002, REVISION 0 B-27 Outlier Program Equip System Equip Noun Name Status at Time of SRT Outlier Description Interim Resolution Documented Status I Final Required Date No. Class ID Walkdown in 1993 in the USI A-46 Seismic Resolution Close Out Completed Evaluation Report to NRC A, I 20 COMP C-178- Computer 0 - Line Printer Line Printer, LP-300, C-178-179 are computer 12130198 - Have SQ-001834 12130198 93 179 Input Mux adjacent to cabinet is kept on the floor cabinets contain primarily solid inspected the Outlier is adjacent to the state and circuit board Computer Room on resolved.

cabinet. components. There are no numerous occasions essential relays in the cabinets. since the USI A-46 The cabinets are considered walkdown. The seismically operable. I&C will printer has been store the printer in a different relocated. No location and have it adjacent to interaction hazards the cabinets only when being were identified.

used.

A,I,C 21 RH 2HX- Residual 0 - Base bolt nuts not The caste in place Not an operability concern since EWR 96-053 SQ-001835 6118199 94 11A Heat seated. 114" to 318" anchor bolt nuts are HX is top supported in both assigned. WO Outlier is Removal gaps. Not an not fully seated. lateral directions. 9815436 initiated to resolved.

Heat operability concern There are 114" to inspect I replace Exchanger since HX is top 318" gaps between anchor bolt nuts.

supported in both the nut and the HX WO complete lateral directions. foot.

96 A,I,C 21 cc 2T-12 Component 0 - Oversized anchor The saddle There are large washers MR 94-091*C SQ-001837 815196 Cooling bolt holes (2.25" x anchorage on both between the anchorage nut and installed 112" steel Outlier is Surge Tank 1.18") identified from ends of the tank has the oval holes. Therefore, some plate under each of resolved.

WEST 685J 114. oversized anchor load will be transferred to all of the nuts on the Anchor bolts are 1" bolt holes (2.25" x the anchor bolts. In addition, the south side of the diameter. Too much 1.18") identified from attached piping will help in tank. The plate is clearance to say WEST 685J114. The restraining the tank. Therefore, welded to the seismic load is anchor bolts are 1" the tanks are considered saddle. The transferred to enough diameter. Therefore, seismically operable. The installation was anchor bolts. there is too much anchorage will be upgraded with checked 1213197 clearance to say a structural member between seismic load is the tank base and the anchor transferred evenly to bolt.

enough anchor bolts

POINT BEACH NUCLEAR PLANT, UNIT 2 1200114-R-002, REVISION 0 B-28 Outlier Program Equip System Equip Noun Name Status at Time of SRT Outlier Description Interim Resolution Documented Status I Final Required Date No. Class ID Walkdown in 1993 in the USI A-46 Seismic Resolution Close Out Completed Evaluation Report to NRC A, I 21 Sl 2T-13 Refueling 0- The tank does not 98 Water ANALYSIS/REINFORC pass the screening The tank has been analyzed using a finite element analysis In WE NRC RAI response NPL 97-SQ-001909 Outlier is 4/18/01 Storage EMENT 7/25/94- criteria of Section 7 [23]. 0450, page 5 of 22, resolved.

Tank W/6 Received DRAFT of the GIP. WE stated that the Immersion analysis from S& A design margin from Htrs showing RWST has the A-46 analysis is sufficient capacity. not sufficient. EWR 97-169 assigned.

MR 99-041 upgraded RWST.

MR 00-0052 replaced tank vent FME screen with a new screen.

A, I 21 DA T-61F G-02 Edg 0 - Anchor - cracked The grout under the An inspection subsequent to the WO- 9501221 99 Starting Air grout foot of one of the air seismic verification walkdown completed 5/23/97 -

SQ-001838 resolves the 5/23/97 Receiver receiver tank legs is found a steel spacer plate under installed new grout outlier cracked. the leg of the tank. Therefore the grout is not structural and the tank is considered seismically operable. The leg will be re-qrouted.

A, I 22 AUX8 Pab 8' Cable LAR 9 is an Work completed SQ-001714 100 FTAR & Conduit OUTLIER because under MR 96-022. resolves the 8/1/00 EA Raceways it does not meet the Post installation outlier requirements of walkdown complete.

Section 8.0 of the wo 9808941 GIP. See S&A's LAR - Cable Tray and Conduit Supports Report, 91C2696-C-018.

A, I 22 SPRE Csr Cable & LAR 3 & LAR 4 are MR 96-080 created SQ-001881 101 AD IN Conduit OUTLIER(s) to upgrade cable Outlier is 9/25/00 GRM Raceways because it does not tray supports in the resolved.

meet the CSR (RE: DNC).

requirements of Installation complete Section 8.0 of the GIP. See S&A's LAR - Cable Tray and Conduit Supports Report, 91 C2696-C-018.

POINT BEACH NUCLEAR PLANT, UNIT 2 1200114-R-002, REVISION 0 B-29 Outlier Program Equip System Equip Noun Name Status at Time of SRT Outlier Description Interim Resolution Documented Status I Final Required Date No. Class ID Walkdown in 1993 in the USI A-46 Seismic Resolution Close Out Completed Evaluation Report to NRC A, I 22 U2C46 U2c46' 0 - Cables not tied to There is an isolated Resolved during SQ-001640 1/8/99 105 FTAR Cable & tray vertical cable tray U2R23. WO resolves EA Conduit which has no plastic 9713098. Verified outlier Raceways ties and the cables during walkdown.

appear to be hanging out of it, hence it is an outlier, see figure 18.

A,I,RG 3 4.16KV 2A-05 4.16 KvBus SAT-0-WELD Weld inspection NOT AN 12/13/00 108 Switchgear QUALITY IN completed, used OUTLIER-(Safeguards) QUESTION, results to adjust resolved w/

Recommend thorough anchorage capacity weld weld inspection. T. in the anchorage inspection Dykstra to check with calculation. and QA about weld anchorage inspections calc.

A,I,RG 3 4.16KV 2A-06 4.16 Kv Bus PO - Not fastened to MR 94-048 SQ-001938 12/13/00 110 (old) Switchgear adjacent D-07 battery connected cabinets Outlier is (Safeguards) charger. WELD together. WO resolved.

QUALITY IN 9904504.

QUESTION, Recommend thorough weld inspection. T.

Dykstra to check with QA about weld inspections. 11/7/94-Renamed to 1A-06 (old). The old 1A-05 and old 1A-06 will be hard tied together A,I,V 7 Sl 2SI- Si Test Line SAT Attached Resolved NOT AN 11/11/94 114 8978 Return copper lines too stiff. OUTLIER-Second Off T. Dykstra to evaluate Resolved on Isolation failure if copper line original breaks. Valve currently SEWS gagged open during normal operation. P-MAT 11/11/94 Update

- Valve walked down again 9/26/94. SRT confirmed that copper line was too st

POINT BEACH NUCLEAR PLANT, UNIT 2 1200114-R-002, REVISION 0 B-30 Outlier Program Equip System Equip Noun Name Status at Time of SRT Outlier Description Interim Resolution Documented Status I Final Required Date No. Class ID Walkdown in 1993 in the USI A-46 Seismic Resolution Close Out Completed Evaluation Report to NRC 116 A,I,C 8 cc 2CC- T-12 Cc PO- pipe has NOT AN OUTLIER- NOT AN 3/30/01 815 Surge Tank insufficient supports - CCW Upgrade OUTLIER-Emergency 11/11/94 update- identified these Resolved on Makeup STATUS changed to valves as having original Water Inlet outlier. Valves also insufficient support. - SEWS identified as having MR 94-091 installed insufficient pipe valve support.

support adjacent to Verified installation valve during the CCW 12/3/97 Upgrade piping walkdowns. PO - 3g required to qualify valve yoke. Trapeze supports may allow valve yoke to swing resulting in possible pipe failure 117 A, I 8 sw SW- K-3a Sa SAT Attached Resolved NOT AN 10/26/94 2832A Compressor conduit is very flexible OUTLIER-

-S Inlet and should be Resolved on Solenoid restrained. Check with original Frank Mueller about SEWS SW piping replacement.

Rewalked 10/26/94 by SR StAmour and W Djordjevic. Determined flexibility was not a problem.

A, I 15 125V D-05 125v De SAT- 0-SPACER, Resolved 118 Station Need battery cell type NOT AN OUTLIER-1/18/95 Battery information. EWR Resolved on submitted 2/4/94 for original ESE to install SEWS styrofoam bead spacers. 7/25/94 -

EWR cancelled. T.

Dykstra to submit MWR to install spacers. 1/18/95-Qual report shows batteries shake table tested in same

POINT BEACH NUCLEAR PLANT, UNIT 2 1200114-R-002, REVISION 0 B-31 Outlier Program Equip System Equip Noun Name Status at Time of SRT Outlier Description Interim Resolution Documented Status I Final Required Date No. Class ID Walkdown in 1993 in the USI A-46 Seismic Resolution Close Out Completed Evaluation Report to NRC A, I 15 125V D-06 125v De SAT- 0-SPACER. Resolved NOT AN 1/18/95 119 Station EWR submitted 2/4/94 OUTLIER-Battery for ESE to install Resolved on styrofoam bead original spacers. 7/25/94- SEWS EWR cancelled. T.

Dykstra to submit MWR to install spacers. 1/18/95-Qual report shows batteries shake table tested in same configuration at PBNP.

No addition A, I 15 125V D-305 Swing SAT- 0-SPACER. Resolved NOT AN 1/18/95 120 Station EWR submitted 2/4/94 OUTLIER-Battery for ESE to install Resolved on styrofoam bead original spacers. 7/25/94- SEWS EWR cancelled. T.

Dykstra to submit MWR to install spacers. 1/18/95-Qual report shows batteries shake table tested in same configuration at PBNP.

No addition 121 A,I,C 18 cc Fl-643 K-1a Waste SAT Anchor Bolted Resolved NOT AN 7/94 Gas Comp to Block Wall - no thru OUTLIER-Cc Return bolts T. Dykstra to Resolved on Flow check scope of block original Indicator wall program. Tug SEWS tested by B.O. Sasman

& W. Djordjevic 7/94 OK.

122 A,I,C 18 cc Fl-645 K-1b Waste SAT Anchor Bolted Resolved NOT AN 7/94 Gas Comp to Block Wall - no thru OUTLIER-Cc Return bolts T. Dykstra to Resolved on Flow check scope of block original Indicator wall program. Tug SEWS tested by B.O. Sasman

& W. Djordjevic 7/94 OK.

POINT BEACH NUCLEAR PLANT, UNIT 2 1200114-R-002, REVISION 0 B-32 Outlier Program Equip System Equip Noun Name Status at Time of SRT Outlier Description Interim Resolution Documented Status I Final Required Date No. Class ID Walkdown in 1993 in the USI A-46 Seismic Resolution Close Out Completed Evaluation Report to NRC I,RG 18 AF LT- T-24b Cst 0 - Interaction, Deleted from SSEL Deleted from 1/18/95 123 4039 Level POTENTIAL FOR SSEL Transmitter BLOCK WALL TO FALLON COMPONENT. T.

Dykstra to evaluate function of LT.

1/18/95- LTs removed from A-46 list. Still IPEEE and RG 1.97.

I,RG 18 AF LT- T-24a Cst 0 - Interaction, Deleted from SSEL Deleted from 1/18/95 124 4040 Level POTENTIAL FOR SSEL Transmitter BLOCK WALL TO FALL ON COMPONENT. T.

Dykstra to evaluate function of LT.

1/18/95- LTs removed from A-46 list. Still IPEEE and RG 1.97.

I,RG 18 AF LT- T-24b Cst 0- Interaction, Deleted from SSEL Deleted from 1/18/95 125 4041 Level POTENTIAL FOR SSEL Transmitter BLOCK WALL TO FALLON COMPONENT. T.

Dykstra to evaluate function of LT.

1/18/95- LTs removed from A-46 list. Still IPEEE and RG 1.97.

I,RG 18 AF LT- T-24a Cst 0- Interaction, Deleted from SSEL Deleted from 1/18/95 126 4038 Level POTENTIAL FOR SSEL Transmitter BLOCK WALL TO FALLON COMPONENT. T.

Dykstra to evaluate function of LT. 1/18/95

- LTs removed from A-46 list. StiiiiPEEE and RG 1.97.

POINT BEACH NUCLEAR PLANT, UNIT 2 1200114-R-002, REVISION 0 8-33 Outlier Program Equip System Equip Noun Name Status at Time of SRT Outlier Description Interim Resolution Documented Status I Final Required Date No. Class ID Walkdown in 1993 in the USI A-46 Seismic Resolution Close Out Completed Evaluation Report to NRC A, I 18 RP 2PT- Hx-1a Sg 127 469 Pressure SAT- 0-lnteraction-Insufficient slack on Resolved NOT AN OUTLIER-11/11/94 Transmitter inlet tube. T. Dykstra Resolved on to submit MWR original 11/11/94 Update- SEWS 926/94 walkdown by SRT did tug test on all 6 PTs in PAB 46' elevation east of SFP.

Concluded that robust stanchions were rigid enough to prevent difference A, I 18 RP 2PT- Hx-1a Sg SAT- 0-lnteraction-128 482 Steam Insufficient slack on Resolved NOT AN OUTLIER-11/11/94 Pressure inlet tube. T. Dykstra Resolved on Transmitter to submit MWR original 11/11/94 Update- SEWS 926/94 walkdown by SRT did tug test on all 6 PTs in PAB 46' elevation east of SFP.

Concluded that robust stanchions were rigid enough to prevent difference 131 A,I,C 18 sc 2RK- Primary SAT Interim 4/25/95 - phone NOT AN 4/25/95 20 Plant Sample outlier until anchorage conversation with OUTLIER-Room Rack is checked. Interaction Wally Djordjevic - Resolved on

- adjacent sample sink determined that original has no visible since the only SEWS anchorage function of the rack was to support flow indicator and that the sample tubing is isolated upstream of rack and there is no requirement to operate the valves on the rack.

POINT BEACH NUCLEAR PLANT, UNIT 2 1200114-R-002, REVISION 0 B-34 Outlier Program Equip System Equip Noun Name Status at Time of SRT Outlier Description Interim Resolution Documented Status I Final Required Date No. Class ID Walkdown in 1993 in the USI A-46 Seismic Resolution Close Out Completed Evaluation Report to NRC A,l 20 RP 2C- Plant PO- Interaction- Fixed, MR 94-021 SQ-001839 8/24/94 132 115- Process I&C Supply cabinet bolted supply completed.

133 Cabinets interference. EWR cabinet to the back submitted. 1/18/95- of 2C-03.

MR 94-021 installed 6/9/94 resolves interaction concern.

6/28/96 - wo 9503622 replaced missing CEA bolt in 2C-130.

POINT BEACH NUCLEAR PLANT, UNIT 2 1200114-R-002, REVISION 0 B-35 ATTACHMENT A Seismic Walkdown Eauioment List Unit 2 and SFP fSWEL)

SWEL RISK N UNIT SYS EQUIP WALK EQUIP# EQUIP NAME 1 2 3 4 5 TRN IPEEE LOCATION DESC E CODE CLASS BY Equip.

w AREA Enhanced SWELI-2 y 2 AF 5 2P-029 AUX FEEDWATER TURBINE-DRIVEN PUMP X X X B 8/CB/AFP RM 2P-29 CUB 30 SWELI-2 0 AF 5 30 P-038B STAND BY STEAM GENERATOR PUMP X X X B 8/CB/AFP RM P-38B CUB SWELI-2 y y 2 AF 7 2AF-04002 2P-29 AFP MINI RECIRC CONTROL X X X B 8/CB/AFP RM 2P-29 CUB 30 SWELI-2 y 0 AF 7 30 AF-04014 P-38B SSGP MINI RECIRC CONTROL X X X B 8/CB/AFP RM P-38B CUB SWELI-2 0 AF 7 30 AF-04019 P-38B SSGP DISCHARGE CONTROL X X X B 8/CB/AFP RM P-38B CUB SWELI-2 y 0 125V 14 D-64 125V DC DISTRIBUTION PANEL X X X X X B 8/CB/AFP RM 2P-29 CUB 30 SWELI-2 2 AF 18 2RK-35 2P-29 AUX FEED WATER PUMP X X X B 8/CB/AFP RM 2P-29 CUB 30 INSTRUMENTATION RACK SWELI-2 2 MS 20 2C-197 2P-29 AFP SUCTION PRESSURE CONTROL X X X B 8/CB/AFP RM 2P-29 CUB 30 PANEL SWELI-2 2 AF 21a 2T-212 2P-29 AFP MINI RECIRC IA 2AF-4002 BACKUP X X X B 8/CB/AFP RM 30 ACCUMULATOR SWELI-2 2 AF 8a 2AF-04000 2P-29 AFP DISCHARGE 2HX-1B SG INLET X X X B 8/CB/AFP RM 2P-29 CUB 30 ISOLATION MOV SWELI-2 2 AF 8a 2AF-04001 2P-29 AFP DISCHARGE 2HX-1A SG INLET X X X B 8/CB/AFP RM 2P-29 CUB 30 ISOLATION MOV SWELI-2 2 AF 8a 30 2AF-04006 2P-29 AFP SUCTION FROM SERVICE WATER X X X B 8/CB/AFP RM 2P-29 CUB SWELI-2 0 AF 8a 30 AF-04016 P-38B SSGP SUCTION FROM SERVICE WATER X X X B 8/CB/AFP RM P-38B CUB SWELI-2 0 AF Sa AF-04020 P-38B SSGP DISCHARGE TO 2HX-1B STEAM X X X B 8/CB/AFP RM P-38B CUB 30 GENERATOR SWELI-2 2 MS 8b 30 2MS-02090 2P-29 AFP BEARING COOLING INLET X X X B 8/CB/AFPRM SWEL1-2 y 2 480V 2 9 2B-03 480V SAFEGUARDS LOAD CENTER X X X X X A X 26/CB/CSR SWELI-2 y 2 480V 2 2B-04 480V SAFEGUARDS LOAD CENTER X X X X X B X 26/CB/CSR 9

SWELI-2 y 2 480V 4 9 2X-13 2B-03 STATION SERVICE TRANSFORMER X X X X X A X 26/CB/CSR SWELI-2 y 2 480V 4 9 2X-14 2B-04 STATION SERVICE TRANSFORMER X X X X X B X 26/CB/CSR SWELI-2 y 0 125V 14 D-ll 125V DC DISTRIBUTION PANEL X X X X X A 26/CB/CSR EAST 9

SWELI-2 y y 0 125V 14 9 D-13 125V DC DISTRIBUTION PANEL X X X X X B 26/CB/CSR EAST SWELI-2 y 0 125V 14 D-26 125V DC DISTRIBUTION PANEL X X X X X A 26/CB/CSR 9

SWELI-2 y 0 125V 14 D-27 125V DC DISTRIBUTION PANEL X X X X X B 26/CB/CSR EAST 9

SWELI-2 0 y 14 Y-203 WHITE 120V INVERTER DISTRIBUTION X X X X X A 26/CB/CSR WEST WALL 9

PANEL

POINT BEACH NUCLEAR PLANT, UNIT 2 1200114-R-002, REVISION 0 B-36 SWEL RISK N UNIT SYS EQUIP WALK EQUIP# EQUIP NAME 1 2 3 4 5 TRN IPEEE LOCATION DESC E CODE CLASS BY Equip.

w AREA Enhanced SWELI-2 2 y 16 9 2DY-01 RED 125V DC/120V AC INVERTER X X X X X A 26/CB/CSR SWELI-2 2 y 16 9 2DY-02 BLUE 125V DC/120V AC INVERTER X X X X X B 26/CB/CSR SWELI-2 0 y 16 DY-OA RED 125V DC/120V AC ALTERNATE X X X X X A X 26/CB/CSR 9

INVERTER SWELI-2 y 0 sw 6 27 P-032B SERVICE WATER PUMP X X A X 8/CWPH/SW BLDG SWELI-2 y 0 sw 6 27 P-032C SERVICE WATER PUMP X X B X 8/CWPH/SW BLDG SWELI-2 y 0 sw 6 28 P-032D SERVICE WATER PUMP X X B X 8/CWPH/SW BLDG SWELI-2 y 0 sw 6 28 P-032E SERVICE WATER PUMP X X B X 8/CWPH/SW BLDG SWEL1-2 y 0 sw 6 28 P-032F SERVICE WATER PUMP X X A X 8/CWPH/SW BLDG SWELI-2 0 sw 8a 27 SW-02890 NORTH HEADER TO SOUTH SUPPLY X X B 8/CWPH/SW BLDG HEADER CROSSCONNECT SWELI-2 0 sw 8a 28 SW-02891 SOUTH TO NORTH SUPPLY HEADER X X A 8/CWPH/SW BLDG CROSSCONNECT SWELI-2 y 2 480V 1 35 2B-40 480V MOTOR CONTROL CENTER DGB X X X X X B 28/DGB/G-04 SWGR RM SWELI-2 y 0 DG 9 31 W-181B1 G-04 EDG HX-265B RADIATOR FAN X X X X X B 50/DGB/G-04 RADTR RM SWELI-2 y 0 DG 9 31 W-181B2 G-04 EDG HX-265B RADIATOR FAN X X X X X B 50/DGB/G-04 RADTR RM SWELI-2 y 0 DG 9 31 W-181B3 G-04 EDG HX-265B RADIATOR FAN X X X X X B 50/DGB/G-04 RADTR RM SWELI-2 y y 0 VNDG 9 W-184B G-04 EDG RM LARGE CAPACITY EXHAUST X X X X X B 50/DGB/G-04 FAN RM 32 FAN SWELI-2 y y 0 VNDG 9 W-184C G-04 EDG RM SMALL CAPACITY EXHAUST X X X X X B 50/DGB/G-04 FAN RM 32 FAN SWELI-2 y 0 125V 14 35 D-40 G-04 EDG DC DISTRffiUTION PANEL X X X X X B 28/DGB/G-04 SWGR RM SWELI-2 y y 0 DG 17 36 G-04 EMERGENCY DIESEL GENERATOR X X X X X B 28/DGB/G-04 RM SWELI-2 y 0 DG 20 35 C-082 G-04 EDG CONTROL PANEL X X X X X B 28/DGB/G-04 SWGR RM SWELI-2 y 0 DA 21a T-171A G-04 EDG STARTING AIR RECEIVER X X X X X B 28/DGB/G-04 RM 36 SWELI-2 y 0 DA 21a 36 T-171B G-04 EDG STARTING AIR RECEIVER X X X X X B 28/DGB/G-04 RM SWELI-2 y 1 480V 1 1B420C- P-32C SERVICE WATERPUMPNORMAL/ALT X X B 8/CB/G-02 RM 11 B957D TRANSFERSW SWELI-2 y 2 480V 1 2B427C- P-32E SERVICE WATER PUMP NORMAL/ALT X X B 8/CB/G-02 RM 11 B957D TRANSFERSW SWELI-2 y 0 DG 17 11 G-02 EMERGENCY DIESEL GENERATOR X X X X X A 8/CB/G-02 RM SWELI-2 0 DG 20 11 C-035 G-02 EDG ALARM AND ELECTRICAL PANEL X X X X X A 8/CB/G-02 RM W WALL SWELI-2 0 DG 20 11 C-035A G-02 EDG LOCAL TRANSFER PANEL X X X X X A 8/CB/G-02 RM W WALL

POINT BEACH NUCLEAR PLANT, UNIT 2 1200114-R-002, REVISION 0 8-37 SWEL RISK N UNIT SYS EQUIP WALK EQUIP# EQUIP NAME 1 2 3 4 5 TRN IPEEE LOCATION DESC E CODE CLASS BY Equip.

w AREA Enhanced SWEL1-2 0 DG 20 C-079 G-02 EDG DC POWER TRANSFER CONTROL X X X X X A 8/CB/G-02 RM 11 PANEL SWEL1-2 0 PO 21a 11 T-031B G-02 DIESEL GENERATOR DAY TANK X X X X X A 8/CB/G-02 RM SWELl-2 0 DA 21a T-061A G-02 EDG STARTING AIR RECEIVER (RlGHT X X X X X A 8/CB/G-02 RM 11 BANK)

SWELl-2 0 DA 21a T-061D G-02 EDG STARTING AIR RECEIVER (LEFT X X X X X A 8/CB/G-02 RM 11 BANK)

SWELl-2 0 DA 21a T-061F G-02 EDG STARTING AIR RECEIVER (LEFT X X X X X A 8/CB/G-02 RM 11 BANK)

SWELl-2 0 PO 8a F0-03931 T-31B G-02 EDG DAY TANK INLET SECOND X X X X X A 8/CB/G-02 RM 11 OFF ISOLATION SWELl-2 0 sw 8b 29 SW-02820- K-2B IA COMPRESSOR INLET SOLENOID X B G-02ROOM s

SWELl-2 0 sw 8b 29 SW-02826- K-2A IA COMPRESSOR INLET SOLENOID X A 8/CB/AIR COMP RM s

SWELl-2 2 IA 7 23 2IA-03047 U2C IA HEADER INLET CONTROL X A 26/PAB/PIPEW AY #3 SWELl-2 2 IA 7 23 2IA-03048 U2C IA HEADER INLET CONTROL X B 26/PAB/PIPEWA Y #3 SWELl-2 y 0 sw 8a 22 SW-02869 NORTH HEADER TO WEST HEADER X A 26/PAB/CENTRAL SWELl-2 y 0 sw 8a 46 SW-02870 SOUTH HEADER TO WEST HEADER X B 26/PAB/CENTRAL CROSSCONNECT SWELl-2 y 2 cc 5 20 2P-011A COMPONENT COOLING WATER PUMP X X X A X 8/PAB/CC PUMP AREA SWEL1-2 y 2 cc 5 20 2P-011B COMPONENT COOLING WATER PUMP X X X B X 8/P AB/CC PUMP AREA SWELl-2 2 SI 5 2P-014A CONTAINMENT SPRAY PUMP X A X 8/PAB/SPRAY PUMP 19 AREA SWELl-2 2 SI 5 2P-014B CONIAINMENT SPRAY PUMP X B X 8/PAB/SPRAY PUMP 19 AREA SWELl-2 y 2 SI 5 19 2P-015A SAFETY INJECTION PUMP X X X X X A 8/PAB/SI PUMP AREA SWELl-2 y 2 SI 5 19 2P-015B SAFETY INJECTION PUMP X X X X X B 8/PAB/SI PUMP AREA SWELl-2 2 SI 8a 2SI- T-13 RWST OUTLET TO P-15NB SI PUMP X X X X X B 8/PAB/SPRAY PUMP 19 00825B AREA SWELl-2 y 2 SI 8a 2SI- HX-11B RHR HX OUTLET TO P-15B SI PUMP X X X X X B 8/PAB/SI PUMP AREA 19 00857B SUCTION SWELl-2 y 2 SI 8a 2SI- P-15B SI PUMP SUCTION X X X X X B 8/PAB/SI PUMP AREA 19 00896B SWELl-2 y 2 480V 1 2B-32 480V MOTOR CONTROL CENTER PAB X X X X X A 8/PABIU2 CHG PUMP 16 SAFEGUARDS AREA SWELl-2 y 2 CV 5 2P-002C CHARGING PUMP (Pump Only as Pressure X X X B 8/PABIU2 CHG PUMP RM 40 Boundary)

POINT BEACH NUCLEAR PLANT, UNIT 2 1200114-R-002, REVISION 0 B-38 SWEL RISK N UNIT SYS EQUIP WALK EQUIP# EQUIP NAME 1 2 3 4 5 TRN IPEEE LOCATION DESC E CODE CLASS BY Equip.

w AREA Enhanced SWELl-2 2 cv 7 12 2CV-00142 CHARGING LINE FLOW CONTROL X X X A S/P AB/PIPEWAY #4 SWELl-2 y 2 SI Sa 2SI- COLD LEG INJECTION LINE ISOLATION X X X X X A SIPAB/PIPEWA Y #4 12 OOS66A SWELl-2 y 2 cv Sa 16 2CV- 2P-2A-C CHARGING PUMP REFUELING X X X A S/PABIU2 CHG PUMP 00112B WATER SUCTION AREA SWELl-2 y 2 SI Sa 2SI- CORE DELUGE INJECTION LINE ISOLATION X X X X X B SIPAB/PIPEWAY #4 12 OOS66B SWELl-2 2 SI 21a T-034A SAFETY INJECTION ACCUMULATOR X X X A 21/U2CINW QTR, 49,50 46/U2CNWQTR SWELl-2 2 SI Sa SI-OOS41A T-34A SI ACCUMULATOR OUTLET X X X A 21/U2CINW QTR 49 OPERATOR SWELl-2 2 SI Sa SI-OOS7SA P-15B SI PUMP R-1 REACTOR VESSEL X X X X A 21/U2C/C-1 AIR LOCK 51 INJECTION AREA EAST SWELl-2 y 2 RH Sa 52 RH-00720 RHR RETURN TO RCS X A 46/U2C/SE QTR SWELl-2 2 MS 7 2MS-02015 HX-lB SG HDR ATMOSPHERIC STEAM DUMP X X X B S5/U2F 25 CONTROL SWELl-2 2 MS 7 2MS-02016 HX-lA SG HDR ATMOSPHERIC STEAM DUMP X X X A S5/U2F 25 CONTROL SWELl-2 2 4SOV 1 2B-39 4SOV MOTOR CONTROL CENTER TRAIN A X X X X X A S/CBNSGRM 21 BATTERY CHARGER SUPPLY SWELl-2 2 4SOV 1 2B-49 4SOV MOTOR CONTROL CENTER TRAIN B X X X X X B S/CBNSGRM 21 BATTERY CHARGER SUPPLY SWELl-2 y 2 4.16K 3 2A-05 4.16 KV BUS SWITCHGEAR (SAFEGUARDS) X X X X X A S/CBNSGRM 21 v

SWELl-2 y 0 125V 14 21 D-02 125V DC DISTRIBUTION PANEL X X X X X B S/CBNSGRM SWELl-2 y 0 125V 15 45 D-06 125V DC STATION BATTERY X X X X X B X S/CB/D-06 BATT RM SWELl-2 y y 0 125V 16 21 D-07 D-05 DC STATION BATTERY CHARGER X X X X X A S/CBNSGRM SWELl-2 y y 0 125V 16 21 D-OS D-06 DC STATION BATTERY CHARGER X X X X X B S/CBNSGRM SWELl-2 2 cc 19 s TE-00621 HX-12C/D CC HX OUTLET HEADER X X X 0 46/PAB/CC HX AREA TEMPERATURE RTD SWELl-2 y y 0 cc 21b s HX-012C COMPONENT COOLING WATER HEAT X X X 0 46/PAB/CC HX AREA EXCHANGER SWELl-2 y y 0 cc 21b s HX-012B COMPONENT COOLING WATER HEAT X X X 0 46/PAB/CC HX AREA EXCHANGER SWELl-2 0 VNBI 10 W-OS6 PAB BATTERY AND INVERTER ROOM VENT X X X X X B 35/PAB/D-106 ROOF 4

FAN SWEL2 0 SF 5 24 P-012B SPENT FUEL COOLING PUMP B 46/PAB/SFP HX AREA SWEL2 0 SF 5 24 P-012A SPENT FUEL COOLING PUMP A 46/PAB/SFP HX AREA

POINT BEACH NUCLEAR PLANT, UNIT 2 1200114-R-002, REVISION 0 B-39 SWEL RISK N UNIT SYS EQUIP WALK EQUIP# EQUIP NAME 1 2 3 4 5 TRN IPEEE LOCATION DESC E CODE CLASS BY Equip.

w AREA Enhanced SWEL2 0 SF 21b 24 HX-013B SPENT FUEL POOL HEAT EXCHANGER B 46/PAB/SFP HX AREA SWEL2 0 SF 21b 24 HX-013A SPENT FUEL POOL HEAT EXCHANGER A 46/PAB/SFP HX AREA SWEL2 0 sw 8a 24 SW- HX-13B SFP HX OUTLET B 46/P AB/SFP HX AREA 02930B SWEL2 0 sw 8a 24 SW- HX-13A SFP HX OUTLET A 46/PAB/SFP HX AREA 02930A SWEL2 0 sw 8a 24 SW- HX-13B SFP HX INLET B 46/PAB/SFP HX AREA 02927B SWEL2 0 sw 8a 24 SW- HX-13A SFP HX INLET A 46/PAB/SFP HX AREA 02927A SWEL2 0 sw 0 14 SF-00785B P-9 HUT RECIRC PUMP SUCTION FROM B 8/P AB/P-9 HUT AREA TRANSFER CANAL WEST SWELl-2 y 2 RH 5 44 2P-010B RESIDUAL HEAT REMOVAL PUMP X X X X X A X -19/PAB

POINT BEACH NUCLEAR PLANT, UNIT 2 1200114-R-002, REVISION 0 8-40 ATTACHMENT B Classes of Equipment Unit 2 SWEL1 SWEL Classes of Equipment 2 Unit 2 0 Other 0 1 1 MCCs and wall-mounted contactors 6 0 2 Low voltaqe switchqear and break panels 2 0 3 Medium voltaqe, metal-clad switchgear 1 0 4 Transformers 2 0 5 Horizontal pumps 10 2 6 Vertical pumps 5 0 7 Fluid-operated valves 8 0 8a MOVs 19 4 8b SOVs 3 0 9 Fans 5 0 10 Air handlers 1 0 11 Chiller 0 0 12 Air Compressors 0 0 13 Motor Generators 0 0 Distribution panels and Auto Transfer 14 8 0 Switches 15 Batteries and Racks 1 0 16 Battery charqers and inverters 5 0 17 Enqine Generators 2 0 18 Instrument Racks 1 0 19 Temperature sensors 1 0 20 Instrumentation and Control panels 5 0 21a Tanks 8 0 21b Heat exchangers 2 2 TOTAL 95 9 Note: There are no Chillers, Air Compressors and Motor Generators at Point Beach Unit 1 which are Seismic Category I. Therefore, none of these classes of equipment were included in the SWEL.

POINT BEACH NUCLEAR PLANT, UNIT 2 1200114-R-002, REVISION 0 B-41 Attachment C Selected Equipment List Unit 2 and SFP SYS EQUIP EQUIP SEISMIC SWEL RISK NEW UNIT CODE CLASS NUMBER EQUIPMENT NAME 1 2 3 4 5 LOCATION DESC CAT SWEL1-2 y 0 125V 14 D-02 125V DC DISTRIBUTION PANEL X X X X X 8/CBNSG RM I SWEL1-2 y 0 125V 15 D-06 125V DC STATION BATTERY X X X X X 8/CB/D-06 BATT RM I SWEL1-2 y y 0 125V 16 D-07 D-05 DC STATION BATTERY CHARGER X X X X X 8/CBNSG RM I SWEL1-2 y y 0 125V 16 D-08 D-06 DC STATION BATTERY CHARGER X X X X X 8/CBNSG RM I SWEL1-2 y 0 125V 14 D-11 125V DC DISTRIBUTION PANEL X X X X X 26/CB/CSR EAST I SWEL1-2 y y 0 125V 14 D-13 125V DC DISTRIBUTION PANEL X X X X X 26/CB/CSR EAST I SWEL1-2 y 0 125V 14 D-26 125V DC DISTRIBUTION PANEL X X X X X 26/CB/CSR I SWEL1-2 y 0 125V 14 D-27 125V DC DISTRIBUTION PANEL X X X X X 26/CB/CSR EAST I 28/DGB/G-04 SWGR SWEL1-2 y 0 125V 14 D-40 G-04 EDG DC DISTRIBUTION PANEL X X X X X RM I 8/CB/AFP RM 2P-29 SWEL1-2 y 0 125V 14 D-64 125V DC DISTRIBUTION PANEL X X X X X CUB I SWEL1-2 y 2 4.16KV 3 2A-05 4.16 KV BUS SWITCHGEAR (SAFEGUARDS) X X X X X 8/CBNSG RM I SWEL1-2 y 2 480V 2 2B-03 480V SAFEGUARDS LOAD CENTER X X X X X 26/CB/CSR I SWEL1-2 y 2 480V 2 2B-04 480V SAFEGUARDS LOAD CENTER X X X X X 26/CB/CSR I 480V MOTOR CONTROL CENTER PAB 8/PAB/U2 CHG PUMP SWEL1-2 y 2 480V 1 2B-32 SAFEGUARDS X X X X X AREA I 480V MOTOR CONTROL CENTER TRAIN A SWEL1-2 2 480V 1 2B-39 BATTERY CHARGER SUPPLY X X X X X 8/CBNSG RM I 28/DGB/G-04 SWGR SWEL1-2 y 2 480V 1 2B-40 480V MOTOR CONTROL CENTER DGB X X X X X RM I 480V MOTOR CONTROL CENTER TRAIN B SWEL1-2 2 480V 1 2B-49 BATTERY CHARGER SUPPLY X X X X X 8/CBNSG RM I SWEL1-2 y 2 480V 4 2X-13 2B-03 STATION SERVICE TRANSFORMER X X X X X 26/CB/CSR I SWEL1-2 y 2 480V 4 2X-14 2B-04 STATION SERVICE TRANSFORMER X X X X X 26/CB/CSR I B420C- P-32C SERVICE WATER PUMP SWEL1-2 y 1 480V 1 B957D NORMALIALT TRANSFER SW X X 8/CB/G-02 RM I B427C- P-32E SERVICE WATER PUMP SWEL1-2 y 2 480V 1 B957D NORMAL/ALT TRANSFER SW X X 8/CB/G-02 RM I

POINT BEACH NUCLEAR PLANT, UNIT 2 1200114-R-002, REVISION 0 B-42 2AF- 2P-29 AFP DISCHARGE 2HX-1 B SG INLET 8/CB/AFP RM 2P-29 SWEL1-2 2 AF 8a 04000 ISOLATION MOV X X X CUB I 2AF- 2P-29 AFP DISCHARGE 2HX-1A SG INLET 8/CB/AFP RM 2P-29 SWEL1-2 2 AF 8a 04001 ISOLATION MOV X X X CUB I 2AF- 8/CB/AFP RM 2P-29 SWEL1-2 y y 2 AF 7 04002 2P-29 AFP MINI RECIRC CONTROL X X X CUB I 2AF- 2P-29 AFP SUCTION FROM SERVICE 8/CB/AFP RM 2P-29 SWEL1-2 2 AF 8a 04006 WATER X X X CUB I 8/CB/AFP RM 2P-29 SWEL1-2 y 2 AF 5 2P-029 AUX FEEDWATER TURBINE-DRIVEN PUMP X X X CUB I 2P-29 AUX FEEDWATER PUMP 8/CB/AFP RM 2P-29 SWEL1-2 2 AF 18 2RK-35 INSTRUMENTATION RACK X X X CUB I 2P-29 AFP MINI RECIRC lA 2AF-4002 SWEL1-2 2 AF 21a 2T-212 BACKUP ACCUMULATOR X X X 8/CB/AFP RM I 8/CB/AFP RM P-38B SWEL1-2 y 0 AF 7 AF-04014 P-38B SSGP MINI RECIRC CONTROL X X X CUB I P-38B SSGP SUCTION FROM SERVICE 8/CB/AFP RM P-38B SWEL1-2 0 AF 8a AF-04016 WATER X X X CUB I 8/CB/AFP RM P-38B SWEL1-2 0 AF 7 AF-04019 P-38B SSGP DISCHARGE CONTROL X X X CUB I P-38B SSGP DISCHARGE TO 2HX-1 B 8/CB/AFP RM P-38B SWEL1-2 0 AF 8a AF-04020 STEAM GENERATOR X X X CUB I 8/CB/AFP RM P-38B SWEL1-2 0 AF 5 P-038B STANDBY STEAM GENERATOR PUMP X X X CUB I 8/PAB/CC PUMP SWEL1-2 y 2 cc 5 2P-011A COMPONENT COOLING WATER PUMP X X X AREA I 8/PAB/CC PUMP SWEL1-2 y 2 cc 5 2P-011B COMPONENT COOLING WATER PUMP X X X AREA I COMPONENT COOLING WATER HEAT SWEL1-2 y y 0 cc 21b HX-012B EXCHANGER X X X 46/PAB/CC HX AREA I COMPONENT COOLING WATER HEAT SWEL1-2 y 0 cc 21b HX-012C EXCHANGER X X X 46/PAB/CC HX AREA I HX-12C/D CC HX OUTLET HEADER SWEL1-2 2 cc 19 TE-00621 TEMPERATURE RTD X X X 46/PAB/CC HX AREA I 2CV- 2P-2A-C CHARGING PUMP REFUELING 8/PAB/U2 CHG PUMP SWEL1-2 y 2 cv 8a 00112B WATER SUCTION X X X AREA I 2CV-SWEL1-2 2 cv 7 00142 CHARGING LINE FLOW CONTROL X X X 8/PAB/PIPEWAY#4 I CHARGING PUMP (Pump Only as Pressure 8/PAB/U2 CHG PUMP SWEL1-2 y 2 cv 5 2P-002C Boundary) X X X RM I

POINT BEACH NUCLEAR PLANT, UNIT 2 1200114-R-002, REVISION 0 B-43 G-02 EDG STARTING AIR RECEIVER SWEL1-2 0 DA 21a T-061A (RIGHT BANK) X X X X X 8/CB/G-02 RM I G-02 EDG STARTING AIR RECEIVER (LEFT SWEL1-2 0 DA 21a T-0610 BANK) X X X X X 8/CB/G-02 RM I G-02 EDG STARTING AIR RECEIVER (LEFT SWEL1-2 0 DA 21a T-061 F BANK) X X X X X 8/CB/G-02 RM I SWEL1-2 y 0 DA 21a T-171A G-04 EDG STARTING AIR RECEIVER X X X X X 28/DGB/G-04 RM I SWEL 1-2 y 0 DA 21a T-171B G-04 EDG STARTING AIR RECEIVER X X X X X 28/DGB/G-04 RM I 8/CB/G-02 RM W SWEL1-2 0 DG 20 C-035 G-02 EDG ALARM AND ELECTRICAL PANEL X X X X X WALL I 8/CB/G-02 RM W SWEL1-2 0 DG 20 C-035A G-02 EDG LOCAL TRANSFER PANEL X X X X X WALL I G-02 EDG DC POWER TRANSFER SWEL1-2 0 DG 20 C-079 CONTROL PANEL X X X X X 8/CB/G-02 RM I 28/DGB/G-04 SWGR SWEL1-2 y 0 DG 20 C-082 G-04 EDG CONTROL PANEL X X X X X RM I SWEL1-2 y 0 DG 17 G-02 EMERGENCY DIESEL GENERATOR X X X X X 8/CB/G-02 RM I SWEL1-2 y y 0 DG 17 G-04 EMERGENCY DIESEL GENERATOR X X X X X 28/DGB/G-04 RM I 50/DGB/G-04 RADTR SWEL1-2 y 0 DG 9 W-181B1 G-04 EDG HX-265B RADIATOR FAN X X X X X RM I 50/DGB/G-04 RADTR SWEL1-2 y 0 DG 9 W-181B2 G-04 EDG HX-265B RADIATOR FAN X X X X X RM I 50/DGB/G-04 RADTR SWEL1-2 y 0 DG 9 W-181B3 G-04 EDG HX-265B RADIATOR FAN X X X X X RM I T-31 B G-02 EDG DAY TANK INLET SECOND SWEL1-2 0 FO Sa F0-03931 OFF ISOLATION X X X X X 8/CB/G-02 RM I SWEL1-2 0 FO 21a T-031B G-02 DIESEL GENERATOR DAY TANK X X X X X 8/CB/G-02 RM I SWEL1-2 2 lA 7 21A-03047 U2C lA HEADER INLET CONTROL X 26/PAB/PIPEWAY #3 I SWEL1-2 2 lA 7 21A-03048 U2C lA HEADER INLET CONTROL X 26/PAB/PIPEWAY #3 I P-29 AFP SUCTION PRESSURE CONTROL 8/CB/AFP RM 2P-29 SWEL1-2 2 MS 20 2C-197 PANEL X X X CUB I 2MS- HX-1 B SG HDR ATMOSPHERIC STEAM SWEL1-2 2 MS 7 02015 DUMP CONTROL X X X 85/U2F I 2MS- HX-1A SG HDR ATMOSPHERIC STEAM SWEL1-2 2 MS 7 02016 DUMP CONTROL X X X 85/U2F I

POINT BEACH NUCLEAR PLANT, UNIT 2 1200114-R-002, REVISION 0 B-44 2MS-SWEL1-2 2 MS 8b 02090 P-29 AFP BEARING COOLING INLET X X X 8/CB/AFP RM I SWEL1-2 y 2 RH 8a RH-00720 RHR RETURN TO RCS X 46/U2C/SE QTR I SWEL1-2 2 RH 5 2P-010B RESIDUAL HEAT REMOVAL PUMP X X X X X -19/PAB I T-34A Sl ACCUMULATOR OUTLET 21/U2C/T-34A SWEL1-2 2 Sl 8a SI-00841A OPERATOR X X X ACCUM EAST I P-15B Sl PUMP R-1 REACTOR VESSEL 21/U2C/C-1 AIR LOCK SWEL1-2 2 Sl 8a SI-00878A INJECTION X X X X AREA EAST I SWEL1-2 2 Sl 21a T-034A SAFETY INJECTION ACCUMULATOR X X X 21/U2C/NW QTR I 8/PAB/SPRAY PUMP SWEL1-2 2 Sl 5 2P-014A CONTAINMENT SPRAY PUMP X AREA I 8/PAB/SPRAY PUMP SWEL1-2 2 Sl 5 2P-014B CONTAINMENT SPRAY PUMP X AREA I SWEL1-2 y 2 Sl 5 2P-015A SAFETY INJECTION PUMP X X X X X 8/PAB/SI PUMP AREA I SWEL1-2 y 2 Sl 5 2P-015B SAFETY INJECTION PUMP X X X X X 8/PAB/SI PUMP AREA I 2SI- 8/PAB/SPRAY PUMP SWEL1-2 2 Sl 8a 00825B T-13 RWST OUTLET TO P-15A/B Sl PUMP X X X X X AREA I 2SI- HX-11 B RHR HX OUTLET TO P-15B Sl SWEL1-2 y 2 Sl 8a 00857B PUMP SUCTION X X X X X 8/PAB/SI PUMP AREA I 2SI-SWEL1-2 y 2 Sl 8a 00866A COLD LEG INJECTION LINE ISOLATION X X X X X 8/PAB/PIPEWAY #4 I 2SI- CORE DELUGE INJECTION LINE SWEL1-2 y 2 Sl 8a 00866B ISOLATION X X X X X 8/PAB/PIPEWAY #4 I 2SI-SWEL1-2 y 2 Sl 8a 00896B P-15B Sl PUMP SUCTION X X X X X 8/PAB/SI PUMP AREA I SWEL1-2 y 0 sw 6 P-032B SERVICE WATER PUMP X X 8/CWPH/SW BLDG I SWEL1-2 y 0 sw 6 P-032C SERVICE WATER PUMP X X 8/CWPH/SW BLDG I SWEL1-2 y 0 sw 6 P-032D SERVICE WATER PUMP X X 8/CWPH/SW BLDG I SWEL1-2 y 0 sw 6 P-032E SERVICE WATER PUMP X X 8/CWPH/SW BLDG I SWEL1-2 y 0 sw 6 P-032F SERVICE WATER PUMP X X 8/CWPH/SW BLDG I SW-SWEL1-2 0 sw 8b 02820-S K-2B lA COMPRESSOR INLET SOLENOID X G-02 ROOM I SW-SWEL1-2 0 sw 8b 02826-S K-2A lA COMPRESSOR INLET SOLENOID X 8/CB/AIR COMP RM I

POINT BEACH NUCLEAR PLANT, UNIT 2 12Q0114-R-002, REVISION 0 B-45 SWEL1-2 y 0 sw 8a SW-02869 NORTH HEADER TO WEST HEADER X 26/PAB/CENTRAL I SOUTH HEADER TO WEST HEADER SWEL1-2 y 0 sw 8a SW-02870 CROSSCONNECT X 26/PAB/CENTRAL I NORTH HEADER TO SOUTH SUPPLY SWEL1-2 0 sw 8a SW-02890 HEADER CROSSCONNECT X X 8/CWPH/SW BLDG I SOUTH TO NORTH SUPPLY HEADER SWEL1-2 0 sw 8a SW-02891 CROSSCONNECT X X 8/CWPH/SW BLDG I PAB BATTERY AND INVERTER ROOM SWEL1-2 0 VNBI 10 W-086 VENT FAN X X X X X 35/PAB/D-106 ROOF I G-04 EDG RM LARGE CAPACITY EXHAUST SWEL1-2 y y 0 VNDG 9 W-184B FAN X X X X X 50/DGB/G-04 FAN RM I G-04 EDG RM SMALL CAPACITY EXHAUST SWEL1-2 y y 0 VNDG 9 W-184C FAN X X X X X 50/DGB/G-04 FAN RM I SWEL1-2 2 y 16 2DY-01 RED 125V DC/120V AC INVERTER X X X X X 26/CB/CSR I SWEL1-2 2 y 16 2DY-02 BLUE 125V DC/120V AC INVERTER X X X X X 26/CB/CSR I RED 125V DC/120V AC ALTERNATE SWEL1-2 0 y 16 DY-OA INVERTER X X X X X 26/CB/CSR I WHITE 120V INVERTER DISTRIBUTION 26/CB/CSR WEST SWEL1-2 0 y 14 Y-203 PANEL X X X X X WALL I 2SAF- 2P-29 AFP DISCH 2HX-1B SG INLET !SOL PB 2 125V 2 04000 MOVSTARTER X X X 8/CBNSG EQUIP RM I 2SAF- 2P-29 AFP DISCH 2HX-1A SG INLET !SOL PB 2 125V 2 04001 MOVSTARTER X X X 8/CBNSG EQUIP RM I 2SMS- HX-1 B SG HDR P-29 AFP STEAM SUPPLY PB 2 125V 2 02019 MOVSTARTER X X X 8/CBNSG EQUIP RM I 2SMS- HX-1A SG HDR P-29 AFP STEAM SUPPLY PB 2 125V 2 02020 MOVSTARTER X X X 8/CBNSG EQUIP RM I 2SMS- 8/CB/AFP RM 2P-29 PB 2 125V 2 02082 P-29 AFP OVERSPEED TRIP STARTER X X X CUB I 26/PAB/INVERT RM PB 0 125V 14 D-04 125V DC DISTRIBUTION PANEL X X X X X EAST I 26/PAB/D-1 06 BATT PB y 0 125V 15 D-106 125V DC STATION BATTERY X X X X X RM I 26/PAB/INVERT RM PB 0 125V 16 D-108 D-106 DC STATION BATTERY CHARGER X X X X X EAST I 26/PAB/INVERT RM PB 0 125V 16 D-109 SWING STATION BATTERY CHARGER X X X X X WEST I

POINT BEACH NUCLEAR PLANT, UNIT 2 1200114-R-002, REVISION 0 B-46 B336A- P-1 OA RHR PUMP NORMALIALT TRANSFER PB 2 480V 1 B958B SWITCH X X X X X 8/PAB/COL P-11 I D-09 SWING STN BATTERY CHARGER PB 2 480V 1 B42-391 TRAIN A CONTACTOR X X X X X 8/CBNSG RM 2B-39 I D-107 STATION BATTERY CHARGER TRAIN PB 2 480V 1 B42-394 ACONTACTOR X X X X X 8/CBNSG RM 2B-39 I D-08 STATION BATTERY CHARGER TRAIN PB 2 480V 1 B42-491 B CONTACTOR X X X X X 8/CBNSG RM 2B-49 I B429A- P-1 OB RHR PUMP NORMALIALT TRANSFER PB 2 480V 1 B958B SWITCH X X X X X 8/PAB/COL P-12 I 8/CB/AFP RM P-38B PB 0 AF 18 RK-25B P-38B SSGP INSTRUMENTATION RACK X X X CUB I 2CC- 2HX-11A RHR HX SHELL SIDE OUTLET PB 2 cc 8a 00736A RELIEF X X X 8/PAB/PIPEWAY #3 I 2CC- 2HX-11 B RHR HX SHELL SIDE OUTLET PB 2 cc 8a 00736B RELIEF X X X 8/PAB/PIPEWAY #3 I 2CC-PB 2 cc 8a 00738A 2HX-11A RHR HX SHELL SIDE INLET X X X 8/PAB/PIPEWAY#3 I 2CC-PB 2 cc 8a 00738B 2HX-11 B RHR HX SHELL SIDE INLET X X X 8/PAB/PIPEWAY #3 I 2CC-PB 2 cc 8a 00759A 2P-1A RCP CC OUTLET MOV X X X 8/PAB/PIPEWAY#3 I COMPONENT COOLING WATER HEAT PB 2 cc 21b 2HX-012D EXCHANGER X X X 46/PAB/CC HX AREA I COMPONENT COOLING WATER HEAT PB 0 cc 21b HX-012B EXCHANGER X X X 46/PAB/CC HX AREA I G-01 EDG STARTING AIR RECEIVER PB 0 DA 21a T-060A (RIGHT BANK) X X X X X 8/CB/G-01 RM I G-01 EDG STARTING AIR RECEIVER (LEFT PB 0 DA 21a T-060D BANK) X X X X X 8/CB/G-01 RM I G-02 EDG STARTING AIR RECEIVER PB 0 DA 21a T-061 B (RIGHT BANK) X X X X X 8/CB/G-02 RM I G-02 EDG STARTING AIR RECEIVER PB 0 DA 21a T-061C (RIGHT BANK) X X X X X 8/CB/G-02 RM I G-02 EDG STARTING AIR RECEIVER (LEFT PB 0 DA 21a T-061E BANK) X X X X X 8/CB/G-02 RM I PB 0 DA 21a T-170C G-03 EDG STARTING AIR RECEIVER X X X X X 28/DGB/G-03 RM I G-02 EDG DC POWER TRANSFER 8/CB/G-02 RM N PB 0 DG 20 C-079 CONTROL PANEL X X X X X WALL I

POINT BEACH NUCLEAR PLANT, UNIT 2 1200114-R-002, REVISION 0 B-47 50/DGB/G-03 RADTR PB 0 DG 9 W-181A3 G-03 EDG HX-265A RADIATOR FAN X X X X X RM I SECONDARY SYSTEM POWER SUPPLIES PB 2 MMS 20 2C-105 PANEL X X X 44/CB/CR I 2MS- HX-1 B SG HEADER P-29 AFP STEAM PB 2 MS 8a 02019 SUPPLY MOV X X X 46/PAB/BAST AREA I 2MS- HX-1A SG HEADER P-29 AFP STEAM PB 2 MS 8a 02020 SUPPLY MOV X X X 46/PAB/BAST AREA I RESIDUAL HEAT REMOVAL HEAT PB 2 RH 21b 2HX-011A EXCHANGER X X X X X -5/PAB/RHR HX CUB I RESIDUAL HEAT REMOVAL HEAT PB 2 RH 21b 2HX-011 B EXCHANGER X X X X X -5/PAB/RHR HX CUB I PB 2 RH 5 2P-010A RESIDUAL HEAT REMOVAL PUMP X X X X X -19/PAB I 2RH- -5/PAB/EAST WALL .

PB 2 RH 7 00624 HX-11A RHR HX OUTLET CONTROL X X X X X OVHD I 2RH- -5/PAB/EAST WALL PB 2 RH 7 00625 HX-11 B RHR HX OUTLET CONTROL X X X X X OVHD I 2SI- 8/PAB/SPRAY PUMP PB 2 Sl 8a 00825A T-13 RWST OUTLET TO P-15AIB Sl PUMP X X X X X AREA I 2SI- P-10A RHR PUMP SUMP B SUCTION PB 2 Sl 8a 00850A-M MOTOR/PUMP X X X X X 8/PAB/PIPEWAY #3 I 2SI- P-10B RHR PUMP SUMP B SUCTION PB 2 Sl 8a 00850B-M MOTOR/PUMP X X X X X 8/PAB/PIPEWAY #3 I 2SI- P-10A RHR PUMP SUCTION FROM -5/PAB/RHR PB 2 Sl 8a 00851A CONTAINMENT SUMP B X X X X X PIPEWAY I 2SI- P-10B RHR PUMP SUCTION FROM -5/PAB/RHR PB 2 Sl 8a 00851B CONTAINMENT SUMP B X X X X X PIPEWAY I 2SI- HX-11A RHR HX OUTLET TO P-15A Sl PB 2 Sl 8a 00857A PUMP SUCTION X X X X X 8/PAB/SI PUMP AREA I 2SI-PB 2 Sl 8a 00896A P-15A Sl PUMP SUCTION X X X X X 8/PAB/Sl PUMP AREA I 2SW- HX-12D CC HX OUTLET TEMPERATURE PB 2 sw 7 00012D CONTROL X 46/PAB/CC HX AREA I SW-PB 0 sw 8b 02832B-S K-3B SA COMPRESSOR INLET SOLENOID X G-02 ROOM I PAB BATTERY AND INVERTER ROOM PB 0 VNBI 10 W-086 VENT FAN X X X X X 35/PAB/D-106 ROOF I PB 2 y 14 2Y-02 BLUE 120VVITAL INSTRUMENT PANEL X X X X X 44/CB/CR WEST I

POINT BEACH NUCLEAR PLANT, UNIT 2 1200114-R-002, REVISION 0 B-48 2Y-01 RED 120V AC VITAL INST PNL PWR PB 2 y 14 43/Y-01 SUP TRANSFER SW X X X X X 44/CB/CR WEST I 2Y-02 BLUE 120V AC VITAL INST PNL PWR PB 2 y 14 43/Y-02 SUP TRANSFER SW X X X X X 44/CB/CR WEST I 26/CB/SWBD CHGR PB 0 125V 14 D-301 SWING BATIERY DISTRIBUTION PANEL X X X X X RM I 26/CB/D-305 BATI PB 0 125V 15 D-305 SWING STATION BATTERY X X X X X RM I 480V MOTOR CONTROL CENTER PAB PB y 1 480V 1 1B-42 SAFEGUARDS X X X X X 26/PAB/C-59 AREA I 480V MOTOR CONTROL CENTER PAB PB y 2 480V 1 2B-42 SAFEGUARDS X X X X X 26/PAB/C-59 AREA I CHARGING PUMP (Pump Only as Pressure 8/PAB/U2 CHG PUMP PB y 2 cv 5 2P-002A Boundary) X X X AREA I CHARGING PUMP (Pump Only as Pressure 8/PAB/U2 CHG PUMP PB y 2 cv 5 2P-002B Boundary) X X X RM I REFUELING WATER STORAGE TANK W/6 PB 2 Sl 21a 2T-013 IMMERSION HTRS X X X X X U2F I PB 0 VNDG 9 W-012A G-01 ROOM EXHAUST FAN X X X X X 26/CB I PB 0 VNDG 9 W-012B G-01 ROOM EXHAUST FAN X X X X X 26/CB I PB 0 VNDG 9 W-012C G-02 ROOM EXHAUST FAN X X X X X 26/CB I PB 0 VNDG 9 W-012D G-02 ROOM EXHAUST FAN X X X X X 26/CB I SWEL2 0 SF 21b HX-013A SPENTFUELPOOLHEATEXCHANGER 46/PAB/SFP HX AREA I SWEL2 0 SF 21b HX-013B SPENTFUELPOOLHEATEXCHANGER 46/PAB/SFP HX AREA I SWEL2 0 SF 5 P-012A SPENT FUEL COOLING PUMP 46/PAB/SFP HX AREA I SWEL2 0 SF 5 P-012B SPENT FUEL COOLING PUMP 46/PAB/SFP HX AREA I SF- P-9 HUT RECIRC PUMP SUCTION FROM 8/PAB/P-9 HUT AREA SWEL2 0 SF 0 00785B TRANSFER CANAL WEST I SW-SWEL2 0 sw 8a 02927A HX-13A SFP HX INLET 46/PAB/SFP HX AREA I SW-SWEL2 0 sw 8a 02927B HX-13B SFP HX INLET 46/PAB/SFP HX AREA I SW-SWEL2 0 sw 8a 02930A HX-13A SFP HX OUTLET 46/PAB/SFP HX AREA I SW-SWEL2 0 sw 8a 02930B HX-13B SFP HX OUTLET 46/PAB/SFP HX AREA I PB 0 SF 21a SFP SPENT FUEL POOL 46/PAB/SFP HX AREA I YELLOW 120V INVERTER DISTRIBUTION 26/CB/CSR WEST PB 0 y 14 Y-204 PANEL X X X X X WALL I

Point Beach Nuclear Plant, Unit 2 Sheet 1 of 2 1200114-R-002, Revision 0 Status: [YJ N U Seismic Walkdown Checklist (SWC)

Equipment ID No.: 2P-015B

--~~----------------------------------------------------

Equipment Class: (5) Horizontal Pumps Equipment

Description:

SAFETY INJECTION PUMP Project: Point Beach 2 SWEL 1 Location (Bldg, Elev, Room/Area): __;_PA'-"----B,'-8_._00-----'ft,,_S~l_P_U_M--'-P---=--A;_R_E_A;___ _ _ _ _ _ _ _ _ _ _ _ _ __

Manufacturer/Model:

Instructions for Completing Checklist This checklist may be used to document the results of the Seismic Walkdown of an item of equipment on the SWEL. The space below each of the following questions may be used to record the results of judgments and findings. Additional space is provided at the end of this checklist for documenting other comments.

Anchorage

1. Is anchorage configuration verification required (i.e., is the item one of the 50% Yes of SWEL items requiring such verification)?

2. Is the anchorage free of bent, broken, missing or loose hardware? Yes

3. Is the anchorage free of corrosion that is more than mild surface oxidation? Yes

4. Is the anchorage free of visible cracks in the concrete near the anchors? Yes

5. Is the anchorage configuration consistent with plant documentation? (Note: Yes This question only applies if the item is one of the 50% for which an anchorage configuration verification is required.)

Six 1-1/4" anchors per SQ-000077.

This issue has been entered into the corrective action program.

6. Based on the above anchorage evaluations, is the anchorage free of Yes potentially adverse seismic conditions?

C-66

Point Beach Nuclear Plant, Unit 2 Sheet 1 of2 1200114-R-002, Revision 0 Status: [Y] N U Seismic Walkdown Checklist (SWC)

Equipment JD No.: -'2=X-=-*-=-13::....__ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __

Equipment Class: _(L..:4:L)..:..Tr:..::a::..:n.=.:s~~o:..:.:rm:..:..:e~rs::..__ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __

Equipment

Description:

28-03 STATION SERVICE TRANSFORMER Project: Point Beach 2 SWEL 1 Location (Bldg, Elev, Room/Area): _C=:.:B: :J'"-=2:. : 6.:. :.0;. :.0. . :. ft:!. . ,-=-C=SR:...:___ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __

Manufacturer/Model:

Instructions for Completing Checklist This checklist may be used to document the results of the Seismic Wall<down of an Item of equipment on the SWEL. The space below each of the following questions may be used to record the results of judgments and findings. Additional space Is provided at the end of this checldlst for documenting other comments.

Anchorage

1. Is anchorage configuration verification required (I.e., Is the item one of the 50% Yes of SWEL Items requiring sUch verification)?

2. Is the anchorage free of bent, broken, missing or loose hardware? Yes

3. Is the anchorage free of corrosion that Is more than mild surface oxidation? Yes

4. Is the anchorage free of visible cracks In the concrete near the anchors? Yes

5. Is the anchorage configuration consistent with plant documentation? (Note: Yes This question only applies If the Item Is one of the 50% for which an anchorage configuration verification Is required.)

NE plate has north-south bolt spacing of 12~3/8'~ which Is Jess than the 13" minimum shown on SK-MR-94-012. All dimensions are enveloped by calculation 95-0168, Rev2, Therefore, the as built condition matches the plant documentation.

6. Based on the above anchorage evaluations, Is the anchorage free of Yes potentially adverse seismic conditions?

C-86

Point Beach Nuclear Plant, Unit 2 Sheet 1 of 2 1200114-R-002, Revision 0 Status: [YJ N U Seismic Walkdown Checklist (SWC)

Equipment ID No.: . . .:D=-*. . :.1=..3_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __

Equlpment Class: (14) Distribution Panels Equipment

Description:

125V DC DISTRIBUTION PANEL Project: Point Beach 2 SWEL 1 Location (Bldg, Elev, Room/Area): _C.;;;..B:::..J,'-"2;;..;;;6"'"'.0'--'0-'"ft"--,-'-C-'-S:. . :R_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __

Manufacturer/Model:

Instructions for Completing Checklist This checklist may be used to document the results of the Seismic Walkdown of an Item of equipment on the SWEL. The space below each of the following questions may be used to record the results of judgments and findings. Additional space Is provided at the end of this checklist for documenting other comments.

Anchorage

1. Is anchorage configuration verification required (I.e., Is the Item one of the 50% Yes of SWEL Items requiring such verification)?

2. Is the anchorage free of bent, broken, missing or loose hardware? Yes Panel mounted to 4 Unlstrut P-1000 channels on wall. Each Unlstrut Is mounted with 2- 3/8" expansion anchors. Calculation 2000-0024, Rev. 1 ldentff/es mounting with additional center anchors In top and bottom Unlstrut channels; these anchors are not accessible.

3. Is the anchorage free of corrosion that Is more than mild surface oxidation? Yes

4. Is the anchorage free of visible cracks In the concrete near the anchors? Yes

5. Is the anchorage configuration consistent with plant documentation? (Note: Yes This question only applies If the Item Is one of the 50% for which an anchorage configuration verification Is required.)

Verified per Calculation 2000-0024, Rev. 1, which conservatively Ignored the center anchors In the top and bottom Unlstrut channels.

6. Based on the above anchorage evaluations, Is the anchorage free of Yes potentially adverse seismic conditions?

C-116

Point Beach Nuclear Plant, Unit 2 Sheet 1 of2 1200114-R-002, Revision 0 Status: [Y] N. U Seismic Walkdown Checklist (SWC)

Equipment ID No.: . .;P:. . *. .: .0: : :32::.:.F_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __

Equipment Class: {6} Vertical Pumps Equipment

Description:

SERVICE WATER PUMP Project: Point Beach 2 SWEL 1 Location (Bldg, Elev, Room/Area): _C::..W~PH:..:.,!,...:B:..:.:.O:..::O:....:ft'-'-,.:::.SW.:...:....:B:.::L:.::D-=G'----------------

Manufacturer/Model:

Instructions for Completing Checklist This checklist may be used to document the results of the Seismic Walkdown of an Item of equipment on the SWEL. The space below each of the following questions may be used to record the results of judgments and findings. Additional space Is provided at the end of this checklist for documenting other comments.

Anchorage

1. Is anchorage configuration verification required (I.e., Is the Item one of the 50% No of SWEL Items requiring such verification)?

2. Is the anchorage free of bent, broken, missing or loose hardware? Yes

3. Is the anchorage free of corrosion that Is more than mild surface oxidation? Yes Some corrosion on SE corner baseplate anchor: washer and baseplate corner.

No 1mmedhite seisni.ic concern. This issue has been entered into the station corrective action process.

4. Is the anchorage free of visible cracks In the concrete near the anchors? Yes Hairline crack at the NE corner baseplate Is judged to be acceptable.

5. Is the anchorage configuration consistent with plant documentation? (Note: Not Applicable This question only applies if the item Is one of the 50% for which an anchorage configuration verification Is required.)

6. Based on the above anchorage evaluations, Is the anchorage free of Yes potentially adverse seismic conditions?

C-146

Point Beach Nuclear Plant, Unit 2 Sheet 1 of2 1200114-R-002, Revision 0 Status: I:YJN u Seismic Walkdown Checklist (SWC)

Equipment ID No.: _T.:....-...::.03=-1=-=B=------------------------

Equlpment Class: (21) Tanks and Heat Exchangers Equipment

Description:

G-02 DIESEL GENERATOR DAY TANK Project: Point Beach 2 SWEL 1 Location (Bldg, Elev, Room/Area): _C:: : B: J' -=8:.:. :.0:. : 0. . :.:ft:!. . ,G.=.-c.. : 0.=.2. :. . R: . :M.:. . .__ _ _ _ _ _ _ _ _ _ _ _ _ _ __

Manufacturer/Model:

Instructions for Completing Checklist This checklist may be used to document the results of the Seismic Walkdown of an Item of equipment on the SWEL. The space below each of the following questions may be used to record the results of judgments and findings. Additional space Is provided at the end of this checklist for documenting other comments.

Anchorage

1. Is anchorage configuration verification required (I.e., Is the Item one of the 50% Yes of SWEL Items requiring such verification)?

2. Is the anchorage free of bent, broken, missing or loose hardware? Yes

3. Is the anchorage free of corrosion that Is more than mild surface oxidation? Yes

4. Is the anchorage free of visible cracks In the concrete near the anchors? Yes Crack located above east top bolt, approximately 6" away. Cracks acceptable since anchors are through bolts.

5. Is the anchorage configuration consistent with plant documentation? (Note: Yes This question only applies If the Item Is one of the 50% for which an anchorage configuration verification Is required.)

Tank Is mounted to steel frame with 618 11 diameter bolts and the frame Is mounted with 1 thru bolts and one anchor welded to tan embed plate.

II Calculation N-90-043, Rev. 0, Attachment 2 shows analysis for 518 11 mounting bolts for tank and 111 thru bolts for the attachment of the frame to the wall.

Therefore, the plant documentation Is confirmed.

6. Based on the above anchorage evaluations, Is the anchorage free of Yes potentially adverse seismic conditions?

C-162

Point Beach Nuclear Plant, Unit 2 Sheet 1 of2 1200114-R-002, Revision 0 Status*: [Y] N U Seismic Walkdown Checklist (SWC)

Equipment ID No.: _T.:....*_,_17::....;1:..:B:___ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __

Equipment Class: (21} Tanks and Heat Exchangers Equipment

Description:

G-04 EDG STARTING AIR RECEIVER Project: Point Beach 2 SWEL 1 Location (Bldg, Elev, Room/Area): ....:D=-G=B,L..:2:=8:.:.:.0:..::0:...:.ft:L,-=G~-0:....:4:...:.R..::.M.:..:..__ _ _ _ _ _ _ _ _ _ _ _ _ __

Manufacturer/Model:

Instructions for Completing Checklist This checklist may be used to document the results of the Seismic Walkdown of an Item of equipment on the SWEL. The space below each of the following questions may be used to record the results of judgments and findings, Additional space Is provided at the end of this checklist for documenting other comments.

Anchorage

1. Is anchorage configuration verification required (I.e., Is the Item one of the 50% Yes of SWEL Items requiring such verification)?

2. Is the anchorage free of bent, broken, missing or loose hardware? Yes Anchored to floor with 4 posts, 2- 6/8" bolts each.

Attached to wall at mldhe/ght to two base angles with 2 - ~~~bolts each.

3. Is the anchorage free of corrosion that Is more than mild surface oxidation? Yes

4. Is the anchorage free of visible cracks In the concrete near the anchors? Yes Minor cracks In grout are judged to be acceptable.

5. Is the anchorage configuration consistent with plant documentation? (Note: Yes This question only applies If the Item Is one of the 60% for which an anchorage configuration verification Is required.)

Anchorage ver/flt:Jd per drawing E-121202, Rev. 8 For floor anchor bolts and drawing E-221601, Rev. .3. for wall anchor bolts.

6. Based on the above anchorage evaluations, Is the anchorage free of Yes potentially adverse seismic conditions?

C-172

Point Beach Nuclear Plant, Unit 2 Sheet 1 of2 1200114-R-002, Revision 0 Status: [Y] N U Area Walk-By .Checklist (AWC)

Location (Bldg, Elev, Room/Area): Area Walk-by 28: Pump House El. 8'. North Room.

Instructions for Completing Checklist This checklist may be used to document the results of the Area Walk-By near one or more SWEL Items. The space below each of the following questions may be used to record the results of judgments and findings.

Additional space Is provided at the end of this checklist for documenting other comments.

1. Does anchorage of equipment In the area appear to be free of potentially Yes adverse seismic conditions (If visible without necessarily opening cabinets)?

Bottom anchor bolt for W~28 not fully engaged.

Missing anchor bolt on baseplate NW of P-35A.

Loose grout at NE corner anchor bolt below SW-13.

These Issues have been entered Into the statfon corrective action process.

2. Does anchorage of equipment In the area appear to be free of significant Yes degraded conditions?

Corrosion at P-320, P-32E baseplates n'oted In SWC.

Corrosion on P-318 baseplate. This Issue has been entered Into the station corrective action process.

Corrosion at P-32F baseplate noted on SWC.

3. Based on a visual Inspection from the floor, do the cable/conduit raceways and Yes HVAC dueling appear to be free of potentially adverse seismic conditions (e.g.,

condition of supports Is adequate and fill conditions of cable trays appear to be Inside acceptable limits)?

Overhead raceways and piping well supported.

4. Does It appear that the area Is free of potentially adverse seismic spatial Yes Interactions with other equipment In the area (e.g., ceiling tiles and lighting)?

Overhead piping well supported.

6. Does It appear that the area Is free of potentially adverse seismic Interactions Yes that could cause flooding or spray in the area?

Overhead piping well supported.

6. Does It appear that the area Is free of potentially adverse seismic Interactions Yes that could cause a fire In the area?

7. Does It appear that the area Is free of potentially adverse seismic Interactions Yes associated with housekeeping practices, storage of portable equipment, and temporary Installations (e.g., scaffolding, lead shielding)?

D-30

Point Beach Nuclear Plant, Unit 2 1200114-R-002, Revision 0 E

Plan for Future Seismic Walkdown of Inaccessible Equipment Completion of the walkdowns for four items must be deferred due to accessibility. One item requires a bus outage and five items require a refueling outage. Table E-1 summarizes the reasons each item is inaccessible during normal plant operation. PBNP CRs have been written to identify these deferred components and to provide a schedule the future Seismic Walkdowns for these items.

Table E-1. Summary of Inaccessible Equipment Scheduled Location Reason for Component ID Description Completion Inaccessibility T-034A 21/U2C/NW Safety Injection Access to containment is Complete QTR Accumulator restricted during plant operation SI-00841A 21/U2C/T-34A T-34A 81 Access to containment is Complete Accum. East Accumulator Outlet restricted during plant Operator operation SI-00878A 21/U2C/C-1 Air P-158 81 Pump R- Access to containment is Complete Lock Area East 1 Reactor Vessel restricted during plant Injection operation RH-00720 46/U2C/SE RHR Return to Access to containment is Complete QTR RCS restricted during plant operation C-035 8/CB/G-02 RM G-02 EDG Alarm Equipment energized Complete West Wall and Electrical Panel C-035A 8/CB/G-02 RM G-02 EDG Local Equipment energized Complete West Wall Transfer Panel C-079 8/CB/G-02 Rm G-02 EDG DC Equipment energized Complete Power Transfer Control Panel C-082 28/DGB/G-04 G-04 EDG Control Equipment energized Complete SWGR Rm Panel

Table E-1 Summary of Inaccessible Equipment Scheduled Location Reason for Component ID Description Completion Inaccessibility T-034A 21/U2C/NW Safety Injection Access to containment is Complete QTR Accumulator restricted during plant operation SI-00841A 21/U2C/T-34A T-34ASI Access to containment is Complete Accum. East Accumulator Outlet restricted during plant Operator operation SI-00878A 21/U2C/C-1 Air P-158 Sl Pump R- Access to containment is Complete Lock Area East 1 Reactor Vessel restricted during plant Injection operation RH-00720 46/U2C/SE RHR Return to Access to containment is Complete QTR RCS restricted during plant operation C-035 8/CB/G-02 RM G-02 EDG Alarm Equipment energized Complete West Wall and Electrical Panel C-035A 8/CB/G-02 RM G-02 EDG Local Equipment energized Complete West Wall Transfer Panel C-079 8/CB/G-02 Rm G-02 EDG DC Equipment energized Complete Power Transfer Control Panel C-082 28/DGB/G-04 G-04 EDG Control Equipment energized Complete SWGRRm Panel

Point Beach Nuclear Plant, Unit 2 1200114-R-002, Revision 0

3. PEER REVIEW TEAM & PROCESS The Point Beach (PBN) Peer Review Team consisted of Individuals from PBN operations, civil engineering, licensing, and PRA as well as structural/seismic engineers from Stevenson & Associates. These Individuals participated In phases of preparation, performance, and peer review of the seismic walkdowns. This section documents the peer review process and how the Peer Review Team Interacted with the Seismic Walkdown Engineering Teams.

3.1 Peer Review Team The affiliation, role, and qualifications for each Peer Review Team member are summarized In the following table.

Name Group Role* Qualifications **

Rick Merkes PBN Operations SWEL co-preparer (e)(f)

Douglas P. Brown PBN Civil Engineering Peer Review Team leader (b) (c) (g)

SWE SWEL co-preparer David N. Carter Stevenson &Assoc. SWE Team Ill leader (b) (c) (g)

(consultant eng.) SWEPR Nab II Juraydlnl Stevenson &Assoc. SWE Team #12 leader (b) (c) (g)

(consultant eng.) SWEPR Stanley E. Guokas PBN PRA Group PRTeam (d)

PBN -SWEL Preparer Russ Severson DAEC PRA Group SWELPR (d)

T.l<. Ram Stevenson &Assoc. SWELPR (d) (e) *

(consultant eng.)

Jeffery Buboltz PBN Civil Engineering SWE Team Member (b) (c) (g)

SWEPR Scott Kahl SWE Team Member (b) (c) (g)

SWEPR Richard l. LaPlante SWE Team Member (b)(c)(g)

SWEPR Careen A. McDonald SWE Team Member {b) (c) (g)

SWEPR .

Mark C. Nielsen SWE Team Member (b) (c) (g)

SWEPR License Basis PR Dave J. Nuttall SWE Team Member (b)(c)(g)

SWEPR License Basis PR Notes:

.. Role: PR (peer review), SWEL (seismic walkdown equipment list), SWE (seismic walkdown engineer)

• • Qualifications:

(a) Completed EPRI NTTF 2.3 Seismic Walkdown Training (b) Seismic engineering experience (c) Degree In mechanical engineering or civil/structural engineering (d) Seismic PRA /IPEEE experience F-3

Point Beach Nuclear Plant, Unit 2 1200114-R-002, Revision 0 (e) Knowledge of plant operations, documentation (f) Plant Operations member (g) Completed SQUG Walkdown ScrGenlng and SG/sm/c Evaluation Training Course 3.2 Peer Review Process PRTeam Lead Doug Brown served as the Peer Review Team Lead. In that role, he was responsible for coordinating the peer review and assembling this report. As described below, he also performed some additional roles as part of the walkdown team and checklist PR. He also participated in the SWEL preparation, so he was not part of that PR process. *That Is, even though he was a SWEL co-preparer, the SWEL was independently reviewed and he did not partake in any of the SWEL PR. Therefore, performing as the lead peer review Is considered acceptable.

SWEL Preparation The SWEL was prepared by S. Guokas, who Is a PBN PRA engineer, with familiarity with the PBN IPEEE Report and the PBN PRA model. Additional input Into the SWEL was provided by a plant staff structural/seismic engineer (D. P.

Brown), and a Plant Operations representative (R. Merkes).

The SWEL was Peer Reviewed by a team that included a PRA engineer (R.

Severson), and a Seismic PRAIIPEE engineer (T.K. Ram).

Seismic Walkdown The primary seismic walkdown was conducted with two teams, each with two qualified structural/seismic engineers. A contractor engineer severed as Team Leader of each team. The second team member was an available PBN SWE or the two contract engineers worked together as one team.

The Peer Review of the walkdowns consisted of a Peer Review Team Lead with Operations and PRA knowledge, and structural/seismic engineers. The structural/seismic engineers made up the SWE teams, but also served to peer review each other's work. The Peer Review Team Lead also participated in a few of the walkdowns for logistical support. The ultimate judgments regarding licensing basis were made by qualified Point Beach structural engineers.

• Seismic Walkdown Engineers (SWE):

- SWE Team #1- D. N. Carter (team lead),

- SWE Team #2- N. Juraydlnl (team lead),

- SWE Team member- D.P. Brown

- SWE Team member- J. Buboltz F-4