Text

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)
	v • d • e

October 3, 2013 NEXTera***

ENERGY~

~

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)

(2)

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)

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 "C

Cl "C

s:::

Q)

I E N

Equipment "C

Action Taken to Potentially Adverse Seismic Condition ltl s:::...

'iij Current Status ID 0

0 Address the Condition Cl z.,_

s:::

Q) s:::

ltl c

0 s:::

CJ

J NextEra Engineer A section of tubing is supporting the solenoid and determined from P&ID 1MS-02090 attached flexible conduit fitting. The solenoid and the X

drawings that a loss of Being tracked in 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 south side of panel DY-OC is in contact with an the panels and 1-83/DY-03 determined that the and DY-OC electrical fitting attached to panei1-83/DY-03. It is X

interaction would not Closed uncertain what components are in each panel.

affect the operability of the components.

Initiated CR.

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

the modification and anchors.

calculation determined the CAP.

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 02020.

not a seismic concern initiated to repair.

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

C)

"C Q)

Q)

I E N

Equipment "C

Action Taken to Potentially Adverse Seismic Condition

!tl (ij Current Status ID 0

0 Address the Condition C) z-Q)

!tl c

0 u

J The walkdown team determined that the light fixture would not fall and interact with seismically 1 P-014A An overhead light fixture was raised by overlapping the X

qualified equipment Work Request 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 1 B-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.

Chain for valve SF-1 can interact with the oiler on the behind conduit and Chain is tied off P-012A X

judged not to pose a pump.

current concern.

to a support with Initiated CR.

seal type lock.

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

C)

"C Q)

Q)

I E N

Equipment "C

Action Taken to Potentially Adverse Seismic Condition 11:1 iii Current Status ID 0

0 Address the Condition C) z.,_

Q) 11:1 c

0 (J

=>

Per calculation 91 C2696-C-021 a spacing of 9", 9", 9" is East bolt spacing is not per drawing EC-36A-3, Job used. There is a safety factor of 42.5 on these HX-013A 12703, Rev. 3. Bolts are spaced at 8", 9" and 8" in the X

anchors. Therefore, they Being tracked in north south direction. The drawing shows the bolts are concluded to be the CAP.

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 East bolt spacing is not per drawing EC-36A-3, Job used. There is a safety factor of 42.5 on these HX-013B 12703, Rev. 3. Bolts are spaced at 7 %"", 9 %""and X

anchors. Therefore, they Being tracked in 7 %"" in the north south direction. The drawing shows are concluded to be the CAP.

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 P-32A Overhead trolley control pendant wedged between X

and pump casing are Work request 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

't:J C)

't:J 1:

Q)

I.E N

't:J Action Taken to Area Potentially Adverse Seismic Condition

!tl 1:...

iii Current Status 0

0 Address the Condition C) z-1:

Q) 1:

!tl c

0 1:

(.)

J The seismic walkdown team assessed the potential interaction during the walkdown The instrument pipe behind valve 1RH-716B has a long and determined not to Work request AWB3 X

be a concern. The pipe horizontal cantilever. The first support clamp is loose.

will not move enough to initiated to repair.

interact and damage seismically qualified equipment.

Initiated CR.

NextEra Engineer determined that the AWBS Masonry wall located behind 2CV-351. Could not X

masonry wall was not in 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 AWB8 The nuts for the south post for 1T-006A are not fully X

sufficient capacity in the Work request 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

'0 C)

'0 Q)

Q)

I E N

'0 Action Taken to Area Potentially Adverse Seismic Condition ns jij Current Status 0

0 Address the Condition C) z,._

Q) ns c

0 0

J In the judgment of the walkdown team, the AWB9 An S-Hook supporting a light fixture was observed to be X

light fixture would not Work request opened.

fall and interact with any initiated to repair.

seismically qualified equipment. Initiated CR.

The seismic walkdown team determined that the tubing was AWB 15 The public address speaker is close to an instrument X

sufficiently rugged that Work request 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 A 3/8" tube for valve 1 SI-881A has a long span (-1 0')

deflect but not break in Work request AWB 19 X

a seismic event. A and is very flexible.

preliminary calculation initiated to repair.

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

'0 C)

'0 c

Q)

I "j§ N

'0 Action Taken to Area Potentially Adverse Seismic Condition Ill c,_

Ia Current Status 0 0 Address the Condition C) z-c Q) c Ill 0

0 c

(.)

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

seismic concern. There Work request hose could dislodge from the clamps and interact with were no soft targets initiated to repair.

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 X

to nearby cable tray Work request 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 X

support in the horizontal Work request 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 X

tested and determined 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 "0

C)

"0

-=

Q)

N "0

I E Action Taken to Area Potentially Adverse Seismic Condition IU s:::...

"ii Current Status 0 0 Address the Condition C) z-s:::

Q) s:::

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 AWB20 resisting dead load welded to a four bolt anchor plate at X

acceptable since the Being tracked in each end. One of the anchors on the south plate is support is lightly loaded.

the CAP.

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 Various housekeeping items identified at Elevation 66, judged the items Work request AWB24 X

acceptable due to no above the SFP Hx area soft targets in the area.

initiated to repair.

Initiated CR.

The walkdown team AWB24 The anchors for T-161A appear to be in oversized holes X

judged the anchors to Work request and some had minor corrosion.

be adequate to support initiated to repair.

the tank. Initiated CR.

The walkdown team judged the piping to not AWB24 The piping from T-161C to the header is not clamped to X

be a falling hazard Work request 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 X

of the pipe support is 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

C'l "C

c:

Q)

N "C

I E

Action Taken to Area Potentially Adverse Seismic Condition ctS c:....

iii Current Status 0

0 Address the Condition C'l z-c:

Q) c:

ctS c

0 c:

(J

J AWB27 There is a missing anchor bolt on the pipe support west X

Previously identified Work Request of P-31A and evaluated in CR.

initiated to repair.

AWB27 There is a missing anchor bolt on the base plate north X

Previously identified Work Request west of P-31A for a chlorination line.

and evaluated in CR.

initiated to repair.

Corrosion evaluated by Closed.

NextEra Engineering Will be tracked AWB27 There is corrosion on P-31A and P-318 base plates.

X and determined to through structures minor surface corrosion and not a concern. CR monitoring initiated.

program.

NextEra Engineering performed a walkdown The G-01 diesel room contains threaded fire protection and determined that 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 AWB42 attached to a shell type anchor in the concrete ceiling.

X room and it was Being tracked in On the west end, the fire protection line and a sprinkler determined that the the CAP.

head are relatively close to the room fans. The Seismic piping is within code Walkdown Team was unable to conclude that the fire protection pipe and sprinkler head would not move and allowable stresses 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:::

Q)

. *e N

"C

~

Action Taken to Current Status co s:::...

Potentially Adverse Seismic Condition 0

0 co Address the Condition Area s:::

Cl z..,_

Q) s:::

co 0

0 s:::

(,)

l The walkdown team determined that the AWB48 The cable tray overhead spanning from C-180 to C-181 X

cable tray is sufficiently Closed is sagging and several of the rungs are bent.

supported that it would not fall. CR initiated.

Outlier No.

3 5

8 10 POINT BEACH NUCLEAR PLANT, UNIT 1 1200114-R-001, REVISION 0 Table 3 IPEEE and A-46 Outlier Resolution -Unit 1 Program Equip System Equip Noun Name Status at Time of SRT Outlier Description Interim Resolution Documented Class ID Walkdown in 1993 in the USI A-46 Seismic Evaluation Report to NRC A, I 2

480V 18-480v 0-ANCHORAGE The anchorage weld There is sufficient anchorage 03 Safeguards INSUFFICIENT, Weld spacing is too large, capacity in the existing welds to Load Center spacing is to large.

every 3rd cabinet in carry the seismic anchorage Every 3rd cabinet in some cases. The loads. However, the switchgear some cases. TROLLEY trolley hoist that was declared an outlier because HOIST needs to be rides along the top it is not good engineering clamped in place. T.

of the switchgear practice to transfer the seismic Dykstra to submit poses an interaction loading through the switchgear separate EWRs for weld hazard.

structure. The switchgear is 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 18-480v 0-ANCHORAGE The anchorage weld There is sufficient anchorage 04 Safeguards INSUFFICIENT, Weld spacing is too large, capacity in the existing welds to Load Center spacing is to large.

every 3rd cabinet in carry the seismic anchorage Every 3rd cabinet in some cases. The loads. However, the switchgear some cases. TROLLEY trolley hoist that was declared an outlier because HOIST needs to be rides along the top it is not good engineering clamped in place. T.

of the switchgear practice to transfer the seismic Dykstra to submit poses an interaction loading through the switchgear separate EWRs for weld hazard.

structure. The switchgear is 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 13 Service FRICTION CLIPS. MR anchorage uses adequate capacity to withstand Transformer in process. MR 94-012 friction clips which the P8NP SSE, because the are not covered by friction coefficient exceeds the 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 14 Service FRICTION CLIPS. MR anchorage uses adequate capacity to withstand Transformer in process. MR 94-012 friction clips which the P8NP SSE, because the are not covered by friction coefficient exceeds the the GIP.

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

B-14 Status I Final Required Date Resolution Close Out Completed MR 95-005 SQ-001544, 7/6/99 installed new SQ-001531 anchorage (WO completed 9700600). EWR 96-042 evaluated breaker handling trolley. EWR closed. MR 98-094 installed trolley stops.

MR 95-005 SQ-001545, 7/6/99 installed new SQ-001535 anchorage. EWR complete 96-042 assigned to evaluated breaker handling trolley.

EWR closed. MR 98-094 installed trolley stops.

MR 94-012 SQ-001703 8/1/97 installed new completed anchorage-accepted 4/16/96.

MR 94-012 SQ-001799 8/1/97 installed new completed anchorage-accepted 4/16/96.

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 12 A, I 5

RH 1P-Residual Heat 0 - Anchorage failed The pump The pump anchorage was S&ACalc SQ-1842 11/5/02 10A Removal anchorage has less analyzed in accordance with 91 C2696-C-008 completed.

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.

13 A, I 5

RH 1P-Residual Heat 0 - Anchorage failed The pump The pump anchorage was S&ACalc SQ-1802 11/5/02 108 Removal anchorage has less analyzed in accordance with 91 C2696-C-008 completed.

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.

16 A, I 5

Sl 1P-Containment 0 - Failed Anchorage The anchor J-bolts A calculation per ACI 318-63 S&ACalc SQ-1805 11/12/02 14A 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.

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 18 A, I 5

Sl 1P-Containment 0 - Failed Anchorage The anchor J-bolts A calculation per ACI 318-63 S&A Calc SQ-1806 11/12/02 148 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.

20 A, I 6

SW P-Service Water 0 - Anchorage/capacity The pump extending The pump is considered S&ACalc SQ-1808 6/15/99 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.

21 A, I 6

sw P-Service Water 0 - Anchorage/capacity The pump extending The pump is considered S&ACalc SQ-1809 6/15/99 328 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.

26 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 8/30/00 466 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 0.02 hours 1.190476e-4 weeks 2.7396e-5 months 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.

28 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 8/30/00 476 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 0.02 hours 1.190476e-4 weeks 2.7396e-5 months 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.

34 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 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 36 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-001987 3/10/98 3200 212 Monitor inspection, the building in a climate control for the IPEEE only. Subsequent 96-044 complete.

resolves 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.

39 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 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 41 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 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 43 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 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 45 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 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 47 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 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 48 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 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 49 I,V,RG 7

Sl 1SI-T-34a/B Si 0 - 36" offset on 1.25" The AOV offset of The item has been walked down (MR 94-066*8 is SQ-001951 4/30/96 846 Accum line. Because of pipe 36" < 45" allowable for the IPEEE only. Subsequent incorrect) MR 95-completed 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.

52 I,RG 7

WG 1WG T-16 Rcdt 0 - Even though 24" Even though 24" The item has been walked down EWR 96-049 SQ-001775 1/14/00

-1786 Vent offset< 45" GIP offset < 45" GIP for the IPEEE only. Subsequent assigned - valves resolves 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.

54 I,RG 7

WG 1WG T-16 Rcdt 0 - Even though 24" Even though 24" The item has been walked down EWR 96-049 SQ-001776 1/14/00

-1787 Vent offset < 45" GIP offset< 45" GIP for the IPEEE only. Subsequent assigned - valves resolves 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 56 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 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 58 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 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.

-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 60 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 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 62 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 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.

- 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

Outlier No.

64 65 66 67 POINT BEACH NUCLEAR PLANT, UNIT 1 1200114-R-001 REVISION 0 Program Equip System Equip Noun Name Class ID A, I 10 VNAFW HX-Auxiliary Feed 66 Pump Area Cooler A, I 10 VNAFW HX-Auxiliary Feed 66A Pump Area Cooler A, I 10 sw HX-Residual Heat 98 Removal Pump Area Cooling Coil A, I 10 VNRC 1W-Containment 4A Cavity Cooling Fan Status at Time of SRT Walkdown in 1993 0 - Rubber isolators fail.

They do not have sufficient shear and tension capacity to transfer the anchor loads to the concrete expansion anchors.

0 -The Spring isolator base plate yields.

0 - Mounted on Neoprene pads. Pads need further eva I per GIP Section 4.4.

Evaluation by S&A?

5/22/95 - During the bolt tightness check on 2/20/95, the concrete expansion anchors for the left rear rubber vibration isolator were found to be never installed 0 - No anchorage Anchored during U1 R21 by TCM and ARB.

MR 94-032.

B-24 Outlier Description Interim Resolution Documented Status I Final Required Date in the USI A-46 Seismic Resolution Close Out Completed Evaluation Report to NRC The air handling unit HX-66 is on the SSEL to EWR 96-046 SQ-001672.

5/15/99 is mounted on maintain SW system integrity.

assigned. MR 97-Outlier is rubber vibration The air handling and air cooling 104 installed resolved.

isolators. The function is not required. The SW replacement anchorage system engineer judged that a vibration isolators.

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

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.

The air handling unit HX-66A is on the SSEL to EWR 96-047 SQ-001888 12/14/00 is mounted on spring maintain SW system integrity.

assigned. MR 98-Outlier is 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.

The air handling unit HX-98 is on the SSEL to EWR 96-048 SQ-001841.

9/19/00 is mounted on maintain SW system integrity.

assigned. MR 97-Outlier is rubber vibration The air handling and air cooling 105 installed. WO resolved.

isolators. The function is not required. The SW 9807185 replaced anchorage system engineer judged that a HX-98 cooling calculation break in the attached 2 1/2" SW coils.

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.

The air handling unit The unit was anchored during Fixed, MR 94-032 SQ-001651 9/29/94 was found that same U1 R21 outage under installed new resolves unanchored.O-No modification MR 94-032.

anchorage-outlier.

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 68 A, I 10 VNRC 1W-Containment 0 - No anchorage The air handling unit The unit was anchored during Fixed, MR 94-032 SQ-001652 9/29/94 4B 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.

69 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 38A1 Spreading Motor on steel isolation anchored, the maintain SW integrity. A leak in assigned. Chiller Outlier is

,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.

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

,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.

71 A, I 12 DA K-4B G-02 Edg 0 - Loose hand crank A loose hand crank Hand crank installed on a Hand crank SQ-001822 4/21/95 Starting Air resting against it which was resting against bracket on the wall adjacent to installed on a Outlier is 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 72 A, I 16 125V D-07 Station 0 - Interaction, The battery charger The battery charger does not MR 94-048 bolted SQ-001938 12/13/00 Battery CABINET IS NOT TIED is not attached to the contain essential relays, and D-07 to the old 2A-Outlier is 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.

73 A, I 16 125V D-08 Station 0- Interaction, The battery charger The battery charger does not MR 94-048 bolted SQ-001939 12/18/00 Battery CABINET IS NOT TIED is not attached to the contain essential relays, and D-08 to 1A-05.

Outlier is 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.

74 A, I 16 y

DY-Red 125v 0- Interaction; The outlier is an The inverter does not contain MR 96-037 SQ-001867 5/25/00 OA Dc/120v Ac Mounted directly interaction. DY-OA any essential relays. It is IEEE assigned to move Outlier is 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 1 C-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.

75 A, I 16 y

DY-Blue 125v 0 - Interaction; The outlier is an The inverter does not contain MR 96-037*A SQ-001868 5/25/00 OB Dc/120v Ac Mounted directly interaction. DY-OB any essential relays. It is IEEE assigned to move Outlier is 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 78 I

19 RH 1TE-Hx-11a Rhr 0 - Interaction. Pinned The outlier concern The piping analysis shows that MR 96-036 SQ-001823 7/21/97 622 Hx Outlet against pipe support.

is interaction. The the maximum expected pipe assigned. MR 96-Outlier is 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.

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

-04 secured. EWR spatial interaction under modification MR 94-021.

cabinets to the resolved.

submitted. 7/25/94-hazard.

back of 1 C-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 82 A, I 20 MMS 1C-Plant Process 0 -1C-105 door binding, The door on 1 C-1 05 The cabinet was bolted to the Fixed, MR 94-021 SQ-001827 8/24/94 105-I&C Cabinets not secured. Interaction was identified as back of 1 C-03 under MR 94-bolted supply completed.

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 1 C-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.

84 A, I 20 RP 1C-Plant Process 0- Interaction -Table in An adjacent supply The supply cabinet was Fixed, MR 94-021 SQ-001831 8/24/94 115-I&C Cabinets SE corner should be cabinet posed a attached to the back of 1 C-03 bolted supply completed.

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.

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

87 A, I 20 ESF 1C-Safeguards 0- ANCHOR DETAIL The anchor detail for Since the cabinet has MR 95-011 SQ-001524 12/2/97 156-Train A Relay Unknown. No specific the grout pad and anchorage as originally cancelled, work completed.

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

Outlier No.

89 90 93 95 POINT BEACH NUCLEAR PLANT, UNIT 1 1200114-R-001 REVISION 0 Program Equip System Equip Noun Name Class ID A, I 20 ESF 1C-Safeguards 158/1 Train BAnd 66/16 Mise Relay 7

Cabinets A, I 20 RP 1C-RpTrain B 161-Relay Logic 165 Cabinet (Red)

A, I 20 COMP C-Computer 178-Input Mux 179 A,I,C 21 cc 1T-Component 12 Cooling Surge Tank Status at Time of SRT Outlier Description Walkdown in 1993 0- Interaction; The outlier is an Mounted directly Interaction. The adjacent to inverter DY-cabinets are OA. The cabinets are mounted directly not fastened together.

adjacent to inverter P-REPORT Provide DY-OA. The Mod Package cabinets are not fastened together.

0- ANCHOR DETAIL The anchor detail for Unknown. No specific the grout pad and information on the grout the perimeter pad to concrete floor channel is unknown.

anchorage.

Needs EWR 0 - Line Printer adjacent Line Printer, LP-300, to cabinet is kept on the floor adjacent to the cabinet.

0 - Oversized anchor The saddle bolt holes (2.25" x 1.18")

anchorage on both identified from WEST ends of the tank has 685J114. Anchor bolts oversized anchor are 1" diameter. Too bolt holes (2.25" x much clearance to say 1.18") identified from seismic load is WEST 685J114. The transferred to enough anchor bolts are 1" anchor bolts.

diameter. Therefore, there is too much clearance to say seismic load is transferred evenly to enough anchor bolts B-29 Interim Resolution Documented Status I Final Required Date in the USI A-46 Seismic Resolution Close Out Completed Evaluation Report to NRC No "bad actor" relays are MR 96-037 SQ-001869 5/25/00 located in the cabinets. The assigned to move Outlier is relays in the cabinets have a inverter to create a resolved.

seismic capacity of at least 4 gap between g's. Therefore, they are inverter and relay considered seismically cabinet. WO operable. The cabinet will be 9805185.

fastened to the adjacent Installation inverter.

complete Since the cabinet has MR 95-009 SQ-001843 12/2/97 anchorage as originally cancelled, work Outlier is designed, it is considered combined with MR resolved.

seismically operable.95-007. MR 95-007 Modification request MR 95-009 upgraded the will upgrade the anchorage.

anchorage-accepted 4/15/96 C-178-179 are computer 12/30/98 - Have SQ-001834 12/30/98 cabinets contain primarily solid inspected the Outlier is state and circuit board Computer Room on resolved.

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.

There are large washers MR 94-091*C SQ-001836 8/5/96 between the anchorage nut and installed 1/2" steel Outlier is the oval holes. Therefore, some plate under each of resolved.

load will be transferred to all of the nuts on the the anchor bolts. In addition, the south side of the attached piping will help in tank. The plate is restraining the tank. Therefore, welded to the the tanks are considered saddle. The seismically operable. The installation was anchorage will be upgraded with checked 12/3/97 a structural member between the tank base and the anchor bolt.

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 97 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 13 Water Storage ANAL YSIS/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.

99 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 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.

100 A, I 22 AUX Pab 8' Cable LAR 9 is an Work completed SQ-001714 8/1/00 8FT A

& 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.

101 A, I 22 SPR Csr Cable &

LAR 3 & LAR 4 are MR 96-080 created SQ-001881 9/25/00 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.

Outlier No.

102 103 104 POINT BEACH NUCLEAR PLANT, UNIT 1 1200114-R-001 REVISION 0 Program Equip System Equip Noun Name Class ID A, I 22 U1C2 U1c 21' Cable 1FT A

& Conduit REA Raceways A, I 22 U1C4 U1c 46' Cable 6FT A

& Conduit REA Raceways A, I 22 U1C4 U1c46' Cable 6FT A

& Conduit REA Raceways Status at Time of SRT Walkdown in 1993 0 - Loose base clip angle 0 - Cables not tied to tray 0 - Cables not tied to tray B-31 Outlier Description Interim Resolution Documented Status I Final Required Date in the USI A-46 Seismic Resolution Close Out Completed Evaluation Report to NRC One outlier was DNC & TJD1 SQ-001388 6/4/98 noted on the floor-to-inspected &

resolves 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.

( 1) Vertical trays Resolved during SQ-001549 6/4/98 1VR01 and 1VQ01 U1 R24. Verified resolves 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.

(2) Horizontal tray Resolved during SQ-001549 6/4/98 1VA04 at U1 R24. Verified resolves 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.

Outlier No.

106 107 109 POINT BEACH NUCLEAR PLANT, UNIT 1 1200114-R-001 REVISION 0 Program Equip System Equip Noun Name Class ID A, I 1

480V 18-480v Motor 32 Control Center Pab Safeguards A,I,RG 3

4.16KV 1A-4.16 KvBus 05 Switchgear (Safeguards)

A,I,RG 3

4.16KV 1A-4.16 KvBus 06 Switchgear (old)

(Safeguards)

Status at Time of SRT Walkdown in 1993 SAT End cabinet on right hand side, base channel CEA fastening nuts are loose. Need to be tightened. T. Dykstra to develop CEA torque tightness procedure, AI Bayer to review. Then submit WO to do torque tightness check. WO 9411729. Maintenance SAT WELD QUALITY IN

QUESTION, Recommend thorough weld inspection. T.

Dykstra to check with QA about weld inspections PO - Not fastened to adjacent D-08 battery charger. WELD QUALITY IN

QUESTION, Recommend thorough weld inspection. T.

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

The old 1 A-05 and old 1A-06 will be hard tied t~g_ether B-32 Outlier Description Interim Resolution Documented Status I Final Required Date in the USI A-46 Seismic Resolution Close Out Completed Evaluation Report to NRC 4/20/95 - Attempt NOT AN 4/20/95 to turn the nut OUTLIER-during the bolt Resolved in tightness test was the unsuccessful.

anchorage Application of analysis on torque >installation the original torque was not SEWS desirable due to possibility of breaking the bolt.

Since the bolt is loaded in shear only, this is considered acceptable Weld inspection NOT AN 7/3/02 completed, used OUTLIER-results to adjust resolved w/

anchorage capacity weld in the anchorage inspection calculation and 91 C2696-C-016.

anchorage calc.

MR 94-048 SQ-001939 12/18/00 connected cabinets Outlier is together. WO resolved.

9904505.

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.

118 A, I 15 125V D-05 125v De SAT- 0-SPACER, Need Resolved NOT AN 1/18/95 Station battery cell type OUTLIER-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 119 A, I 15 125V D-06 125v De SAT- 0-SPACER.

Resolved NOT AN 1/18/95 Station EWR submitted 2/4/94 OUTLIER-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 120 A, I 15 125V D-Swing Station SAT- 0-SPACER.

Resolved NOT AN 1/18/95 305 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 123 I,RG 18 AF LT-T-24b Cst 0 - Interaction, D

Deleted from SSEL Deleted 1/18/95 4039 Level POTENTIAL FOR from SSEL Transmitter BLOCK WALL TO FALL ON COMPONENT. T.

Dykstra to evaluate function of LT.

1/18/95

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

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

Dykstra to evaluate function of LT.

1/18/95

- L Ts removed from A-46 list. StiiiiPEEE and RG 1.97.

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

Dykstra to evaluate function of LT.

1/18/95

- L Ts removed from A-46 list. StiiiiPEEE and RG 1.97.

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

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

129 I,RG 18 Sl 1PT-T-34b Si SAT-resolved using Resolved on NOT AN 6/28/95 936 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.

SWEL SWEL 1-1 SWEL 1-1 SWEL 1-1 SWEL 1-1 SWEL 1-1 SWEL 1-1 SWEL 1-1 SWEL 1-1 SWEL 1-1 SWEL 1-1 SWEL 1-1 SWEL1-1 SWEL 1-1 SWEL 1-1 SWEL 1-1 SWEL 1-1 SWEL 1-1 SWEL 1-1 SWEL 1-1 SWEL 1-1 SWEL 1-1 SWEL 1-1 SWEL 1-1 SWEL 1-1 POINT BEACH NUCLEAR PLANT, UNIT 1 1200114-R-001, REVISION 0 ATTACHMENT A Seismic Walkdown Eauioment List Unit 1 & SFP (SWEL)

RISK N

UNIT SYS EQUIP WALK EQUIP#

EQUIP NAME 1

2 3

4 5

TRN E

CODE CLASS BY w

AREA y

1 AF 5

1 1P-029 AUX FEEDWATER TURBINE-DRIVEN PUMP X

X X

A 0

AF 5

1 P-03SA AUX FEEDWATER MOTOR-DRIVEN PUMP X

X X

A y

1 AF 7

1 1AF-04002 1P-29 AFP MINI RECIRC CONTROL X

X X

A 0

AF 7

1 AF-04007 P-3SA SSGP MINI RECIRC CONTROL X

X X

A 0

AF 7

1 AF-04012 P-3SA SSGP DISCHARGE CONTROL X

X X

A y

0 125V 14 1

D-63 125V DC DISTRIBUTION PANEL X

X X

X X A 0

AF 1S 1

RK-25A P-3SA SSGP INSTRUMENTATION RACK X

X X

A y

1 AF 21a 1

1T-212 1P-29 AFP MINI RECIRC lA 1AF-4002 BACKUP X

X X

A ACCUMULATOR 1

AF Sa 1

1AF-04000 1P-29 AFP DISCHARGE 1HX-1B SG INLET X

X X

A ISOLATION MOV 1

AF Sa 1

1AF-04001 1P-29 AFP DISCHARGE 1HX-1A SG INLET X X X

A ISOLATION MOV 1

AF Sa 1

1AF-04006 1P-29 AFP SUCTION FROM SERVICE WATER X

X X

A 0

AF Sa 1

AF-04009 P-3SA SSGP SUCTION FROM SERVICE X

X X

A WATER y

0 AF Sa 1

AF-04023 P-3SA SSGP DISCHARGE TO 1 HX-1A STEAM X

X X

A GENERATOR 1

MS Sb 1

1MS-02090 1 P-29 AFP BEARING COOLING INLET X

X X

A y

1 4SOV 2

9 1B-03 4SOV SAFEGUARDS LOAD CENTER X

X X

A y

1 4SOV 2

9 1B-04 4SOV SAFEGUARDS LOAD CENTER X

X X

B y

1 4SOV 4

9 1X-13 1B-03 STATION SERVICE TRANSFORMER X

X X

A y

1 4SOV 4

9 1X-14 1B-04 STATION SERVICE TRANSFORMER X

X X

B 1

y 14 9

1Y-203 WHITE 120V INVERTER DISTRIBUTION X

X X

A PANEL y

0 125V 14 9

D-12 125V DC DISTRIBUTION PANEL X

X X

A y

y 0

125V 14 9

D-14 125V DC DISTRIBUTION PANEL X

X X

B 1

y 16 9

1DY-01 RED 125V DC/120V AC INVERTER X

X X

A 0

y 16 9

DY-OB BLUE 125V DC/120V AC ALTERNATE X

X X

B INVERTER y

1 sw 7

s SW-00012A HX-12A CC HX OUTLET TEMPERATURE X

0 CONTROL B-38 IPEEE LOCATION DESC Equip.

Enhanced S/CB/AFP RM 1 P-29 CUB S/CB/AFP RM P-3SA CUB S/CB/AFP RM 1 P-29 CUB S/CB/AFP RM P-3SA CUB S/CB/AFP RM P-3SA CUB S/CB/AFP RM 1 P-29 CUB 1RK-S9 S/CB/AFP RM P-3SA CUB S/CB/AFP RM S/CB/AFP RM 1 P-29 CUB S/CB/AFP RM 1 P-29 CUB S/CB/AFP RM 1 P-29 CUB S/CB/AFP RM P-3SA CUB S/CB/AFP RM P-3SA CUB S/CB/AFP RM X

26/CB/CSR X

26/CB/CSR 26/CB/CSR WEST WALL 26/CB/CSR EAST 26/CB/CSR EAST 26/CB/CSR X

26/CB/CSR 46/PAB/CC HX AREA

SWEL SWEL 1-1 SWEL 1-1 SWEL 1-1 SWEL 1-1 SWEL 1-1 SWEL 1-1 SWEL 1-1 SWEL 1-1 SWEL 1-1 SWEL 1-1 SWEL 1-1 SWEL 1-1 SWEL 1-1 SWEL 1-1 SWEL 1-1 SWEL 1-1 SWEL 1-1 SWEL 1-1 SWEL 1-1 SWEL 1-1 SWEL 1-1 SWEL 1-1 SWEL 1-1 SWEL 1-1 SWEL 1-1 SWEL 1-1 POINT BEACH NUCLEAR PLANT, UNIT 1 1200114-R-001, REVISION 0 RISK N

UNIT SYS EQUIP WALK E

CODE CLASS BY w

AREA y

0 sw 7

s y

y 0

sw 7

s 1

cc 19 s

y 1

cc 21a s

y 1

cc 21b s

1 MS Sa s

1 y

14 10 1

y 14 10 y

0 125V 14 10 y

y 0

125V 14 10 y

0 125V 14 10 1

MMS 20 10 y

0 FO 5

26 y

0 DG 9

33 y

0 DG 9

33 y

y 0

VNDG 9

34 y

y 0

VNDG 9

34 y

0 125V 14 37 y

y 0

DG 17 3S y

0 DG 20 37 y

0 DA 21a 3S y

0 DG 17 42 0

VNDG 20 42 0

DG 20 42 0

DG 20 42 EQUIP#

SW-00012B SW-00012C 1TE-00621 1T-012 1HX-012A 1MS-02019 1MS-02020 1-43/Y-01 1-43/Y-02 D-16 D-17 D-1S 1 C-105 P-206A W-1S1A1 W-1S1A2 W-1S3B W-1S3C D-2S G-03 C-OS1 T-170A G-01 C-032 C-034 C-034A B-39 EQUIP NAME 1

2 3

4 5

TRN IPEEE LOCATION DESC Equip.

Enhanced HX-12B CC HX OUTLET TEMPERATURE X

0 46/PAB/CC HX AREA CONTROL HX-12C CC HX OUTLET TEMPERATURE X

0 46/PAB/CC HX AREA CONTROL HX-12A/B CC HX OUTLET HEADER X

X X

0 46/PAB/CC HX AREA TEMPERATURE RTD COMPONENT COOLING SURGE TANK X

X X

0 46/PAB/CC HX AREA COMPONENT COOLING WATER HEAT X

X X

0 46/PAB/CC HX AREA EXCHANGER HX-1B SG HEADER P-29 AFP STEAM SUPPLY X

X X

X A

46/PAB/BAST AREA S MOV HX-1A SG HEADER P-29 AFP STEAM SUPPLY X

X X

X A 46/PAB/BAST AREA S MOV 1Y-01 RED 120V AC VITAL INST PNL PWR X

X X

A 44/CB/CR WEST SUP TRANSFER SW 1Y-02 BLUE 120V AC VITAL INST PNL PWR X

X X

B 44/CB/CR WEST SUP TRANSFER SW 125V DC DISTRIBUTION PANEL X

X X

B 44/CB/CR SOUTH 125V DC DISTRIBUTION PANEL X

X X

A 44/CB/CR SOUTH 125V DC DISTRIBUTION PANEL X

X X

B 44/CB/CR NORTH SECONDARY SYSTEM POWER SUPPLIES X

X X

0 44/CB/CR PANEL G-01 EDG FUEL OIL TRANSFER PUMP X

X X

X X A

2S/DGB/G-01/2 FOTP RM G-03 EDG HX-265A RADIATOR FAN X

X X

B 50/DGB/G-03 RADTR RM G-03 EDG HX-265A RADIATOR FAN X

X X

X X B

50/DGB/G-03 RADTR RM G-03 EDG RM SMALL CAPACITY EXHAUST X

X X

B 50/DGB/G-03 FAN RM FAN G-03 EDG RM LARGE CAPACITY EXHAUST X

X X

B 50/DGB/G-03 FAN RM FAN G-03 EDG DC DISTRIBUTION PANEL X

X X

B 2S/DGB/G-03 SWGR RM EMERGENCY DIESEL GENERATOR X

X X

B 2S/DGB/G-03 RM G-03 EDG CONTROL PANEL X

X X

B 2S/DGB/G-03 SWGR RM G-03 EDG STARTING AIR RECEIVER X

X X

B 2S/DGB/G-03 RM EMERGENCY DIESEL GENERATOR X

X X

A S/CB/G-01 RM G-01 EDG EXHAUST FAN CONTROL PANEL X

X X

A S/CB/G-01 RM S WALL G-01 EDG ALARM AND ELECTRICAL PANEL X

X X

A S/CB/G-01 RM W WALL G-01 EDG LOCAL TRANSFER PANEL X

X X

X X A S/CB/G-01 RM W WALL

SWEL SWEL 1-1 SWEL 1-1 SWEL 1-1 SWEL 1-1 SWEL 1-1 SWEL 1-1 SWEL 1-1 SWEL 1-1 SWEL 1-1 SWEL 1-1 SWEL 1-1 SWEL 1-1 SWEL 1-1 SWEL 1-1 SWEL 1-1 SWEL 1-1 SWEL 1-1 SWEL 1-1 SWEL 1-1 SWEL1-1 SWEL 1-1 SWEL 1-1 SWEL 1-1 SWEL 1-1 SWEL 1-1 POINT BEACH NUCLEAR PLANT, UNIT 1 1200114-R-001, REVISION 0 RISK N

UNIT SYS EQUIP WALK E

CODE CLASS BY w

AREA 0

DG 20 42 0

FO 21a 42 0

DA 21a 42 0

FO Sa 42 y

2 4SOV 1

47 0

VNBI 10 4

1 y

14 7

0 125V 14 7

y 1

4.16K 3

21 v

y 0

125V 15 6

1 y

16 7

0 125V 16 7

0 y

16 7

0 VNBI 20 5

y 1

4SOV 1

14 y

1 cc 5

20 1

Sl 5

19 1

Sl 5

19 y

1 Sl 5

19 y

y 1

AF 5

41 y

1 AF 21a 41 y

1 AF Sa 41 EQUIP#

C-07S T-031A T-060B T-060C T-060E T-060F F0-03930 2B42-4212B W-OS5 1-S3/DY-03 D-03 1A-05 D-105 1DY-03 D-107 DY-OC C-022 1B312A-BS55B 1P-011A 1P-014A 1P-014B 1P-015A 1P-053 T-224B 1AF-04067 B-40 EQUIP NAME 1

2 3

4 5

TRN IPEEE LOCATION DESC Equip.

Enhanced G-01 EDG DC POWER TRANSFER CONTROL X

X X

X X A S/CB/G-01 RM W WALL PANEL G-01 DIESEL GENERATOR DAY TANK X

X X

A S/CB/G-01 RM G-01 EDG STARTING AIR RECEIVER (RIGHT X

X X

A S/CB/G-01 RM BANK)

G-01 EDG STARTING AIR RECEIVER (RIGHT X

X X

X X A S/CB/G-01 RM BANf9_

G-01 EDG STARTING AIR RECEIVER (LEFT X

X X

A S/CB/G-01 RM BANK)_

G-01 EDG STARTING AIR RECEIVER (LEFT X

X X

A S/CB/G-01 RM BANK)

T-31A G-01 EDG DAY TANK INLET SECOND X

X X

A S/CB/G-01 RM OFF ISOLATION 2B4212B-BS11M (D-109) CHGR NRM/ALT XFR X

X X

B 26/PAB/INVERT RM WEST SWITCH CONTACTOR PAB BATTERY AND INVERTER ROOM VENT X

X X

A 35/PAB/D-106 ROOF FAN 1 DY-03 WHITE INVERTER STATIC X

X X

A 26/PAB/INVERT RM WEST TRANSFER SWITCH 125V DC DISTRIBUTION PANEL X

X X

X X A

26/PAB/INVERT RM WEST 4.16 KV BUS SWITCHGEAR (SAFEGUARDS)

X X

X A S/CBNSG RM 125V DC STATION BATTERY X

X X

A 35/P AB/D-1 05 BATT RM WHITE 125V DC/120V AC INVERTER X

X X

X X A 26/PAB/INVERT RM WEST D-105 DC STATION BATTERY CHARGER X

X X

A 26/PAB/INVERT RM WEST WHITE 125V DC/120V AC INVERTER X

X X

A 26/PAB/INVERT RM WEST BATTERY ROOM HVAC CONTROL PANEL X

X X

A 26/PAB/NORTH 1 P-1 OA RHR PUMP NORMAUAL T TRANSFER X

X X

A S/PAB/COL P-11 SWITCH COMPONENT COOLING WATER PUMP X

X X

A S/PAB/CC PUMP AREA CONTAINMENT SPRAY PUMP X

A S/PAB/SPRAY PUMP AREA CONTAINMENT SPRAY PUMP X

B S/PAB/SPRAY PUMP AREA SAFETY INJECTION PUMP X

X X

A S/PAB/SI PUMP AREA UNIT 1 AUX FEEDWATER MOTOR-DRIVEN X

X X

B S/PAB/1P-53 AFP RM PUMP 1AF-4073B/1AF-4074B AFP RECIRC X

X X

B S/PAB/1P-53AFP RM ISOLATION lA ACCUMULATOR 1 P-53 AFP SERVICE WATER SUPPLY X

X X

B S/PAB/1P-53 AFP RM ISOLATION

SWEL SWEL 1-1 SWEL 1-1 SWEL 1-1 SWEL 1-1 SWEL 1-1 SWEL 1-1 SWEL 1-1 SWEL 1-1 SWEL 1-1 SWEL 1-1 SWEL 1-1 SWEL 1-1 SWEL 1-1 SWEL 1-1 SWEL 1-1 SWEL 1-1 SWEL 1-1 SWEL 1-1 SWEL 1-1 SWEL1-1 SWEL2 SWEL2 SWEL2 SWEL2 SWEL2 SWEL2 SWEL2 SWEL2 POINT BEACH NUCLEAR PLANT, UNIT 1 1200114-R-001, REVISION 0 RISK N

UNIT SYS EQUIP WALK E

CODE CLASS BY w

AREA 1

Sl 8a 19 1

Sl 8a 19 y

1 Sl 8a 19 y

1 AF 8b 41 y

1 cv 5

17 1

cv 7

13 y

1 cv 8a 18 y

1 Sl 8a 13 y

1 RH 5

2 y

1 RH 5

43 1

RH 7

3 1

RH 7

3 1

VNCC 9

53 1

PACV 19 54 1

Sl 21a 55,56 1

cv 21b 57 y

0 sw 6

27 1

Sl 8a 58 0

SF 5

24 0

SF 5

24 0

SF 21b 24 0

sw 8a 24 0

sw 8a 24 EQUIP#

1SI-00825A 1SI-00825B 1SI-00857A 1SI-00896A AF-04073B 1P-002A 1CV-00142 1CV-00112B 1SI-00866A 1SI-00866B 1P-010A 1 P-010B 1RH-00624 1RH-00625 W-001A1 TE-03292 T-034A HX-004 P-032A SI-00852A P-012B P-012A HX-013B HX-013A SW-02930B SW-02930A SW-02927B SW-02927A 8-41 EQUIP NAME 1

2 3

4 5

TRN IPEEE LOCATION DESC Equip.

Enhanced T-13 RWST OUTLET TO P-15AIB Sl PUMP X

X X

X X A

8/PAB/SPRAY PUMP AREA T-13 RWST OUTLET TO P-15AIB Sl PUMP X

X X

B 8/PAB/SPRAY PUMP AREA HX-11A RHR HXOUTLETTO P-15A Sl PUMP X

X X

A 8/PAB/SI PUMP AREA SUCTION P-15A Sl PUMP SUCTION X

X X

X X A

8/PAB/SI PUMP AREA 1P-53 AFP RECIRCULATION ISOLATION X

X X

B 8/PAB/1P-53 AFP RM CHARGING PUMP (Pump Only as Pressure X

X X

A 8/PAB/U1 CHG PUMP RM Boundary)

CHARGING LINE FLOW CONTROL X

X X

0 8/PAB/PIPEWAY #1 1 P-2A-C CHARGING PUMP REFUELING X

X X

A 8/PAB/U1 CHG PUMP AREA WATER SUCTION COLD LEG INJECTION LINE ISOLATION X

X X

A 8/PAB/PIPEWAY #1 CORE DELUGE INJECTION LINE ISOLATION X

X X

X X B

8/PAB/PIPEWAY #1 RESIDUAL HEAT REMOVAL PUMP X

X X

X X A

X

-19/PAB RESIDUAL HEAT REMOVAL PUMP X X X

X X

B X

-19/PAB HX-11A RHR HX OUTLET CONTROL X

X X

X X A

-5/PAB/EAST WALL OVHD HX-11B RHR HX OUTLET CONTROL X X X

X X B

-5/PAB/EAST WALL OVHD CONTAINMENT ACCIDENT RECIRCATION X

A 66/U1 C/NORTH FAN EL 66' U1C TEMPERATURE ELEMENT X

0 66/U1C/NE QTR SAFETY INJECTION ACCUMULATOR X X X

A 21/U1C/SW QTR EXCESS LETDOWN HEAT EXCHANGER X

0 21/U1C SERVICE WATER PUMP X

X A

X 8/CWPH/SW BLDG LOW HEAD Sl CORE DELUGE ISOLATION X

A 46/U1C/SEAL TABLE SPENTFUELCOOLINGPUMP B

46/PAB/SFP HX AREA SPENT FUEL COOLING PUMP A

46/PAB/SFP HX AREA SPENT FUEL POOL HEAT EXCHANGER B

46/PAB/SFP HX AREA SPENT FUEL POOL HEAT EXCHANGER A

46/PAB/SFP HX AREA HX-13B SFP HX OUTLET B

46/PAB/SFP HX AREA HX-13A SFP HX OUTLET A

46/PAB/SFP HX AREA HX-13B SFP HX INLET B

46/PAB/SFP HXAREA HX-13A SFP HX INLET A

46/PAB/SFP HX AREA

SWEL SWEL2 POINT BEACH NUCLEAR PLANT, UNIT 1 1200114-R-001, REVISION 0 RISK N

UNIT SYS EQUIP WALK E

CODE CLASS BY w

AREA 0

sw 0

14 B-42 EQUIP#

EQUIP NAME 1

2 3

4 5

TRN IPEEE LOCATION DESC Equip.

Enhanced 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 ATTACHMENT B Classes of Equipment Unit 1 and SFP Classes of Equipment SWEL1 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 14 Distribution panels and Auto Transfer 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

B-43 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.

SWEL SWEL 1-1 SWEL1-1 SWEL 1-1 SWEL 1-1 SWEL 1-1 SWEL1-1 SWEL 1-1 SWEL1-1 SWEL1-1 SWEL1-1 SWEL1-1 SWEL1-1 SWEL 1-1 SWEL1-1 SWEL 1-1 SWEL1-1 SWEL 1-1 SWEL1-1 SWEL 1-1 SWEL 1-1 SWEL 1-1 SWEL 1-1 SWEL1-1 POINT BEACH NUCLEAR PLANT, UNIT 1 12Q0114-R-001, REVISION 0 Attachment C Selected Equipment List Unit 1 and SFP RISK NEW UNIT SYS EQUIP EQUIP EQUIPMENT NAME 1

2 3

CODE CLASS NUMBER D-03 0

125V 14 125V DC DISTRIBUTION PANEL X

X X

D-105 y

0 125V 15 125V DC STATION BATTERY X

X X

D-107 0

125V 16 D-105 DC STATION BATTERY CHARGER X

X X

y 0

125V 14 D-12 125V DC DISTRIBUTION PANEL X

X X

y y

0 125V 14 D-14 125V DC DISTRIBUTION PANEL X

X X

y 0

125V 14 D-16 125V DC DISTRIBUTION PANEL X

X X

y y

0 125V 14 D-17 125V DC DISTRIBUTION PANEL X

X X

y 0

125V 14 D-1S 125V DC DISTRIBUTION PANEL X

X X

D-2S y

0 125V 14 G-03 EDG DC DISTRIBUTION PANEL X

X X

D-63 y

0 125V 14 125V DC DISTRIBUTION PANEL X

X X

y 1

4.16KV 3

1A-05 4.16 KV BUS SWITCHGEAR (SAFEGUARDS)

X X

X y

1 4SOV 2

1B-03 4SOV SAFEGUARDS LOAD CENTER X

X X

y 1

4SOV 2

1B-04 4SOV SAFEGUARDS LOAD CENTER X

X X

y 1

4SOV 4

1X-13 1B-03 STATION SERVICE TRANSFORMER X

X X

y 1

4SOV 4

1X-14 1 B-04 STATION SERVICE TRANSFORMER X

X X

B312A-P-10A RHR PUMP NORMALIALT TRANSFER y

1 4SOV 1

BS55B SWITCH X

X X

B42-2B4212B-BS11M (D-109) CHGR NRM/ALT y

2 4SOV 1

4212B XFR SWITCH CONTACTOR X

X X

1AF-1 P-29 AFP DISCHARGE 1 HX-1 B SG INLET 1

AF Sa 04000 ISOLATION MOV X

X 1AF-1 P-29 AFP DISCHARGE 1 HX-1A SG INLET 1

AF Sa 04001 ISOLATION MOV X

X 1AF-y 1

AF 7

04002 1 P-29 AFP MINI RECIRC CONTROL X

X 1AF-1 P-29 AFP SUCTION FROM SERVICE 1

AF Sa 04006 WATER X

X 1P-029 y

1 AF 5

AUX FEEDWATER TURBINE-DRIVEN PUMP X

X 1P-053 UNIT 1 AUX FEEDWATER MOTOR-DRIVEN y

y 1

AF 5

PUMP X

X B-44 4

5 LOCATION DESC SEISMIC CAT 26/PAB/INVERT RM I

X X

WEST 35/PAB/D-1 05 BATT I

X X

RM 26/PAB/INVERT RM I

X X

WEST X

X 26/CB/CSR EAST I

X X

26/CB/CSR EAST I

X X

44/CB/CR SOUTH I

X X

44/CB/CR SOUTH I

X X

44/CB/CR NORTH I

2S/DGB/G-03 SWGR I

X X

RM S/CB/AFP RM 1 P-29 I

X X

CUB 1RK-S9 X

X S/CBNSG RM I

X X

26/CB/CSR I

X X

26/CB/CSR I

X X

26/CB/CSR I

X X

26/CB/CSR I

I X

X S/PAB/COL P-11 26/PAB/C-59 AREA I

X X

2B-42 S/CB/AFP RM 1 P-29 I

X CUB S/CB/AFP RM 1 P-29 I

X CUB I

X S/PAB/1 P-53 AFP RM

SWEL SWEL1-1 SWEL 1-1 SWEL1-1 SWEL 1-1 SWEL1-1 SWEL 1-1 SWEL 1-1 SWEL1-1 SWEL 1-1 SWEL1-1 SWEL1-1 SWEL1-1 SWEL1-1 SWEL 1-1 SWEL 1-1 SWEL 1-1 SWEL1-1 SWEL 1-1 SWEL1-1 SWEL 1-1 SWEL1-1 POINT BEACH NUCLEAR PLANT, UNIT 1 12Q0114-R-001 REVISION 0 RISK NEW UNIT SYS EQUIP CODE CLASS y

1 AF 21a 0

AF 7

0 AF 8a 0

AF 7

y 0

AF 8a y

1 AF 8a y

1 AF 8b 0

AF 5

0 AF 18 y

1 AF 21a y

y 1

cc 21b y

1 cc 5

y 1

cc 21a 1

cc 19 1

cv 21b y

1 cv 8a 1

cv 7

y 1

cv 5

0 DA 21a 0

DA 21a 0

DA 21a EQUIP NUMBER 1T-212 AF-04007 AF-04009 AF-04012 AF-04023 AF-04067 AF-04073B P-038A RK-25A T-224B 1HX-012A 1P-011A 1T-012 TE-00621 HX-004 1CV-00112B 1CV-00142 1P-002A T-060B T-060C T-060E B-45 EQUIPMENT NAME 1

2 3

4 5

LOCATION DESC SEISMIC CAT 1 P-29 AFP MINI RECIRC lA 1AF-4002 I

BACKUP ACCUMULATOR X

X X

8/CB/AFP RM 8/CB/AFP RM P-38A I

P-38A SSGP MINI RECIRC CONTROL X

X X

CUB P-38A SSGP SUCTION FROM SERVICE 8/CB/AFP RM P-38A I

WATER X

X X

CUB 8/CB/AFP RM P-38A I

P-38A SSGP DISCHARGE CONTROL X

X X

CUB P-38A SSGP DISCHARGE TO 1 HX-1A 8/CB/AFP RM P-38A I

STEAM GENERA TOR X

X X

CUB 1 P-53 AFP SERVICE WATER SUPPLY I

ISOLATION X

X X

8/PAB/1 P-53 AFP RM I

1P-53 AFP RECIRCULATION ISOLATION X

X X

8/PAB/1 P-53 AFP RM 8/CB/AFP RM P-38A I

AUX FEEDWATER MOTOR-DRIVEN PUMP X

X X

CUB 8/CB/AFP RM P-38A I

P-38A SSGP INSTRUMENTATION RACK X

X X

CUB 1AF-4073B/1AF-4074B AFP RECIRC I

ISOLATION lA ACCUMULATOR X

X X

8/PAB/1 P-53 AFP RM COMPONENT COOLING WATER HEAT I

EXCHANGER X

X X

46/PAB/CC HX AREA 8/PAB/CC PUMP I

COMPONENT COOLING WATER PUMP X

X X

AREA COMPONENT COOLING SURGE TANK X

X X

46/PAB/CC HX AREA I

HX-12A/B CC HX OUTLET HEADER I

TEMPERATURE RTD X

X X

46/PAB/CC HX AREA EXCESS LETDOWN HEAT EXCHANGER X

21/U1C I

1 P-2A-C CHARGING PUMP REFUELING 8/PAB/U1 CHG PUMP I

WATER SUCTION X

X X

AREA I

CHARGING LINE FLOW CONTROL X

X X

8/PAB/PIPEWAY #1 CHARGING PUMP (Pump Only as Pressure 8/PAB/U1 CHG PUMP I

Boundary)

X X

X RM G-01 EDG STARTING AIR RECEIVER I

(RIGHT BANK)

X X

X 8/CB/G-01 RM G-01 EDG STARTING AIR RECEIVER I

{RIGHT BANK)

X X

X 8/CB/G-01 RM G-01 EDG STARTING AIR RECEIVER (LEFT I

BANK)

X X

X 8/CB/G-01 RM

SWEL SWEL 1-1 SWEL 1-1 SWEL 1-1 SWEL1-1 SWEL 1-1 SWEL 1-1 SWEL1-1 SWEL 1-1 SWEL 1-1 SWEL 1-1 SWEL 1-1 SWEL 1-1 SWEL1-1 SWEL 1-1 SWEL1-1 SWEL 1-1 SWEL 1-1 SWEL 1-1 SWEL1-1 SWEL 1-1 SWEL1-1 SWEL 1-1 SWEL 1-1 SWEL 1-1 POINT BEACH NUCLEAR PLANT, UNIT 1 12Q0114-R-001 REVISION 0 RISK NEW UNIT SYS EQUIP CODE CLASS 0

DA 21a y

0 DA 21a 0

DG 20 0

DG 20 y

0 DG 20 y

0 DG 17 y

y 0

DG 17 y

0 DG 9

y 0

DG 9

0 FO 8a y

0 FO 5

0 FO 21a 1

MMS 20 1

MS 8a 1

MS 8b 1

PACV 19 y

1 RH 5

y 1

RH 5

1 RH 7

1 Sl 8a 1

Sl 21a EQUIP NUMBER T-060F T-170A C-034 C-034A C-078 C-081 G-01 G-03 W-181A1 W-181A2 F0-03930 P-206A T-031A 1C-105 1MS-02019 1MS-02020 1MS-02090 TE-03292 1P-010A 1 P-010B 1RH-00624 1RH-00625 SI-00852A T-034A B-46 EQUIPMENT NAME 1

2 3

4 5

LOCATION DESC SEISMIC CAT G-01 EDG STARTING AIR RECEIVER (LEFT I

BANK)

X X

X 8/CB/G-01 RM G-03 EDG STARTING AIR RECEIVER X

X X

28/DGB/G-03 RM I

8/CB/G-01 RM W I

G-01 EDG ALARM AND ELECTRICAL PANEL X

X X

WALL 8/CB/G-01 RM W I

G-01 EDG LOCAL TRANSFER PANEL X

X X

WALL G-01 EDG DC POWER TRANSFER 8/CB/G-01 RM W I

CONTROL PANEL X

X X

WALL 28/DGB/G-03 SWGR I

G-03 EDG CONTROL PANEL X

X X

RM EMERGENCY DIESEL GENERATOR X

X X

8/CB/G-01 RM I

EMERGENCY DIESEL GENERATOR X

X X

28/DGB/G-03 RM I

50/DGB/G-03 RADTR I

G-03 EDG HX-265A RADIATOR FAN X

X X

RM 50/DGB/G-03 RADTR I

G-03 EDG HX-265A RADIATOR FAN X

X X

RM T-31A G-01 EDG DAY TANK INLET SECOND I

OFF ISOLATION X

X X

8/CB/G-01 RM G-01 EDG FUEL OIL TRANSFER PUMP 28/DGB/G-01/2 FOTP I

X X

X RM G-01 DIESEL GENERATOR DAY TANK X

X X

8/CB/G-01 RM I

SECONDARY SYSTEM POWER SUPPLIES I

PANEL X

X X

44/CB/CR HX-1 B SG HEADER P-29 AFP STEAM I

SUPPLY MOV X

X X

X 46/PAB/BAST AREA S HX-1A SG HEADER P-29 AFP STEAM I

SUPPLY MOV X

X X

X 46/PAB/BAST AREAS I

P-29 AFP BEARING COOLING INLET X

X X

8/CB/AFP RM EL 66' U1C TEMPERATURE ELEMENT X

66/U1C/NE QTR I

RESIDUAL HEAT REMOVAL PUMP X

X X

-19/PAB I

RESIDUAL HEAT REMOVAL PUMP X

X X

-19/PAB I

-5/PAB/EAST WALL I

HX-11A RHR HX OUTLET CONTROL X

X X

OVHD

-5/PAB/EAST WALL I

HX-11 B RHR HX OUTLET CONTROL X

X X

OVHD LOW HEAD Sl CORE DELUGE ISOLATION X

46/U1C/SEAL TABLE I

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

1 P-015A SAFETY INJECTION PUMP 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

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

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

8/PAB/SI PUMP AREA 1SI-I SWEL 1-1 y

1 Sl 8a 00866A COLD LEG INJECTION LINE ISOLATION X

X X

8/PAB/PIPEWAY #1 1SI-CORE DELUGE INJECTION LINE I

SWEL1-1 y

1 Sl 8a 00866B ISOLATION X

X X

8/PAB/PIPEWAY#1 1SI-I SWEL1-1 y

1 Sl 8a 00896A P-15A Sl PUMP SUCTION 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

26/PAB/NORTH.

I W-085 PAB BATTERY AND INVERTER ROOM I

SWEL 1-1 0

VNBI 10 VENT FAN X

X X

35/PAB/D-106 ROOF W-001B1 CONTAINMENT ACCIDENT I

SWEL 1-1 1

VNCC 9

RECIRCULATION FAN 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

WALL W-183B G-03 EDG RM SMALL CAPACITY EXHAUST I

SWEL1-1 y

y 0

VNDG 9

FAN 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

50/DGB/G-03 FAN RM SWEL 1-1 1

y 16 1 DY-01 RED 125V DC/120V AC INVERTER 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

WEST 1Y-203 WHITE 120V INVERTER DISTRIBUTION 26/CB/CSR WEST I

SWEL 1-1 1

y 14 PANEL 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

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

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

WEST DY-OB BLUE 125V DC/120V AC ALTERNATE I

SWEL 1-1 0

y 16 INVERTER 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

WEST 1SAF-1 P-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-1 P-29 AFP DISCH 1 HX-1A SG INLET I SOL 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 1 P-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

8/CBNSG RM I

PB 0

125V 15 D-05 125V DC STATION BATTERY X

X X

8/CB/D-05 BATT RM I

PB y

0 125V 16 D-09 SWING STATION BATTERY CHARGER X

X X

8/CBNSG RM I

PB y

0 125V 14 D-19 125V DC DISTRIBUTION PANEL X

X X

44/CB/CR NORTH I

PB y

y 0

125V 14 D-21 125V DC DISTRIBUTION PANEL 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

WEST 1B-32 480V MOTOR CONTROL CENTER PAB 8/PAB/U1 CHG PUMP I

PB 1

480V 1

SAFEGUARDS X

X X

AREA 1B-39 480V MOTOR CONTROL CENTER TRAIN A I

PB 1

480V 1

BATTERY CHARGER SUPPLY 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

8/CBNSG RM B311C-P-32B SERVICE WATER PUMP I

PB 1

480V 1

B854D NORMAL!AL T TRANSFER SW X

X 8/CB/G-01 RM B334B-P-32F SERVICE WATER PUMP I

PB 2

480V 1

B854D NORMAL/AL T 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

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

AREA 1B-32 B42-391 D-07 STATION BATTERY CHARGER TRAIN I

PB 1

480V 1

ACONTACTOR 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

8/CBNSG RM 1 B-49 B42-494 D-108 STATION BATTERY CHARGER TRAIN 26/PAB/INVERT RM I

PB 1

480V 1

B CONTACTOR X

X X

EAST 1RK-35 1P-29 AUX FEEDWATER PUMP 8/CB/AFP RM 1 P-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 GENERA TOR 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 1 HX-11A RHR HX SHELL SIDE INLET X

X X

8/PAB/PIPEWAY #2 1CC-I PB 1

cc 8a 00738B 1 HX-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 1 P-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

-5/PAB/RHR HX CUB 1HX-011 B RESIDUAL HEAT REMOVAL HEAT I

PB 1

RH 21b EXCHANGER X

X X

-5/PAB/RHR HX CUB PB 1

Sl 5

1P-015B SAFETY INJECTION PUMP 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

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

PIPEWAY 1SI-P-10B RHR PUMP SUCTION FROM

-5/PAB/RHR I

PB 1

Sl Sa OOS51B CONTAINMENT SUMP B 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

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

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

S/PAB/Sl PUMP AREA 1SI-I PB 1

Sl Sa OOS96B P-15B Sl PUMP SUCTION 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

U1F 2SI-T-13 RWST OUTLET TO P-10A RHR PUMP I

PB 2

Sl Sa OOS56A SUCTION HEADER 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

S/PAB/PIPEWAY #3 PB 1

y 16 1DY-02 BLUE 125V DC/120V AC INVERTER 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

EAST PB 1

y 14 1Y-01 RED 120V VITAL INSTRUMENT PANEL X

X X

44/CB/CR WEST I

PB 1

y 14 1Y-02 BLUE 120V VITAL INSTRUMENT PANEL X

X X

44/CB/CR WEST I

PB 1

y 14 1Y-104 YELLOW 120V VITAL INSTRUMENT PANEL 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

WALL PB 0

y 14 S3/DY-OC DY-OC WHITE INVERTER STATIC 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

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 1 HX-1 B 8/CB/AFP RM P-38B I

PB 0

AF 8a STEAM GENERA TOR 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

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

WALL

Point Beach Nuclear Plant, Unit 1 1200114-R-001, Revision 0 Seismic Walkdown Checklist (SWC)

Sheet 1 of 2 Status: [YJ N U 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%

of SWEL Items requiring such verification)?

2.

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

3.

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

4.

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

5.

Is the anchorage configuration consistent with plant documentation? {Note:

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 potentially adverse seismic conditions?

Interaction Effects

7.

Are soft targets free from Impact by nearby equipment or structures?

Yes Yes Yes Yes Yes Yes Yes C-49

Point Beach Nuclear Plant, Unit 1 1200114-R-001, Revision 0 Seismic Walkdown Checklist (SWC)

Sheet 2 of2 status: [Y] N u 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?

Tube In contact with CC pipe and judged to be acceptable.

8.

Are overhead equipment, distribution systems, ceiling Illes and lighting, and 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'/

Attached conduit Is flexible.

10.

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

other Adverse Conditions

11.

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

Comments Seismic Walkdown Team: M. Nielsen & D. Carter-9/18/2012 Yes Yes Yes Yes Yes Evaluated by:

Detailed signed records of the checklists are available at

_.::clh:.::e..::s::.:.ite::..:*~---------------- Date: --------

C-56

Point Beach Nuclear Plant, Unit 1 1200114-R-001, Revision 0 Seismic Walkdown Checklist (SWC)

Sheet 1 of2 Status: [Y] N U 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%

of SWEL items requiring such verification)?

2.

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

3.

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

4.

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

5.

Is the anchorage configuration consistent with plant documentation? (Note:

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 potentially adverse seismic conditions?

Yes Yes Yes Yes Yes Yes C-179

Point Beach Nuclear Plant, Unit 1 1200114-R-001, Revision 0 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 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 that could cause a fire In the area?

No sources.

Sheet 2 of2

Status: [YJ N U Yes Yes

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 Evaluated by:

Detailed signed records of the checldlsts are available at the site.

Date:

Point Beach Nuclear Plant, Unit 1 1200114-R-001, Revision 0 Area Walk-By Checklist (AWC)

Location (Bldg, Elev, Room/Area):

Area Walk-by 24: PAB EL. 46' SFP HX AREA Instructions for Completing Checklist Sheet 1 of 2 Status: W N U

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 adverse seismic conditions (if visible without necessarily opening cabinets)?

2.

Does anchorage of equipment in the area appear to be free of significant 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 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 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 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 that could cause a fire in the area?

7.

Does it appear that the area is free of potentially adverse seismic interactions 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.

Yes Yes Yes Yes Yes Yes Yes D-40

E Point Beach Nuclear Plant, Unit 1 1200114-R-001, Revision 0 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 Location Reason for Scheduled Component ID Description Inaccessibility Completion 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 1 B312A-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 C-032 8/CB/G-01 Rm G-01 EDG Exhaust Equipment energized 1

51 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

(e) Knowledge of plant operations, documentation (f) Plant Operations member Point Beach Nuclear Plant, Unit 1 1200114-R-001, Revision 0 (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 1 0 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)

Action Taken to Q)

I E N

"0

>o Equipment Potentially Adverse Seismic Condition co s:::...

iU Address the Current Status 0

0 s:::

10 C) z-Condition Q) s:::

co c

0 s:::

(.)

J NextEra Engineering Closed.

evaluated the corrosion Will be tracked X

and determined minor through P-0320 Corrosion observed on the base plate.

and would not affect structures the design function of monitoring the pump. CR initiated.

program.

NextEra Engineering Closed.

evaluated the corrosion Will be tracked X

and determined minor through P-032E Corrosion observed on the base plate.

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 X

and determined minor through Corrosion observed on the baseplate.

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 Being tracked in attached flexible conduit fitting. The solenoid and the X

air to the valve results 2MS-02090 fitting are relatively heavy compared to the capacity of in the valve going to a the CAP.

the tubing supporting them.

safe position. Initiated CR.

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

'0 Cl

'0 s::::

Q)

I E N

Action Taken to Equipment

'0

~

Potentially Adverse Seismic Condition n:s s::::

n:s Address the Current Status ID 0

0 Cl z-s::::

Condition Q) s::::

n:s c

0 s::::

u

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

have greater capacity The Drawing C-240 shows the anchors as 1" Wejit type than Wejit expansion 2P-002C expansion anchor. The SQUG SEWS prepared for the X

anchors. Based on Being tracked in 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 2B-03 Rear bottom panel is missing a mounting bolt.

X seismic capability of initiated to install the equipment. The bolt is one of many that the bolt.

attach the rear panel to the frame. Initiated CR.

NextEra Engineering D26 Two crank handles in vicinity are loosely hung from X

determined that the 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 X

SQ-000077. Since the Being tracked in 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 c:

(I)

. *e N

Action Taken to Area Potentially Adverse Seismic Condition

.2' ca c:...

0 0

ca Address the Current Status C'l z-c:

(I) c:

ca Condition c

0 c:

(J

~

In the judgment of the walkdown team, the AWB9 An S-Hook supporting a light fixture was observed to light fixture would not Work request be opened.

X fall and interact with any seismically initiated to repair.

qualified equipment.

Initiated CR.

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

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

of the room and it was Being tracked in line and a sprinkler head are relatively close to the determined that the the CAP.

room fans. The Seismic Walkdown Team was unable piping is within code to conclude that the fire protection pipe and sprinkler allowable stresses and head would not move and interaction with the fans. In will not leak. This addition, the team could not conclude that the fire preliminary evaluation protection line would not deflect in a manner that was considered a 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*b~ lnsQections "C

O'l "C

c:

Q)

. *e N

Action Taken to "C

Area Potentially Adverse Seismic Condition

!tl c:...

iO Address the Current Status 0

0 O'l z-c:

Condition Q) c:

!tl c

0 c:

0

J The walkdown team judged that the tube was not an interaction hazard and would A 3/8" tube for valve 1 SI-881A has a long span (-1 0')

deflect but not break in Work request AWB 19 X

a seismic event. A and is very flexible.

preliminary calculation initiated to repair.

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

Initiated CR.

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

seismic concern.

Work request hose could dislodge from the clamps and interact with There were no soft initiated to repair.

items below.

targets immediately below. Initiated CR.

A conduit for valve 2SI-825C is attached to the flange The conduit is attached to nearby AWB 19 of a vertical hanger with clamps oriented such that X

cable tray JG08 and Work request they are resisting dead load with friction. Clamps will not fall. Initiated initiated to repair.

should be re-orientated.

CR.

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

horizontal run at the Work Request resisting dead load with friction. The clamps should top of the riser. Based initiated to repair.

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

C'l "C

Cl)

I "E N

Action Taken to "C

Area Potentially Adverse Seismic Condition

~

iii Address the Current Status 0

0 C'l z-Condition Cl) co c

0 CJ

J 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 magnets be backed up with lanyards to assure they X

to be adequately Closed will not fall.

supported. Initiated 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.

AWB27 There is a missing anchor bolt on the pipe support X

Previously identified Work Request west of P-31 A and evaluated in CR.

initiated to repair.

AWB27 There is a missing anchor bolt on the base plate north X

Previously identified Work Request 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 There is a missing anchor bolt on the base plate a seismic concern due Work Request AWB28 X

to ruggedness of the northwest of P-35A.

overall assembly. CR initiated to repair.

initiated.

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

C'l "0

c Q)

Q)

I'§ N

Action Taken to "0

~

Area Potentially Adverse Seismic Condition

!1:1 c...

!1:1 Address the Current Status 0

0 C'l z-c Condition Q) c

!1:1 c

0 c

()

J AW828 NextEra Engineering evaluated the condition and determined that the fan is not required to be seismically The bottom anchor bolt for W-0028 is not fully qualified. The Work Request engaged.

X remaining anchorage 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 There is loose grout at the northeast corner below design function of the Work Request AW828 X

support since it is not SW-13.

in the bearing area of initiated to repair.

the base plate. CR initiated.

Due to the light load on the support and the AW829 A conduit support on the southwest corner of K-38 has X

remaining anchorage Work Request 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 "C

Cl "C

s:::::

Q)

N Action Taken to "C

I E Area Potentially Adverse Seismic Condition cu s:::::

iii Address the Current Status 0

0 Cl z-s:::::

Condition Q) s:::::

cu 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 AWB29 The west nut on T-033A does not have full thread X

of the nut. The 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 The platform just east of the Main Steam Safety Valve prevent the platform from overturning AWB39 is not anchored to the slab. In some cases there are X

during a seismic Work Request anchor with no nuts, in other cases there are no event. Other initiated to repair.

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.

Outlier No.

1 2

POINT BEACH NUCLEAR PLANT, UNIT 2 1200114-R-002, REVISION 0 Table 3 IPEEE and A-46 Outlier Resolution - Unit 2 Program Equip System Equip Noun Name Status at Time of SRT Outlier Description Interim Resolution Documented Class ID Walkdown in 1993 in the USI A-46 Seismic Evaluation Report to NRC I

0 cv 2F-Rep Seal 0 - Anchor nuts are not The.nuts for the This is not an operability 39A Water seated. Not an caste in place concern because the attached Injection operability concern.

anchors are not fully pipe has sufficient flexibility to Filter EWR, 6/20/96 - EWR seated.

accommodate the displacement 96-040 assigned of the filter. The nuts will be seated or washers installed to close up the gaps. 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 1

480V 2B-42 480v Motor 0 - The connecting bolt The connecting bolt The MCC is considered Control that connects the that connects the seismically operable because Center Pab double P1 000 to the double P1 000 to the the other top supports are Safeguards strut that is anchored to strut that is sufficient to resist overturning.

the wall has either anchored to the wall The bolts will be check tight and loose or missing has either loose or any missing hardware replaced.

fastening nuts. T.

missing fastening 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.

B-12 Status I Final Required Date Resolution Close Out Completed wo 9815435 SQ-001530 11/6/98 completed 11/6/98.

completed Removed existing nuts, added washers and torqued down new nuts on all 4 anchors.

wo 9606365, SQ-001250 11/13/96 completed 11/13/96 resolves the checked the outlier.

connecting bolts tight and replaced any missing hardware.

Outlier No.

4 6

7 9

POINT BEACH NUCLEAR PLANT, UNIT 2 1200114-R-002, REVISION 0 Program Equip System Equip Noun Name Class ID A, I 2

480V 28-03 480v Safeguards Load Center A, I 2

480V 28-04 480v Safeguards Load Center A, I 3

RP 2C-41 Rod Ctl Mg/Reactor Trip 8kr Switchgear Ctl Panel A, I 4

4.16KV 2X-13 8-03 Station Service Transformer Status at Time of SRT Outlier Description Walkdown in 1993 0- ANCHORAGE The anchorage weld INSUFFICIENT, Weld spacing is to large, spacing is to large.

every 3rd cabinet in Every 3rd cabinet in some cases. The some cases. TROLLEY trolley hoist that HOIST needs to be rides along the top clamped in place. T.

of the switchgear Dykstra to submit poses an interaction separate EWRs for hazard.

weld and trolley hoist.

0 - ANCHORAGE The anchorage weld INSUFFICI_ENT, Weld spacing is to large, spacing is to large.

every 3rd cabinet in Every 3rd cabinet in some cases. The some cases. TROLLEY trolley hoist that HOIST needs to be rides along the top clamped in place, Cub of the switchgear 28-00-328-28-04 has poses an interaction loose material, should hazard.

remove it. T. Dykstra to submit separate EWRs for weld and trolley hoist.

0 - NOT ANCHORED.

The cabinet is not MR in process. MR anchored.94-045. Candice Curtis 0- ANCHORED WITH The transformer FRICTION CLIPS. MR anchorage uses in process MR 94-013 friction clips which is not covered by the GIP.

B-13 Interim Resolution Documented Status I Final Required Date in the USI A-46 Seismic Resolution Close Out Completed Evaluation Report to NRC There is sufficient anchorage MR 95-006 installed SQ-001588, 7/6/99 capacity in the existing welds to new anchorage (WO SQ-001532 carry the seismic anchorage 9705903). EWR completed loads. However, the switchgear 96-042 evaluated was declared an outlier because breaker handling it is not good engineering trolley. EWR closed.

practice to transfer the seismic MR 98-095 installed loading through the switchgear trolley stops.

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

There is sufficient anchorage MR 95-006 installed SQ-001589, 7/6/99 capacity in the existing welds to new anchorage.

SQ-001536 carry the seismic anchorage EWR 96-042 completed loads. However, the switchgear assigned to was declared an outlier because evaluated breaker it is not good engineering handling trolley.

practice to transfer the seismic EWR closed. MR loading through the switchgear 98-095 installed structure. The switchgear is trolley stops.

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

The relay review showed that MR 94-045 installed SQ-001537 8/23/96 there were no essential Reactor new anchorage.

completed Protection System relays Accepted 11/7/95.

located in the cabinet. Any 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.

The friction clips provide MR 94-013 installed SQ-001800 8/1/97 adequate capacity to withstand new anchorage -

completed the P8NP SSE, because the accepted 11/3/95.

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

Outlier No.

11 17 19 20 POINT BEACH NUCLEAR PLANT, UNIT 2 1200114-R-002, REVISION 0 Program Equip System Equip Noun Name Class ID A,l 4

4.16KV 2X-14 B-04 Station Service Transformer A, I 5

Sl 2P-Containment 14A Spray Pump A, I 5

Sl 2P-Containment 148 Spray Pump A, I 6 sw P-32A Service Water Pump Status at Time of SRT Outlier Description Walkdown in 1993 0- ANCHORED WITH The transformer FRICTION CLIPS. MR anchorage uses in process. MR 94-013 friction clips which is not covered by the GIP.

0 - Failed Anchorage The anchor J-bolts Calc PIPE LOAD ON have an embedment SUCTION NOZZLES

< 16D as required by the GIP.

0- Failed Anchorage The anchor J-bolts Calc PIPE LOAD ON have an embedment SUCTION NOZZLES

< 16D as required by the GIP.

0 - Anchorage/capacity The pump extending check on bolts & studs, casing is 34' long >

restraint of overhead the 20' allowable.

trolley, The overhead crane poses an interaction hazard.

B-14 Interim Resolution Documented Status I Final Required Date in the USI A-46 Seismic Resolution Close Out Completed Evaluation Report to NRC The friction clips provide MR 94-013 installed SQ-001801 8/1/97 adequate capacity to withstand new anchorage -

completed the PBNP SSE, because the accepted 11/3/95.

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

A calculation per ACI 318-63 S&A Calc 91C2696-SQ-1807 11/12/02 and ACI 349-80 Appendix B C-019 uses the completed.

shows that the pump anchorage guidelines from ACI has sufficient capacity.

318-63 and ACI 349-80 Appendix B to show that the pump anchorage has sufficient capacity.

A calculation per ACI 318-63 S&A Calc 91 C2696-SQ-1828 11/12/02 and ACI 349-80 Appendix B C-019 uses the completed.

shows that the pump anchorage guidelines from ACI has sufficient capacity.

318-63 and ACI 349-80 Appendix B to show that the pump anchorage has sufficient capacity.

The pump is considered S&A Calc 91 C2696-SQ-1808 6/15/99 operable based on original C-012 shows pump completed.

design calculations. S&A shaft stresses within calculation 91C2696-C-012 limits. EWR 96-041 shows that the pump shaft evaluated the 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.

Outlier No.

21 22 23 POINT BEACH NUCLEAR PLANT, UNIT 2 1200114-R-002, REVISION 0 Program Equip System Equip Noun Name Class ID A, I 6

sw P-328 Service Water Pump A, I 6

sw P-32C Service Water Pump A, I 6

sw P-32D Service Water Pump Status at Time of SRT Outlier Description Walkdown in 1993 0 -Anchorage/capacity The pump extending check on bolts & studs, casing is 34' long >

restraint of overhead the 20' allowable.

trolley, The overhead crane poses an interaction hazard.

0 - Anchorage/capacity The pump extending check on bolts & studs, casing is 34' long >

restraint of overhead the 20' allowable.

trolley, The overhead crane poses an interaction hazard.

0 - Anchorage/capacity The pump extending check on bolts & studs, casing is 34' long >

restraint of overhead the 20' allowable.

trolley, The overhead crane poses an interaction hazard.

B-15 Interim Resolution Documented Status I Final Required Date in the USI A-46 Seismic Resolution Close Out Completed Evaluation Report to NRC The pump is considered S&A Calc 91C2696-SQ-1809 6/15/99 operable based on original C-012 shows pump completed.

design calculations. S&A shaft stresses within calculation 91 C2696-C-012 limits. EWR 96-041 shows that the pump shaft evaluated the 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.

The pump is considered S&A Calc 91 C2696-SQ-1810 6/15/99 operable based on original C-012 shows pump completed.

design calculations. S&A shaft stresses within calculation 91 C2696-C-O 12 limits. EWR 96-041 shows that the pump shaft evaluated the 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.

The pump is considered S&A Calc 91C2696-SQ-1811 6/15/99 operable based on original C-012 shows pump completed.

design calculations. S&A shaft stresses within calculation 91C2696-C-012 limits. EWR 96-041 shows that the pump shaft evaluated the 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.

Outlier No.

24 25 27 POINT BEACH NUCLEAR PLANT, UNIT 2 1200114-R-002, REVISION 0 Program Equip System Equip Noun Name Class ID A, I 6

sw P-32E Service Water Pump A, I 6

sw P-32F Service Water Pump A,I,V 7

cs 2CS-Hx-1a Sg 466 Feedwater Regulator Control Status at Time of SRT Outlier Description Walkdown in 1993 0 - Anchorage/capacity The pump extending check on bolts & studs, casing is 34' long >

restraint of overhead the 20' allowable.

trolley, The overhead crane poses an interaction hazard.

0 - Anchorage/capacity The pump extending check on bolts & studs, casing is 34' long >

restraint of overhead the 20' allowable.

trolley, The overhead crane poses an interaction hazard.

0- Block Wall The valves are interaction adjacent to a large unanalyzed block wall. The block wall poses an interaction hazard for the valve and it sub-components.

B-16 Interim Resolution Documented Status I Final Required Date in the USI A-46 Seismic Resolution Close Out Completed Evaluation Report to NRC The pump is considered S&A Calc 91 C2696-SQ-1812 6/15/99 operable based on original C-012 shows pump completed.

design calculations. S&A shaft stresses within calculation 91 C2696-C-012 limits. EWR 96-041 shows that the pump shaft evaluated the 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.

The pump is considered S&A Calc 91C2696-SQ-1813 6/15/99 operable based on original C-012 shows pump completed.

design calculations. S&A shaft stresses within calculation 91 C2696-C-012 limits. EWR 96-041 shows that the pump shaft evaluated the 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.

The function of the valve is to EWR - Functional Nowalkdown 8/30/00 close to isolate feed to the S/Gs.

Evaluation. 6/20/96

required, The valve is not required to shut

- EWR 96-043 SQ-001815 during the 30 second period of assigned to update strong motion. However, it is document complete.

desired to have it shut during evaluation.

the 72 hour8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months recovery period. As Evaluation 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.

Outlier No.

29 31 33 POINT BEACH NUCLEAR PLANT, UNIT 2 1200114-R-002, REVISION 0 Program Equip System Equip Noun Name Class ID A,I,V 7 cs 2CS-Hx-1b Sg 476 Feedwater Regulator Control A,I,V 7 cs 2CS-Hx-1a Sg 480 Regulator Control Bypass A,I,V 7 cs 2CS-Hx-1b Sg 481 Regulator Control Bypass Status at Time of SRT Outlier Description Walkdown in 1993 0- Block Wall The valves are interaction adjacent to a large unanalyzed block wall. The block wall poses an interaction hazard for the valve and it sub-components.

0- Block Wall The valves are interaction adjacent to a large unanalyzed block wall. The block wall poses an interaction hazard for the valve and it sub-components.

B-17 Interim Resolution Documented Status I Final Required Date in the USI A-46 Seismic Resolution Close Out Completed Evaluation Report to NRC The function of the valve is to EWR-Functional Nowalkdown 8/30/00 close to isolate feed to the S/Gs.

Evaluation. 6/20/96

required, The valve is not required to shut

- EWR 96-043 SQ-001817 during the 30 second period of assigned to update strong motion. However, it is document complete.

desired to have it shut during evaluation.

the 72 hour8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months recovery period. As Evaluation 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.

The valve is normally close and EWR - Functional Nowalkdown 8/30/00 must remain closed to isolate Evaluation. 6/20/96

required, feed to the S/Gs. Therefore,

- EWR 96-043 SQ-001819 during the 30 second period of assigned to update strong motion, the valve is not document complete.

required to change state. It is evaluation.

not likely, that the block wall Evaluation 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.

The valve is normally close and EWR - Functional Nowalkdown 8/30/00 must remain closed to isolate Evaluation. 6/20/96

required, feed to the S/Gs. Therefore,

- EWR 96-043 SQ-001821 during the 30 second period of assigned to update strong motion, the valve is not document complete.

required to change state. It is evaluation.

not likely, that the block wall Evaluation 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.

Outlier No.

35 37 40 42 44 46 POINT BEACH NUCLEAR PLANT, UNIT 2 1200114-R-002, REVISION 0 Program Equip System Equip Noun Name Class ID I,V,RG 7

RM 2RM-Re-211/Re-3200A 212 Monitor Return I,V,RG 7

RM 2RM-Re-211/Re-3200B 212 Monitor Supply A,I,V 7

Sl 2SI-T-34a Si 839A Accum Outlet To Si Test Line Isolation A,I,V 7

Sl 2SI-SiACold 839B Leg To Si Test Line Isolation A,I,V 7

Sl 2SI-T-34b Si 839C Accum Outlet To Si Test Line Isolation A,I,V 7

Sl 2SI-SiB Cold 839D Leg To Si Test Line Isolation Status at Time of SRT Walkdown in 1993 0 - Based on visual inspection, the building the RMs are located in is not anchored. Need to check any drawings.

0 - Based on visual inspection, the building the RMs are located in is not anchored. Need to check any drawings.

0 - UNSUPPORTED OPERATOR-MODIFIED U2R19-Supported operators MWR 935398 0 - UNSUPPORTED OPERATOR-MODIFIED U2R19-Supported operators MWR935398 0 - UNSUPPORTED OPERATOR-MODIFIED U2R19-Supported operators MWR935398 0- UNSUPPORTED OPERATOR-MODIFIED U2R19-Supported operators MWR 935398 B-18 Outlier Description Interim Resolution Documented Status I Final Required Date in the USI A-46 Seismic Resolution Close Out Completed Evaluation Report to NRC The valve is located The item has been walked down 12/28/98 - EWR 96-SQ-001986 3/10/98 in a climate control for the IPEEE only. Subsequent 044 complete. ID'd resolves this hut that has no to the walkdown, it has been the anchorage. S&L outlier visible base screened out using the Seismic completed calc.

anchorage.

PSA screening criteria.

Calculation resolves outlier.

The valve is located The item has been walked down 12/28/98 - EWR 96-SQ-001988 3/10/98 in a climate control for the IPEEE only. Subsequent 044 complete. ID'd resolves this hut that has no to the walkdown, it has been the anchorage. S&L outlier visible base screened out using the Seismic completed calc.

anchorage.

PSA screening criteria.

Calculation resolves outlier.

TheAOVwas The valve was determined to be Fixed, MWR 935398 SQ-001631 10/22/93 mounted on a 3/4" seismically inoperable. The

-completed resolves line with the valve operator was supported that 10/22/93

outlier, operator same refueling out under MWR completed unsupported 935398 TheAOVwas The valve was determined to be Fixed, MWR 935398 SQ-001632 10/22/93 mounted on a 3/4" seismically inoperable. The

-completed resolves line with the valve operator was supported that 10/22/93 outlier.

operator same refueling out under MWR Completed unsupported 935398 TheAOVwas The valve was determined to be Fixed, MWR 935398 SQ-001633 10/22/93 mounted on a 3/4" seismically inoperable. The

-completed resolves line with the valve operator was supported that 10/22/93 outlier.

operator same refueling out under MWR completed unsupported 935398 TheAOVwas The valve was determined to be Fixed, MWR 935398 SQ-001634 10/22/93 mounted on a 3/4" seismically inoperable. The

-completed resolves line with the valve operator was supported that 10/22/93 outlier.

operator same refueling out under MWR Completed unsupported 935398

Outlier No.

50 51 53 55 POINT BEACH NUCLEAR PLANT, UNIT 2 1200114-R-002, REVISION 0 Program Equip System Equip Noun Name Class ID I,V,RG 7

Sl 281-T-34a/B Si 846 Accum Nitrogen Inlet Control I,V 7

Sl 2SI-T-34a/B Si 957 Accum Nitrogen Header Vent Control I,RG 7

WG 2WG-T-16 Rcdt 1786 Vent I,RG 7

WG 2WG-T-16 Rcdt 1787 Vent Status at Time of SRT Walkdown in 1993 0 - 36" offset on 1.25" line. Because of pipe support configuration, potential for pipe overstress. Valve is considered operable -

attached conduit will stabflize valve.

0- Yoke U-bolt missing, MWR submitted 7/25/94-U-bolt to be installed U2R20 10/18/94 - U-Bolt installed 10/7/94 W0935298 0- Even though 15" offset < 45" GIP allowable for a 1" there is a potential for pipe overstress in line 1 "-

WD-151R-1 because of how the 1" line is supported. Check offset, 1WG-1786 offset measured at 24" EWR 0 - Even though 15" offset< 45" GIP allowable for a 1" there is a potential for pipe overstress in line 1 "-

WD-151R-1 because of how the 1" line is supported. Check offset, 1WG-1787 offset measured at 24" EWR B-19 Outlier Description Interim Resolution Documented Status I Final Required Date in the USI A-46 Seismic Resolution Close Out Completed Evaluation Report to NRC The AOV offset of The item has been walked down MR 94-066 was SQ-001829 2/6/96 36" < 45" allowable for the IPEEE only. Subsequent installed during completed offset for a 1" line.

to the walkdown, it has been U2R21. The pipe However, because screened out using the Seismic was moved to of the pipe support PSA screening criteria.

eliminated rubbing configuration, there Modification request MR 94-on adjacent pipe.

is a potential for pipe 066*B is initiated to upgrade the New supports were 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 The valve operator The valve was considered Fixed, WO 935298 SQ-001635 10/10/94 yoke U-bolt was seismically operable based on a installed a new U-resolves missing.

calculation that showed the pipe bolt. Completed outlier.

stress was< 2Sy. The valve 10/10/94 Completed operator U-bolt was installed during the next refueling outage under Word Order 935298 The AOV offset of The item has been walked down EWR 96-050 SQ-001777 1/14/00 15" < 45" allowable for the IPEEE only. Subsequent assigned - valves resolves this offset for a 1" line.

to the walkdown, it has been have been as-built, outlier However, because screened out using the Seismic 9/3/98. Need to of the pipe support PSA screening criteria.

draft sketch for valve configuration, there supports. 4/1/99-is a potential for pipe MR 96-035will overstress.

install operator support. WO 9904476.

Installation complete.

The AOV offset of The item has been walked down EWR 96-050 SQ-001778 1/14/00 15" < 45" allowable for the I PEEE only. Subsequent assigned - valves resolves this offset for a 1" line.

to the walkdown, it has been have been as-built, outlier However, because screened out using the Seismic 9/3/98. Need to of the pipe support PSA screening criteria.

draft sketch for valve configuration, there supports. 4/1/99-is a potential for pipe MR 96-035 will overstress.

install operator support. WO 9904476.

Installation complete.

Outlier No.

57 59 61 63 POINT BEACH NUCLEAR PLANT, UNIT 2 1200114-R-002, REVISION 0 Program Equip System Equip Noun Name Class ID A, I 8

Sl 2SI-P-15b Si 878A Pump R-1 Reactor Vessel Injection A, I 8

Sl 2SI-P-15a Si 8788 Pump Loop B Injection A, I 8

Sl 2SI-P-15b Si 878C Pump R-1 Reactor Vessel Injection A, I 8

Sl 2SI-P-15a Si 878D Pump Loop A Injection Status at Time of SRT Walkdown in 1993 0 - Valve body not shimmed. MSA evaluated. Considered acceptable. Accession

- WE-200084 0 - Valve body not shimmed. MSA evaluated. Considered acceptable. Accession

- WE-200084 0 - Valve body not shimmed. MSA evaluated. Considered acceptable. Accession

- WE-200084 0- Valve body not shimmed. MSA evaluated. Considered acceptable. Accession

- WE-200084 B-20 Outlier Description Interim Resolution Documented Status I Final Required Date in the USI A-46 Seismic Resolution Close Out Completed Evaluation Report to NRC The valve was The piping analysis, Accession EWR 96-045 SQ-001636 3/27/97 supported by the

- WE-200084, shows that the assigned to resolves valve operator but valve will not be overstressed.

document resolution.

outlier.

not the valve body.

NRC RAI asked for In addition, the gap piping analysis.

between the valve Resolved.

body and the gravity support stanchion is not properly shimmed The valve was The piping analysis, Accession EWR 96-045 SQ-001637 3/27/97 supported by the

- WE-200084, shows that the assigned to resolves valve operator but valve will not be overstressed.

document resolution.

outlier.

not the valve body.

NRC RAI asked for In addition, the gap piping analysis.

between the valve Resolved.

body and the gravity support stanchion is not properly shimmed The valve was The piping analysis, Accession EWR 96-045 SQ-001638 3/27/97 supported by the

- WE-200084, shows that the assigned to resolves valve operator but valve will not be overstressed.

document resolution.

outlier.

not the valve body.

NRC RAI asked for In addition, the gap piping analysis.

between the valve Resolved.

body and the gravity support stanchion is not properly shimmed The valve was The piping analysis, Accession EWR 96-045 SQ-001639 3/27/97 supported by the

- WE-200084, shows that the assigned to resolves valve operator but valve will not be overstressed.

document resolution.

outlier.

not the valve body.

NRC RAI asked for In addition, the gap piping analysis.

between the valve Resolved.

body and the gravity support stanchion is not properly shimmed

Outlier No.

64 65 66 POINT BEACH NUCLEAR PLANT, UNIT 2 1200114-R-002, REVISION 0 Program Equip System Equip Noun Name Class ID A, I 10 VNAFW HX-66 Auxiliary Feed Pump Area Cooler A, I 10 VNAFW HX-Auxiliary 66A Feed Pump Area Cooler A, I 10 sw HX-98 Residual Heat Removal Pump Area Cooling Coil Status at Time of SRT Outlier Description Walkdown in 1993 0 - Rubber isolators The air handling unit fail. They do not have is mounted on sufficient shear and rubber vibration tension capacity to isolators. The transfer the anchor anchorage loads to the concrete calculation expansion anchors.

concluded that the rubber isolators had insufficient capacity to transfer the anchorage loads to the concrete expansion anchors.

0 - The Spring isolator The air handling unit base plate yields.

is mounted on spring vibration isolators.

The anchorage calculation determined that the spring isolator base plate will yield.

0 - Mounted on The air handling unit Neoprene pads. Pads is mounted on need further eval per rubber vibration GIP Section 4.4.

isolators. The Evaluation by S&A?

anchorage 5/22/95 - During the calculation bolt tightness check on concluded that the 2/20/95, the concrete rubber isolators had expansion anchors for insufficient capacity the left rear rubber to transfer the vibration isolator were anchorage loads to found to be never the concrete installed expansion anchors.

B-21 Interim Resolution Documented Status I Final Required Date in the USI A-46 Seismic Resolution Close Out Completed Evaluation Report to NRC HX-66 is on the SSEL to EWR 96-046 SQ-001672.

6/18/99 maintain SW system integrity.

assigned. MR 97-Outlier is The air handling and air cooling 1 04 installed resolved.

function is not required. The SW replacement system engineer judged that a vibration isolators.

break in the attached 2" SW Accepted 2/28/98.

line would not significantly impact service water to other essential loads. The function of the air handling unit will be evaluated to determine if an anchorage upgrade is required.

HX-66A is on the SSEL to EWR 96-047 SQ-001888 12/14/00 maintain SW system integrity.

assigned. MR 98-Outlier is The air handling and air cooling 127 initiated. (RE:

resolved.

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

system engineer judged that a NeedWO. WO break in the attached 2" SW 9808637 is replacing line would not significantly HX-66A cooling 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.

HX-98 is on the SSEL to EWR 96-048 SQ-001841.

9/19/00 maintain SW system integrity.

assigned. MR 97-Outlier is The air handling and air cooling 105 installed. WO resolved.

function is not required. The SW 9807185 replaced system engineer judged that a HX-98 cooling coils.

break in the attached 2 1/2" SW line would not significantly impact service water to other essential loads. The function of the air handling unit will be evaluated to determine if an anchorage upgrade is required.

Outlier No.

69 70 71 POINT BEACH NUCLEAR PLANT, UNIT 2 1200114-R-002, REVISION 0 Program Equip System Equip Noun Name Class ID A,I,H 11 VNCSR HX-Cable

38A1, Spreading A2,A3 Room Air Conditioning Unit A,I,H 11 VNCR HX-Control

3881, Room Air 82,83, Conditioning 84 Unit A, I 12 DA K-48 G-02 EDG Starting Air Compressor Motor Or Diesel Status at Time of SRT Walkdown in 1993 0 - No Anchorage, Motor on steel isolation springs. ISRS exceeds RS. New component 7/13/94. It is the parent component of HX-38A 1, HX-38A2 and HX-38A3.

Equipment class changed from 21 to 11 0 - No Anchorage, Motor on steel isolation springs. ISRS exceeds RS. New component 7/13/94. It is the parent component of HX-3881, HX-3882, HX-3883 and HX-3884. Equipment class changed from 21 to 11 0 - Loose hand crank resting against it which may pose an interaction hazard.

4/21/95-a hand crank mount has been installed on the wall adjacent to the compressor B-22 Outlier Description Interim Resolution Documented Status I Final Required Date in the USI A-46 Seismic Resolution Close Out Completed Evaluation Report to NRC The chiller unit is not The chiller is on the SSEL to EWR 96-052 SQ-001957 5/19/02 anchored, the maintain SW integrity. A leak in assigned. Chiller Outlier is compressor motors the SW pipe would not HX-038A replaced.

resolved.

are on springs, and significantly affect SW flow to MR 97-049*8 the seismic demand other essential loads. The installed new heat exceeds 1.5 x 8S at HVAC room is designed to exchangers.

the low frequency handle that flooding from a SW peak.

break. The chill water cooling function of the unit is not required. The function of the chiller unit will be evaluated to determine if an anchorage upgrade is required.

The chiller unit is not The chiller is on the SSEL to EWR 96-051 SQ-001962 8/15/02 anchored, the maintain SW integrity. A leak in assigned. Chiller Outlier is compressor motors the SW pipe would not HX-0388 replaced.

resolved.

are on springs, and significantly affect SW flow to MR 97-049*C the seismic demand other essential loads. The installed new heat exceeds 1.5 x 8S at HVAC room is designed to exchangers.

the low frequency handle that flooding from a SW peak.

break. The chill water cooling 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 loose hand crank Hand crank installed on a Hand crank installed SQ-001822 4/21/95 was resting against bracket on the wall adjacent to on a bracket on the Outlier is the air compressor the air compressor wall adjacent to the resolved.

posing an air compressor interaction hazard.

Outlier No.

72 73 74 75 POINT BEACH NUCLEAR PLANT, UNIT 2 1200114-R-002, REVISION 0 Program Equip System Equip Noun Name Class ID A, I 16 125V D-07 Station Battery Charger A, I 16 125V D-08 Station Battery Charger A, I 16 y

DY-OA Red 125v Dc/120v Ac Alternate Inverter A, I 16 y

DY-OB Blue 125v Dc/120v Ac Alternate Inverter Status at Time of S RT Walkdown in 1993 0- Interaction, CABINET IS NOT TIED TO ADJACENT CABINET, ALSO BLOCK WALL MAY GOVERN HCLPF.

EWR submitted 2/4/94 for CSE to bolt battery charger to adjacent switchgear. MR 94-048 0- Interaction, CABINET IS NOT TIED TO ADJACENT CABINET, ALSO BLOCK WALL MAY GOVERN HCLPF.

EWR submitted 2/4/94 for CSE to bolt battery charger to adjacent switchgear.

MR 94-048 0 - Interaction; Mounted directly adjacent to 1 C-167.

The cabinets are not fastened together. P-REPORT 0- Interaction; Mounted directly adjacent to 2C-156.

The cabinets are not fastened together. P-REPORT B-23 Outlier Description Interim Resolution Documented Status I Final Required Date in the USI A-46 Seismic Resolution Close Out Completed Evaluation Report to NRC The battery charger The battery charger does not MR 94-048 bolted D-SQ-001938 12/13/00 is not attached to the contain essential relays, and 07 to the old 2A-05.

Outlier is adjacent switchgear.

there are 3 switchgear cubicles WO 9904504.

resolved.

between the battery charger and switchgear cubicle that contains the essential relays. Therefore, the battery charger and the switchgear are considered seismically operable.

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

The battery charger The battery charger does not MR 94-048 bolted D-SQ-001939 12/13/00 is not attached to the contain essential relays, and 08 to 1A-05. wo Outlier is adjacent switchgear.

there are 3 switchgear cubicles 9504505.

resolved.

between the battery charger and switchgear cubicle that contains the essential relays. Therefore, the battery charger and the switchgear are considered seismically operable.

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

The outlier is an The inverter does not contain MR 96-037 assigned SQ-001867 5/25/00 interaction. DY-OA any essential relays. It is IEEE to move inverter to Outlier is is mounted directly 344-1975 qualified. It is create a gap resolved.

adjacent to 1 C-167.

considered seismically operable between inverter The cabinets are not based on there being no and relay cabinet.

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.

The outlier is an The inverter does not contain MR 96-037*A SQ-001868 5/25/00 interaction. DY-OB any essential relays. It is IEEE assigned to move Outlier is is mounted directly 344-1975 qualified. It is inverter to create a resolved.

adjacent to 2C-157.

considered seismically operable gap between The cabinets are not based on there being no inverter and relay 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.

Outlier No.

76 77 POINT BEACH NUCLEAR PLANT, UNIT 2 1200114-R-002, REVISION 0 Program Equip System Equip Noun Name Class ID A,I,RG 19 RC 2TE-Rc Loop A 4508 Hot Leg Temperature Rtd A,I,RG 19 RC 2TE-Rc Loop A 450D Hot Leg Temperature Rtd Status at Time of SRT Walkdown in 1993 0 - Impinging on insulation. Does thermal expansion while hot accommodate seismic displacements? EWR submitted for MSA inspection/evaluation EWR 94-056. EWR determined that interaction was a problem, Calc N 168. MR 95-021 initiated to replace TE.

0 - Impinging on insulation. Does thermal expansion while hot accommodate seismic displacements? EWR submitted for MSA inspection/evaluation.

EWR 94-056 EWR determined that interaction was a problem, Calc N 168. MR 95-021 initiated to replace TE.

B-24 Outlier Description Interim Resolution Documented Status I Final Required Date in the USI A-46 Seismic Resolution Close Out Completed Evaluation Report to NRC The temperature An engineering evaluation MR 95-021 initiated SQ-001570 2/24/99 element is impinging showed that thermal expansion to replace TE with a Outlier is on insulation. It must did not accommodate the bent unit.

resolved.

be determined if expected seismic Scheduled for thermal expansion displacements. Modification U2R23 (RE: PHB) while hot request MR 95-021 is initiated to Replacement TE accommodate replace TE with a shorter one.

installed U2R23 seismic displacements.

The temperature An engineering evaluation MR 95-021 initiated SQ-001571 2/24/99 element is impinging showed that thermal expansion to replace TE with a Outlier is on insulation. It must did not accommodate the bent unit.

resolved.

be determined if expected seismic Scheduled for thermal expansion displacements. Modification U2R23 (RE: PHS) while hot request MR 95-021 is initiated to Replacement TE accommodate replace TE with a shorter one.

installed U2R23 seismic displacements.

Outlier No.

79 81 83 POINT BEACH NUCLEAR PLANT, UNIT 2 1200114-R-002, REVISION 0 Program Equip System Equip Noun Name Class ID A,I,RG 20 MMS C Main Control 1 (2)C-Boards 04 A, I 20 lOPS 2C-75 Turbine lops Main Trip Panel A, I 20 MMS 2C-Plant 105-Process I&C 114 Cabinets Status at Time of SRT Walkdown in 1993 0- Interaction, adjacent supply cabinets not secured.

EWR submitted.

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.

0 - Doors are not positively latched. T.

Dykstra to submit MWR after inspection.

6/19/95 - Need to discuss with Steve Bowe to see if he would rather install different handles or have I&C start using the key lock to latch the door. 9/23/96-wo 9607849 0 - Interaction-Supply cabinet interference EWR submitted.

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

B-25 Outlier Description Interim Resolution Documented Status I Final Required Date in the USI A-46 Seismic Resolution Close Out Completed Evaluation Report to NRC An adjacent supply The supply cabinet was Fixed, MR 94-021 SQ-001824 8/24/94 cabinet posed a attached to the back of 2C-03 bolted supply Outlier is spatial interaction under modification MR 94-021.

cabinets to the back resolved.

hazard.

of 1 C-03 and 2C-03.

The doors are not The cabinet does not contain wo 9607850 SQ-001826 12/796 positively latched.

any essential relays, and the installed new handle Outlier is doors are fairly light weight

-completed 12/7/96 resolved.

therefore, significant damage is not expected to occur. I & C will be contacted to determine if the existing door latch can be used or whether a new handle would be preferred.

An adjacent supply The supply cabinet was Fixed, MR 94-021 SQ-001830 8/24/94 cabinet posed a attached to the back of 2C-03 bolted supply completed.

spatial interaction under modification MR 94-021.

cabinet to the back hazard.

of 2C-03. Accepted 7/28/94

Outlier No.

86 88 91 92 POINT BEACH NUCLEAR PLANT, UNIT 2 1200114-R-002, REVISION 0 Program Equip System Equip Noun Name Class ID A, I 20 RP 2C-Rp Train A 151-Relay 155 Cabinets A, I 20 ESF 2C-Safeguards 156-Train A 158 Relay Cabinets A, I 20 RP 2C-Rp Train B 161-Relay 165 Cabinets A, I 20 ESF 2C-Safeguards 166-Train BAnd 167 Mise Relay Cabinets Status at Time of SRT Walkdown in 1993 0- ANCHOR DETAIL Unknown. No specific information on the grout pad to concrete floor anchorage.

Needs EWR 0- Interaction; Mounted directly adjacent to inverter DY-OB. The cabinets are not fastened together. P-REPORT Provide Mod Package 0- ANCHOR DETAIL Unknown. No specific information on the grout pad to concrete floor anchorage.

Needs EWR 0- ANCHOR DETAIL Unknown. No specific information on the grout pad to concrete floor anchorage.

Overhead light S-clamp needs to be clamped down.

Needs EWR B-26 Outlier Description Interim Resolution Documented Status I Final Required Date in the USI A-46 Seismic Resolution Close Out Completed Evaluation Report to NRC The anchor detail for Since the cabinet has MR 95-008 SQ-001604 12/2/97 the grout pad and anchorage as originally upgraded the Outlier is the perimeter designed, it is considered anchorage. Outlier resolved.

channel is unknown.

seismically operable.

Resolved Modification request MR 95-008 will upQrade the anchoraQe.

The outlier is an No "bad actor" relays are MR 96-037*A SQ-001870 5/25/00 Interaction. The located in the cabinets. The assigned to move Outlier is cabinets are relays in the cabinets have a inverter to create a resolved.

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

fastened together.

fastened to the adjacent Installation inverter.

complete.

The anchor detail for Since the cabinet has MR 95-010 SQ-001605 12/2/97 the grout pad and anchorage as originally cancelled, work Outlier is the perimeter designed, it is considered combined with MR resolved.

channel is unknown.

seismically operable.95-008. MR 95-008 Modification request MR 95-010 upgraded the will upgrade the anchorage.

anchorage. Outlier Resolved.

The anchor detail for Since the cabinet has MR 95-012 SQ-001833 12/2/97 the grout pad and anchorage as originally cancelled - work Outlier is the perimeter designed, it is considered transferred to MR resolved.

channel is unknown.

seismically operable.95-008. MR 95-008 Modification request MR 95-012 upgrade the will upgrade the anchorage.

anchorage, accepted 10/25/95.

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.

Outlier No.

93 94 96 POINT BEACH NUCLEAR PLANT, UNIT 2 1200114-R-002, REVISION 0 Program Equip System Equip Noun Name Class ID A, I 20 COMP C-178-Computer 179 Input Mux A,I,C 21 RH 2HX-Residual 11A Heat Removal Heat Exchanger A,I,C 21 cc 2T-12 Component Cooling Surge Tank Status at Time of SRT Outlier Description Walkdown in 1993 0 - Line Printer Line Printer, LP-300, adjacent to cabinet is kept on the floor adjacent to the cabinet.

0 - Base bolt nuts not The caste in place seated. 114" to 318" anchor bolt nuts are gaps. Not an not fully seated.

operability concern There are 114" to since HX is top 318" gaps between supported in both the nut and the HX lateral directions.

foot.

0 - Oversized anchor The saddle bolt holes (2.25" x anchorage on both 1.18") identified from ends of the tank has WEST 685J 114.

oversized anchor Anchor bolts are 1" bolt holes (2.25" x diameter. Too much 1.18") identified from clearance to say WEST 685J114. The seismic load is anchor bolts are 1" transferred to enough diameter. Therefore, anchor bolts.

there is too much clearance to say seismic load is transferred evenly to enough anchor bolts B-27 Interim Resolution Documented Status I Final Required Date in the USI A-46 Seismic Resolution Close Out Completed Evaluation Report to NRC C-178-179 are computer 12130198 - Have SQ-001834 12130198 cabinets contain primarily solid inspected the Outlier is state and circuit board Computer Room on resolved.

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.

Not an operability concern since EWR 96-053 SQ-001835 6118199 HX is top supported in both assigned. WO Outlier is lateral directions.

9815436 initiated to resolved.

inspect I replace anchor bolt nuts.

WO complete There are large washers MR 94-091*C SQ-001837 815196 between the anchorage nut and installed 112" steel Outlier is the oval holes. Therefore, some plate under each of resolved.

load will be transferred to all of the nuts on the the anchor bolts. In addition, the south side of the attached piping will help in tank. The plate is restraining the tank. Therefore, welded to the the tanks are considered saddle. The seismically operable. The installation was anchorage will be upgraded with checked 1213197 a structural member between the tank base and the anchor bolt.

Outlier No.

98 99 100 101 POINT BEACH NUCLEAR PLANT, UNIT 2 1200114-R-002, REVISION 0 Program Equip System Equip Noun Name Class ID A, I 21 Sl 2T-13 Refueling Water Storage Tank W/6 Immersion Htrs A, I 21 DA T-61F G-02 Edg Starting Air Receiver A, I 22 AUX8 Pab 8' Cable FTAR

& Conduit EA Raceways A, I 22 SPRE Csr Cable &

AD IN Conduit GRM Raceways Status at Time of SRT Walkdown in 1993 0-ANAL YSIS/REINFORC EMENT 7/25/94-Received DRAFT analysis from S& A showing RWST has sufficient capacity.

0 - Anchor - cracked grout B-28 Outlier Description Interim Resolution Documented Status I Final Required Date in the USI A-46 Seismic Resolution Close Out Completed Evaluation Report to NRC The tank does not The tank has been analyzed In WE NRC RAI SQ-001909 4/18/01 pass the screening using a finite element analysis response NPL 97-Outlier is criteria of Section 7

[23].

0450, page 5 of 22, resolved.

of the GIP.

WE stated that the design margin from the A-46 analysis is not sufficient. EWR 97-169 assigned.

MR 99-041 upgraded RWST.

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

The grout under the An inspection subsequent to the WO-9501221 SQ-001838 5/23/97 foot of one of the air seismic verification walkdown completed 5/23/97 -

resolves the 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.

LAR 9 is an Work completed SQ-001714 8/1/00 OUTLIER because under MR 96-022.

resolves the 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.

LAR 3 & LAR 4 are MR 96-080 created SQ-001881 9/25/00 OUTLIER(s) to upgrade cable Outlier is 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.

Outlier No.

105 108 110 114 POINT BEACH NUCLEAR PLANT, UNIT 2 1200114-R-002, REVISION 0 Program Equip System Equip Noun Name Class ID A, I 22 U2C46 U2c46' FTAR Cable &

EA Conduit Raceways A,I,RG 3

4.16KV 2A-05 4.16 KvBus Switchgear (Safeguards)

A,I,RG 3

4.16KV 2A-06 4.16 Kv Bus (old)

Switchgear (Safeguards)

A,I,V 7

Sl 2SI-Si Test Line 8978 Return Second Off Isolation Status at Time of SRT Walkdown in 1993 0 - Cables not tied to tray SAT-0-WELD QUALITY IN

QUESTION, Recommend thorough weld inspection. T.

Dykstra to check with QA about weld inspections PO - Not fastened to adjacent D-07 battery charger. WELD QUALITY IN

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 SAT Attached copper lines too stiff.

T. Dykstra to evaluate failure if copper line breaks. Valve currently 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 B-29 Outlier Description Interim Resolution Documented Status I Final Required Date in the USI A-46 Seismic Resolution Close Out Completed Evaluation Report to NRC There is an isolated Resolved during SQ-001640 1/8/99 vertical cable tray U2R23. WO resolves which has no plastic 9713098. Verified outlier ties and the cables during walkdown.

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

Weld inspection NOT AN 12/13/00 completed, used OUTLIER-results to adjust resolved w/

anchorage capacity weld in the anchorage inspection calculation.

and anchorage calc.

MR 94-048 SQ-001938 12/13/00 connected cabinets Outlier is together. WO resolved.

9904504.

Resolved NOT AN 11/11/94 OUTLIER-Resolved on original SEWS

Outlier No.

116 117 118 POINT BEACH NUCLEAR PLANT, UNIT 2 1200114-R-002, REVISION 0 Program Equip System Equip Noun Name Class ID A,I,C 8 cc 2CC-T-12 Cc 815 Surge Tank Emergency Makeup Water Inlet A, I 8 sw SW-K-3a Sa 2832A Compressor

-S Inlet Solenoid A, I 15 125V D-05 125v De Station Battery B-30 Status at Time of SRT Outlier Description Interim Resolution Documented Status I Final Required Date Walkdown in 1993 in the USI A-46 Seismic Resolution Close Out Completed Evaluation Report to NRC PO-pipe has NOT AN OUTLIER-NOT AN 3/30/01 insufficient supports -

CCW Upgrade OUTLIER-11/11/94 update-identified these Resolved on STATUS changed to valves as having original 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 SAT Attached Resolved NOT AN 10/26/94 conduit is very flexible OUTLIER-and should be Resolved on 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.

SAT- 0-SPACER, Resolved NOT AN 1/18/95 Need battery cell type OUTLIER-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

Outlier No.

119 120 121 122 POINT BEACH NUCLEAR PLANT, UNIT 2 1200114-R-002, REVISION 0 Program Equip System Equip Noun Name Class ID A, I 15 125V D-06 125v De Station Battery A, I 15 125V D-305 Swing Station Battery A,I,C 18 cc Fl-643 K-1a Waste Gas Comp Cc Return Flow Indicator A,I,C 18 cc Fl-645 K-1b Waste Gas Comp Cc Return Flow Indicator B-31 Status at Time of SRT Outlier Description Interim Resolution Documented Status I Final Required Date Walkdown in 1993 in the USI A-46 Seismic Resolution Close Out Completed Evaluation Report to NRC SAT- 0-SPACER.

Resolved NOT AN 1/18/95 EWR submitted 2/4/94 OUTLIER-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 SAT- 0-SPACER.

Resolved NOT AN 1/18/95 EWR submitted 2/4/94 OUTLIER-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 SAT Anchor Bolted Resolved NOT AN 7/94 to Block Wall - no thru OUTLIER-bolts T. Dykstra to Resolved on check scope of block original wall program. Tug SEWS tested by B.O. Sasman

& W. Djordjevic 7/94 OK.

SAT Anchor Bolted Resolved NOT AN 7/94 to Block Wall - no thru OUTLIER-bolts T. Dykstra to Resolved on check scope of block original wall program. Tug SEWS tested by B.O. Sasman

& W. Djordjevic 7/94 OK.

Outlier No.

123 124 125 126 POINT BEACH NUCLEAR PLANT, UNIT 2 1200114-R-002, REVISION 0 Program Equip System Equip Noun Name Class ID I,RG 18 AF LT-T-24b Cst 4039 Level Transmitter I,RG 18 AF LT-T-24a Cst 4040 Level Transmitter I,RG 18 AF LT-T-24b Cst 4041 Level Transmitter I,RG 18 AF LT-T-24a Cst 4038 Level Transmitter B-32 Status at Time of SRT Outlier Description Interim Resolution Documented Status I Final Required Date Walkdown in 1993 in the USI A-46 Seismic Resolution Close Out Completed Evaluation Report to NRC 0 - Interaction, Deleted from SSEL Deleted from 1/18/95 POTENTIAL FOR SSEL 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.

0 - Interaction, Deleted from SSEL Deleted from 1/18/95 POTENTIAL FOR SSEL 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.

0- Interaction, Deleted from SSEL Deleted from 1/18/95 POTENTIAL FOR SSEL 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.

0- Interaction, Deleted from SSEL Deleted from 1/18/95 POTENTIAL FOR SSEL BLOCK WALL TO FALLON COMPONENT. T.

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

- L Ts removed from A-46 list. StiiiiPEEE and RG 1.97.

Outlier No.

127 128 131 POINT BEACH NUCLEAR PLANT, UNIT 2 1200114-R-002, REVISION 0 Program Equip System Equip Noun Name Class ID A, I 18 RP 2PT-Hx-1a Sg 469 Pressure Transmitter A, I 18 RP 2PT-Hx-1a Sg 482 Steam Pressure Transmitter A,I,C 18 sc 2RK-Primary 20 Plant Sample Room Rack Status at Time of SRT Walkdown in 1993 SAT- 0-lnteraction-Insufficient slack on inlet tube. T. Dykstra to submit MWR 11/11/94 Update-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 SAT- 0-lnteraction-Insufficient slack on inlet tube. T. Dykstra to submit MWR 11/11/94 Update-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 SAT Interim outlier until anchorage is checked. Interaction

- adjacent sample sink has no visible anchorage 8-33 Outlier Description Interim Resolution Documented Status I Final Required Date in the USI A-46 Seismic Resolution Close Out Completed Evaluation Report to NRC Resolved NOT AN 11/11/94 OUTLIER-Resolved on original SEWS Resolved NOT AN 11/11/94 OUTLIER-Resolved on original SEWS 4/25/95 - phone NOT AN 4/25/95 conversation with OUTLIER-Wally Djordjevic -

Resolved on determined that original since the only SEWS 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.

Outlier No.

132 POINT BEACH NUCLEAR PLANT, UNIT 2 1200114-R-002, REVISION 0 Program Equip System Equip Noun Name Class ID A,l 20 RP 2C-Plant 115-Process I&C 133 Cabinets B-34 Status at Time of SRT Outlier Description Interim Resolution Documented Status I Final Required Date Walkdown in 1993 in the USI A-46 Seismic Resolution Close Out Completed Evaluation Report to NRC PO-Interaction-Fixed, MR 94-021 SQ-001839 8/24/94 Supply cabinet bolted supply completed.

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.

SWEL SWELI-2 SWELI-2 SWELI-2 SWELI-2 SWELI-2 SWELI-2 SWELI-2 SWELI-2 SWELI-2 SWELI-2 SWELI-2 SWELI-2 SWELI-2 SWELI-2 SWELI-2 SWEL1-2 SWELI-2 SWELI-2 SWELI-2 SWELI-2 SWELI-2 SWELI-2 SWELI-2 SWELI-2 POINT BEACH NUCLEAR PLANT, UNIT 2 1200114-R-002, REVISION 0 ATTACHMENT A Seismic Walkdown Eauioment List Unit 2 and SFP fSWEL)

RISK N

UNIT SYS EQUIP WALK EQUIP#

EQUIP NAME 1

2 3

4 5

TRN E

CODE CLASS BY w

AREA y

2 AF 5

30 2P-029 AUX FEED WATER TURBINE-DRIVEN PUMP X X X

B 0

AF 5

30 P-038B STAND BY STEAM GENERATOR PUMP X

X X

B y

y 2

AF 7

30 2AF-04002 2P-29 AFP MINI RECIRC CONTROL X X X

B y

0 AF 7

30 AF-04014 P-38B SSGP MINI RECIRC CONTROL X X X

B 0

AF 7

30 AF-04019 P-38B SSGP DISCHARGE CONTROL X X X

B y

0 125V 14 30 D-64 125V DC DISTRIBUTION PANEL X X X X X B

2 AF 18 30 2RK-35 2P-29 AUX FEED WATER PUMP X X X

B INSTRUMENTATION RACK 2

MS 20 30 2C-197 2P-29 AFP SUCTION PRESSURE CONTROL X X X

B PANEL 2

AF 21a 30 2T-212 2P-29 AFP MINI RECIRC IA 2AF-4002 BACKUP X X X

B ACCUMULATOR 2

AF 8a 30 2AF-04000 2P-29 AFP DISCHARGE 2HX-1B SG INLET X X X

B ISOLATION MOV 2

AF 8a 30 2AF-04001 2P-29 AFP DISCHARGE 2HX-1A SG INLET X X X

B ISOLATION MOV 2

AF 8a 30 2AF-04006 2P-29 AFP SUCTION FROM SERVICE WATER X X X

B 0

AF 8a 30 AF-04016 P-38B SSGP SUCTION FROM SERVICE WATER X X X

B 0

AF Sa 30 AF-04020 P-38B SSGP DISCHARGE TO 2HX-1B STEAM X X X

B GENERATOR 2

MS 8b 30 2MS-02090 2P-29 AFP BEARING COOLING INLET X

X X

B y

2 480V 2

9 2B-03 480V SAFEGUARDS LOAD CENTER X X X X X A y

2 480V 2

9 2B-04 480V SAFEGUARDS LOAD CENTER X X X X X B

y 2

480V 4

9 2X-13 2B-03 STATION SERVICE TRANSFORMER X X X X X A y

2 480V 4

9 2X-14 2B-04 STATION SERVICE TRANSFORMER X X X X X B y

0 125V 14 9

D-ll 125V DC DISTRIBUTION PANEL X X X X X A y

y 0

125V 14 9

D-13 125V DC DISTRIBUTION PANEL X X X X X B y

0 125V 14 9

D-26 125V DC DISTRIBUTION PANEL X X X X X A y

0 125V 14 9

D-27 125V DC DISTRIBUTION PANEL X X X X X B 0

y 14 9

Y-203 WHITE 120V INVERTER DISTRIBUTION X

X X X X A PANEL B-35 IPEEE LOCATION DESC Equip.

Enhanced 8/CB/AFP RM 2P-29 CUB 8/CB/AFP RM P-38B CUB 8/CB/AFP RM 2P-29 CUB 8/CB/AFP RM P-38B CUB 8/CB/AFP RM P-38B CUB 8/CB/AFP RM 2P-29 CUB 8/CB/AFP RM 2P-29 CUB 8/CB/AFP RM 2P-29 CUB 8/CB/AFP RM 8/CB/ AFP RM 2P-29 CUB 8/CB/AFP RM 2P-29 CUB 8/CB/AFP RM 2P-29 CUB 8/CB/AFP RM P-38B CUB 8/CB/AFP RM P-38B CUB 8/CB/AFPRM X

26/CB/CSR X

26/CB/CSR 26/CB/CSR EAST 26/CB/CSR EAST 26/CB/CSR 26/CB/CSR EAST 26/CB/CSR WEST WALL

SWEL SWELI-2 SWELI-2 SWELI-2 SWELI-2 SWELI-2 SWELI-2 SWELI-2 SWEL1-2 SWELI-2 SWELI-2 SWELI-2 SWELI-2 SWELI-2 SWELI-2 SWELI-2 SWELI-2 SWELI-2 SWELI-2 SWELI-2 SWELI-2 SWELI-2 SWELI-2 SWELI-2 SWELI-2 SWELI-2 SWELI-2 POINT BEACH NUCLEAR PLANT, UNIT 2 1200114-R-002, REVISION 0 RISK N

UNIT SYS EQUIP WALK E

CODE CLASS BY w

AREA 2

y 16 9

2 y

16 9

0 y

16 9

y 0

sw 6

27 y

0 sw 6

27 y

0 sw 6

28 y

0 sw 6

28 y

0 sw 6

28 0

sw 8a 27 0

sw 8a 28 y

2 480V 1

35 y

0 DG 9

31 y

0 DG 9

31 y

0 DG 9

31 y

y 0

VNDG 9

32 y

y 0

VNDG 9

32 y

0 125V 14 35 y

y 0

DG 17 36 y

0 DG 20 35 y

0 DA 21a 36 y

1 480V 1

11 y

2 480V 1

11 y

0 DG 17 11 0

DG 20 11 0

DG 20 11 EQUIP#

2DY-01 2DY-02 DY-OA P-032B P-032C P-032D P-032E P-032F SW-02890 SW-02891 2B-40 W-181B1 W-181B2 W-181B3 W-184B W-184C D-40 G-04 C-082 T-171A T-171B 1B420C-B957D 2B427C-B957D G-02 C-035 C-035A B-36 EQUIP NAME 1

2 3

4 5

TRN IPEEE LOCATION DESC Equip.

Enhanced RED 125V DC/120V AC INVERTER X

X X

A 26/CB/CSR BLUE 125V DC/120V AC INVERTER X

X X

B 26/CB/CSR RED 125V DC/120V AC ALTERNATE X

X X

A X

26/CB/CSR INVERTER SERVICE WATER PUMP X

X A

X 8/CWPH/SW BLDG SERVICE WATER PUMP X

X B

X 8/CWPH/SW BLDG SERVICE WATER PUMP X

X B

X 8/CWPH/SW BLDG SERVICE WATER PUMP X

X B

X 8/CWPH/SW BLDG SERVICE WATER PUMP X

X A

X 8/CWPH/SW BLDG NORTH HEADER TO SOUTH SUPPLY X

X B

8/CWPH/SW BLDG HEADER CROSSCONNECT SOUTH TO NORTH SUPPLY HEADER X

X A

8/CWPH/SW BLDG CROSSCONNECT 480V MOTOR CONTROL CENTER DGB X

X X

B 28/DGB/G-04 SWGR RM G-04 EDG HX-265B RADIATOR FAN X

X X

B 50/DGB/G-04 RADTR RM G-04 EDG HX-265B RADIATOR FAN X

X X

B 50/DGB/G-04 RADTR RM G-04 EDG HX-265B RADIATOR FAN X

X X

B 50/DGB/G-04 RADTR RM G-04 EDG RM LARGE CAPACITY EXHAUST X

X X

B 50/DGB/G-04 FAN RM FAN G-04 EDG RM SMALL CAPACITY EXHAUST X

X X

B 50/DGB/G-04 FAN RM FAN G-04 EDG DC DISTRffiUTION PANEL X

X X

B 28/DGB/G-04 SWGR RM EMERGENCY DIESEL GENERATOR X

X X

B 28/DGB/G-04 RM G-04 EDG CONTROL PANEL X

X X

B 28/DGB/G-04 SWGR RM G-04 EDG STARTING AIR RECEIVER X

X X

B 28/DGB/G-04 RM G-04 EDG STARTING AIR RECEIVER X

X X

B 28/DGB/G-04 RM P-32C SERVICE WATERPUMPNORMAL/ALT X

X B

8/CB/G-02 RM TRANSFERSW P-32E SERVICE WATER PUMP NORMAL/ ALT X

X B

8/CB/G-02 RM TRANSFERSW EMERGENCY DIESEL GENERATOR X

X X

A 8/CB/G-02 RM G-02 EDG ALARM AND ELECTRICAL PANEL X

X X

A 8/CB/G-02 RM W WALL G-02 EDG LOCAL TRANSFER PANEL X

X X

A 8/CB/G-02 RM W WALL

SWEL SWEL1-2 SWEL1-2 SWELl-2 SWELl-2 SWELl-2 SWELl-2 SWELl-2 SWELl-2 SWELl-2 SWELl-2 SWELl-2 SWELl-2 SWELl-2 SWEL1-2 SWELl-2 SWELl-2 SWELl-2 SWELl-2 SWELl-2 SWELl-2 SWELl-2 SWELl-2 SWELl-2 POINT BEACH NUCLEAR PLANT, UNIT 2 1200114-R-002, REVISION 0 RISK N

UNIT SYS EQUIP WALK E

CODE CLASS BY w

AREA 0

DG 20 11 0

PO 21a 11 0

DA 21a 11 0

PO 8a 11 0

sw 8b 29 0

sw 8b 29 2

IA 7

23 2

IA 7

23 y

0 sw 8a 22 y

0 sw 8a 46 y

2 cc 5

20 y

2 cc 5

20 2

SI 5

19 2

SI 5

19 y

2 SI 5

19 y

2 SI 5

19 2

SI 8a 19 y

2 SI 8a 19 y

2 480V 1

16 y

2 CV 5

40 EQUIP#

C-079 T-031B T-061A T-061D T-061F F0-03931 SW-02820-s SW-02826-s 2IA-03047 2IA-03048 SW-02869 SW-02870 2P-011A 2P-011B 2P-014A 2P-014B 2P-015A 2P-015B 2SI-00825B 2SI-00857B 2SI-00896B 2B-32 2P-002C 8-37 EQUIP NAME 1

2 3

4 5

TRN IPEEE LOCATION DESC Equip.

Enhanced G-02 EDG DC POWER TRANSFER CONTROL X

X X

A 8/CB/G-02 RM PANEL G-02 DIESEL GENERA TOR DAY TANK X

X X

A 8/CB/G-02 RM G-02 EDG STARTING AIR RECEIVER (RlGHT X

X X

A 8/CB/G-02 RM BANK)

G-02 EDG STARTING AIR RECEIVER (LEFT X

X X

A 8/CB/G-02 RM BANK)

G-02 EDG STARTING AIR RECEIVER (LEFT X

X X

A 8/CB/G-02 RM BANK)

T-31B G-02 EDG DAY TANK INLET SECOND X

X X

A 8/CB/G-02 RM OFF ISOLATION K-2B IA COMPRESSOR INLET SOLENOID X

B G-02ROOM K-2A IA COMPRESSOR INLET SOLENOID X

A 8/CB/AIR COMP RM U2C IA HEADER INLET CONTROL X

A 26/P AB/PIPEW A Y #3 U2C IA HEADER INLET CONTROL X

B 26/P AB/PIPEW A Y #3 NORTH HEADER TO WEST HEADER X

A 26/P AB/CENTRAL SOUTH HEADER TO WEST HEADER X

B 26/P AB/CENTRAL CROSSCONNECT COMPONENT COOLING WATER PUMP X

X X

A X

8/P AB/CC PUMP AREA COMPONENT COOLING WATER PUMP X

X X

B X

8/P AB/CC PUMP AREA CONTAINMENT SPRAY PUMP X

A X

8/P AB/SPRA Y PUMP AREA CONI AINMENT SPRAY PUMP X

B X

8/P AB/SPRA Y PUMP AREA SAFETY INJECTION PUMP X

X X

A 8/P AB/SI PUMP AREA SAFETY INJECTION PUMP X

X X

B 8/P AB/SI PUMP AREA T-13 RWST OUTLET TO P-15NB SI PUMP X

X X

B 8/P AB/SPRA Y PUMP AREA HX-11B RHR HX OUTLET TO P-15B SI PUMP X

X X

B 8/P AB/SI PUMP AREA SUCTION P-15B SI PUMP SUCTION X

X X

B 8/P AB/SI PUMP AREA 480V MOTOR CONTROL CENTER P AB X

X X

A 8/PABIU2 CHG PUMP SAFEGUARDS AREA CHARGING PUMP (Pump Only as Pressure X

X X

B 8/PABIU2 CHG PUMP RM Boundary)

SWEL SWELl-2 SWELl-2 SWELl-2 SWELl-2 SWELl-2 SWELl-2 SWELl-2 SWELl-2 SWELl-2 SWELl-2 SWELl-2 SWELl-2 SWELl-2 SWELl-2 SWELl-2 SWELl-2 SWELl-2 SWELl-2 SWELl-2 SWELl-2 SWELl-2 SWEL2 SWEL2 POINT BEACH NUCLEAR PLANT, UNIT 2 1200114-R-002, REVISION 0 RISK N

UNIT SYS EQUIP WALK E

CODE CLASS BY w

AREA 2

cv 7

12 y

2 SI Sa 12 y

2 cv Sa 16 y

2 SI Sa 12 2

SI 21a 49,50 2

SI Sa 49 2

SI Sa 51 y

2 RH Sa 52 2

MS 7

25 2

MS 7

25 2

4SOV 1

21 2

4SOV 1

21 y

2 4.16K 3

21 v

y 0

125V 14 21 y

0 125V 15 45 y

y 0

125V 16 21 y

y 0

125V 16 21 2

cc 19 s

y y

0 cc 21b s

y y

0 cc 21b s

0 VNBI 10 4

0 SF 5

24 0

SF 5

24 EQUIP#

2CV-00142 2SI-OOS66A 2CV-00112B 2SI-OOS66B T-034A SI-OOS41A SI-OOS7SA RH-00720 2MS-02015 2MS-02016 2B-39 2B-49 2A-05 D-02 D-06 D-07 D-OS TE-00621 HX-012C HX-012B W-OS6 P-012B P-012A B-38 EQUIP NAME 1

2 3

4 5

TRN IPEEE LOCATION DESC Equip.

Enhanced CHARGING LINE FLOW CONTROL X X X

A S/P AB/PIPEW A Y #4 COLD LEG INJECTION LINE ISOLATION X X X

X X A SIP AB/PIPEW A Y #4 2P-2A-C CHARGING PUMP REFUELING X X X

A S/PABIU2 CHG PUMP WATER SUCTION AREA CORE DELUGE INJECTION LINE ISOLATION X X X X X B SIP AB/PIPEW A Y #4 SAFETY INJECTION ACCUMULATOR X

X X A

21/U2CINW QTR, 46/U2CNWQTR T-34A SI ACCUMULATOR OUTLET X X X A

21/U2CINW QTR OPERATOR P-15B SI PUMP R-1 REACTOR VESSEL X X X

X A 21/U2C/C-1 AIR LOCK INJECTION AREA EAST RHR RETURN TO RCS X

A 46/U2C/SE QTR HX-lB SG HDR ATMOSPHERIC STEAM DUMP X X X

B S5/U2F CONTROL HX-lA SG HDR ATMOSPHERIC STEAM DUMP X X X

A S5/U2F CONTROL 4SOV MOTOR CONTROL CENTER TRAIN A X X X X X A S/CBNSGRM BATTERY CHARGER SUPPLY 4SOV MOTOR CONTROL CENTER TRAIN B X X X X X B

S/CBNSGRM BATTERY CHARGER SUPPLY 4.16 KV BUS SWITCHGEAR (SAFEGUARDS)

X X X X X A S/CBNSGRM 125V DC DISTRIBUTION PANEL X X X

X X B S/CBNSGRM 125V DC STATION BATTERY X X X X X B

X S/CB/D-06 BATT RM D-05 DC STATION BATTERY CHARGER X X X X X A S/CBNSGRM D-06 DC STATION BATTERY CHARGER X X X X X B

S/CBNSGRM HX-12C/D CC HX OUTLET HEADER X

X X

0 46/P AB/CC HX AREA TEMPERATURE RTD COMPONENT COOLING WATER HEAT X

X X

0 46/P AB/CC HX AREA EXCHANGER COMPONENT COOLING WATER HEAT X X X

0 46/P AB/CC HX AREA EXCHANGER PAB BATTERY AND INVERTER ROOM VENT X X X X X B 35/PAB/D-106 ROOF FAN SPENT FUEL COOLING PUMP B

46/P AB/SFP HX AREA SPENT FUEL COOLING PUMP A

46/P AB/SFP HX AREA

SWEL SWEL2 SWEL2 SWEL2 SWEL2 SWEL2 SWEL2 SWEL2 SWELl-2 POINT BEACH NUCLEAR PLANT, UNIT 2 1200114-R-002, REVISION 0 RISK N

UNIT SYS EQUIP WALK E

CODE CLASS BY w

AREA 0

SF 21b 24 0

sw 8a 24 0

sw 0

14 y

2 RH 5

44 B-39 EQUIP#

EQUIP NAME 1

2 3

4 5

TRN IPEEE LOCATION DESC Equip.

Enhanced HX-013B SPENT FUEL POOL HEAT EXCHANGER B

46/P AB/SFP HX AREA HX-013A SPENT FUEL POOL HEAT EXCHANGER A

46/P AB/SFP HX AREA SW-HX-13B SFP HX OUTLET B

46/P AB/SFP HX AREA 02930B SW-HX-13A SFP HX OUTLET A

46/P AB/SFP HX AREA 02930A SW-HX-13B SFP HX INLET B

46/P AB/SFP HX AREA 02927B SW-HX-13A SFP HX INLET A

46/P AB/SFP HX AREA 02927A SF-00785B P-9 HUT RECIRC PUMP SUCTION FROM B

8/P AB/P-9 HUT AREA TRANSFER CANAL WEST 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 Unit 2 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 14 Distribution panels and Auto Transfer 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.

SWEL SWEL1-2 SWEL1-2 SWEL1-2 SWEL1-2 SWEL1-2 SWEL1-2 SWEL1-2 SWEL1-2 SWEL1-2 SWEL1-2 SWEL1-2 SWEL1-2 SWEL1-2 SWEL1-2 SWEL1-2 SWEL1-2 SWEL1-2 SWEL1-2 SWEL1-2 SWEL1-2 SWEL1-2 POINT BEACH NUCLEAR PLANT, UNIT 2 1200114-R-002, REVISION 0 Attachment C Selected Equipment List Unit 2 and SFP SYS EQUIP EQUIP RISK NEW UNIT CODE CLASS NUMBER EQUIPMENT NAME 1

2 3

y 0

125V 14 D-02 125V DC DISTRIBUTION PANEL X

X X

y 0

125V 15 D-06 125V DC STATION BATTERY X

X X

y y

0 125V 16 D-07 D-05 DC STATION BATTERY CHARGER X

X X

y y

0 125V 16 D-08 D-06 DC STATION BATTERY CHARGER X

X X

y 0

125V 14 D-11 125V DC DISTRIBUTION PANEL X

X X

y y

0 125V 14 D-13 125V DC DISTRIBUTION PANEL X

X X

y 0

125V 14 D-26 125V DC DISTRIBUTION PANEL X

X X

y 0

125V 14 D-27 125V DC DISTRIBUTION PANEL X

X X

y 0

125V 14 D-40 G-04 EDG DC DISTRIBUTION PANEL X

X X

y 0

125V 14 D-64 125V DC DISTRIBUTION PANEL X

X X

y 2

4.16KV 3

2A-05 4.16 KV BUS SWITCHGEAR (SAFEGUARDS)

X X

X y

2 480V 2

2B-03 480V SAFEGUARDS LOAD CENTER X

X X

y 2

480V 2

2B-04 480V SAFEGUARDS LOAD CENTER X

X X

480V MOTOR CONTROL CENTER PAB y

2 480V 1

2B-32 SAFEGUARDS X

X X

480V MOTOR CONTROL CENTER TRAIN A 2

480V 1

2B-39 BATTERY CHARGER SUPPLY X

X X

y 2

480V 1

2B-40 480V MOTOR CONTROL CENTER DGB X

X X

480V MOTOR CONTROL CENTER TRAIN B 2

480V 1

2B-49 BATTERY CHARGER SUPPLY X

X X

y 2

480V 4

2X-13 2B-03 STATION SERVICE TRANSFORMER X

X X

y 2

480V 4

2X-14 2B-04 STATION SERVICE TRANSFORMER X

X X

B420C-P-32C SERVICE WATER PUMP y

1 480V 1

B957D NORMALIAL T TRANSFER SW X

B427C-P-32E SERVICE WATER PUMP y

2 480V 1

B957D NORMAL/AL T TRANSFER SW X

B-41 SEISMIC 4

5 LOCATION DESC CAT X

X 8/CBNSG RM I

X X

8/CB/D-06 BATT RM I

X X

8/CBNSG RM I

X X

8/CBNSG RM I

X X

26/CB/CSR EAST I

X X

26/CB/CSR EAST I

X X

26/CB/CSR I

X X

26/CB/CSR EAST I

28/DGB/G-04 SWGR X

X RM I

8/CB/AFP RM 2P-29 X

X CUB I

X X

8/CBNSG RM I

X X

26/CB/CSR I

X X

26/CB/CSR I

8/PAB/U2 CHG PUMP X

X AREA I

X X

8/CBNSG RM I

28/DGB/G-04 SWGR X

X RM I

X X

8/CBNSG RM I

X X

26/CB/CSR I

X X

26/CB/CSR I

X 8/CB/G-02 RM I

SWEL1-2 SWEL1-2 SWEL1-2 SWEL1-2 SWEL1-2 SWEL1-2 SWEL1-2 SWEL1-2 SWEL1-2 SWEL1-2 SWEL1-2 SWEL1-2 SWEL1-2 SWEL1-2 SWEL1-2 SWEL1-2 SWEL1-2 SWEL1-2 SWEL1-2 SWEL1-2 POINT BEACH NUCLEAR PLANT, UNIT 2 1200114-R-002, REVISION 0 2

AF 8a 2

AF 8a y

y 2

AF 7

2 AF 8a y

2 AF 5

2 AF 18 2

AF 21a y

0 AF 7

0 AF 8a 0

AF 7

0 AF 8a 0

AF 5

y 2

cc 5

y 2

cc 5

y y

0 cc 21b y

0 cc 21b 2

cc 19 y

2 cv 8a 2

cv 7

y 2

cv 5

2AF-04000 2AF-04001 2AF-04002 2AF-04006 2P-029 2RK-35 2T-212 AF-04014 AF-04016 AF-04019 AF-04020 P-038B 2P-011A 2P-011B HX-012B HX-012C TE-00621 2CV-00112B 2CV-00142 2P-002C B-42 2P-29 AFP DISCHARGE 2HX-1 B SG INLET 8/CB/AFP RM 2P-29 ISOLATION MOV X

X X

CUB I

2P-29 AFP DISCHARGE 2HX-1A SG INLET 8/CB/AFP RM 2P-29 ISOLATION MOV X

X X

CUB I

8/CB/AFP RM 2P-29 2P-29 AFP MINI RECIRC CONTROL X

X X

CUB I

2P-29 AFP SUCTION FROM SERVICE 8/CB/AFP RM 2P-29 WATER X

X X

CUB I

8/CB/AFP RM 2P-29 AUX FEEDWATER TURBINE-DRIVEN PUMP X

X X

CUB I

2P-29 AUX FEEDWATER PUMP 8/CB/AFP RM 2P-29 INSTRUMENTATION RACK X

X X

CUB I

2P-29 AFP MINI RECIRC lA 2AF-4002 BACKUP ACCUMULATOR X

X X

8/CB/AFP RM I

8/CB/AFP RM P-38B P-38B SSGP MINI RECIRC CONTROL X

X X

CUB I

P-38B SSGP SUCTION FROM SERVICE 8/CB/AFP RM P-38B WATER X

X X

CUB I

8/CB/AFP RM P-38B P-38B SSGP DISCHARGE CONTROL X

X X

CUB I

P-38B SSGP DISCHARGE TO 2HX-1 B 8/CB/AFP RM P-38B STEAM GENERATOR X

X X

CUB I

8/CB/AFP RM P-38B STANDBY STEAM GENERATOR PUMP X

X X

CUB I

8/PAB/CC PUMP COMPONENT COOLING WATER PUMP X

X X

AREA I

8/PAB/CC PUMP COMPONENT COOLING WATER PUMP X

X X

AREA I

COMPONENT COOLING WATER HEAT EXCHANGER X

X X

46/PAB/CC HX AREA I

COMPONENT COOLING WATER HEAT EXCHANGER X

X X

46/PAB/CC HX AREA I

HX-12C/D CC HX OUTLET HEADER TEMPERATURE RTD X

X X

46/PAB/CC HX AREA I

2P-2A-C CHARGING PUMP REFUELING 8/PAB/U2 CHG PUMP WATER SUCTION X

X X

AREA I

CHARGING LINE FLOW CONTROL X

X X

8/PAB/PIPEWAY#4 I

CHARGING PUMP (Pump Only as Pressure 8/PAB/U2 CHG PUMP Boundary)

X X

X RM I

SWEL1-2 SWEL1-2 SWEL1-2 SWEL1-2 SWEL 1-2 SWEL1-2 SWEL1-2 SWEL1-2 SWEL1-2 SWEL1-2 SWEL1-2 SWEL1-2 SWEL1-2 SWEL1-2 SWEL1-2 SWEL1-2 SWEL1-2 SWEL1-2 SWEL1-2 SWEL1-2 SWEL1-2 POINT BEACH NUCLEAR PLANT, UNIT 2 1200114-R-002, REVISION 0 0

DA 21a 0

DA 21a y

0 DA 21a y

0 DA 21a 0

DG 20 0

DG 20 y

0 DG 20 y

0 DG 17 y

y 0

DG 17 y

0 DG 9

y 0

DG 9

y 0

DG 9

0 FO Sa 0

FO 21a 2

lA 7

2 lA 7

2 MS 20 2

MS 7

2 MS 7

T-061A T-0610 T-061 F T-171A T-171B C-035 C-035A C-079 C-082 G-02 G-04 W-181B1 W-181B2 W-181B3 F0-03931 T-031B 21A-03047 21A-03048 2C-197 2MS-02015 2MS-02016 B-43 G-02 EDG STARTING AIR RECEIVER (RIGHT BANK)

X X

X 8/CB/G-02 RM I

G-02 EDG STARTING AIR RECEIVER (LEFT BANK)

X X

X 8/CB/G-02 RM I

G-02 EDG STARTING AIR RECEIVER (LEFT BANK)

X X

X 8/CB/G-02 RM I

G-04 EDG STARTING AIR RECEIVER X

X X

28/DGB/G-04 RM I

G-04 EDG STARTING AIR RECEIVER X

X X

28/DGB/G-04 RM I

8/CB/G-02 RM W G-02 EDG ALARM AND ELECTRICAL PANEL X

X X

WALL I

8/CB/G-02 RM W G-02 EDG LOCAL TRANSFER PANEL X

X X

WALL I

G-02 EDG DC POWER TRANSFER CONTROL PANEL X

X X

8/CB/G-02 RM I

28/DGB/G-04 SWGR G-04 EDG CONTROL PANEL X

X X

RM I

EMERGENCY DIESEL GENERATOR X

X X

8/CB/G-02 RM I

EMERGENCY DIESEL GENERATOR X

X X

28/DGB/G-04 RM I

50/DGB/G-04 RADTR G-04 EDG HX-265B RADIATOR FAN X

X X

RM I

50/DGB/G-04 RADTR G-04 EDG HX-265B RADIATOR FAN X

X X

RM I

50/DGB/G-04 RADTR G-04 EDG HX-265B RADIATOR FAN X

X X

RM I

T-31 B G-02 EDG DAY TANK INLET SECOND OFF ISOLATION X

X X

8/CB/G-02 RM I

G-02 DIESEL GENERATOR DAY TANK X

X X

8/CB/G-02 RM I

U2C lA HEADER INLET CONTROL X

26/PAB/PIPEWAY #3 I

U2C lA HEADER INLET CONTROL X

26/PAB/PIPEWAY #3 I

P-29 AFP SUCTION PRESSURE CONTROL 8/CB/AFP RM 2P-29 PANEL X

X X

CUB I

HX-1 B SG HDR ATMOSPHERIC STEAM DUMP CONTROL X

X X

85/U2F I

HX-1A SG HDR ATMOSPHERIC STEAM DUMP CONTROL X

X X

85/U2F I

SWEL1-2 SWEL1-2 SWEL1-2 SWEL1-2 SWEL1-2 SWEL1-2 SWEL1-2 SWEL1-2 SWEL1-2 SWEL1-2 SWEL1-2 SWEL1-2 SWEL1-2 SWEL1-2 SWEL1-2 SWEL1-2 SWEL1-2 SWEL1-2 SWEL1-2 SWEL1-2 SWEL1-2 SWEL1-2 POINT BEACH NUCLEAR PLANT, UNIT 2 1200114-R-002, REVISION 0 2

MS 8b y

2 RH 8a 2

RH 5

2 Sl 8a 2

Sl 8a 2

Sl 21a 2

Sl 5

2 Sl 5

y 2

Sl 5

y 2

Sl 5

2 Sl 8a y

0 sw 6

y 0

sw 6

y 0

sw 6

y 0

sw 6

y 0

sw 6

0 sw 8b 0

sw 8b 2MS-02090 RH-00720 2P-010B SI-00841A SI-00878A T-034A 2P-014A 2P-014B 2P-015A 2P-015B 2SI-00825B 2SI-00857B 2SI-00866A 2SI-00866B 2SI-00896B P-032B P-032C P-032D P-032E P-032F SW-02820-S SW-02826-S B-44 P-29 AFP BEARING COOLING INLET X

X X

8/CB/AFP RM I

RHR RETURN TO RCS X

46/U2C/SE QTR I

RESIDUAL HEAT REMOVAL PUMP X

X X

-19/PAB I

T-34A Sl ACCUMULATOR OUTLET 21/U2C/T-34A OPERATOR X

X X

ACCUM EAST I

P-15B Sl PUMP R-1 REACTOR VESSEL 21/U2C/C-1 AIR LOCK INJECTION X

X X

X AREA EAST I

SAFETY INJECTION ACCUMULATOR X

X X

21/U2C/NW QTR I

8/PAB/SPRAY PUMP CONTAINMENT SPRAY PUMP X

AREA I

8/PAB/SPRAY PUMP CONTAINMENT SPRAY PUMP X

AREA I

SAFETY INJECTION PUMP X

X X

8/PAB/SI PUMP AREA I

SAFETY INJECTION PUMP X

X X

8/PAB/SI PUMP AREA I

8/PAB/SPRAY PUMP T-13 RWST OUTLET TO P-15A/B Sl PUMP X

X X

AREA I

HX-11 B RHR HX OUTLET TO P-15B Sl PUMP SUCTION X

X X

8/PAB/SI PUMP AREA I

COLD LEG INJECTION LINE ISOLATION X

X X

8/PAB/PIPEWAY #4 I

CORE DELUGE INJECTION LINE ISOLATION X

X X

8/PAB/PIPEWAY #4 I

P-15B Sl PUMP SUCTION X

X X

8/PAB/SI PUMP AREA I

SERVICE WATER PUMP X

X 8/CWPH/SW BLDG I

SERVICE WATER PUMP X

X 8/CWPH/SW BLDG I

SERVICE WATER PUMP X

X 8/CWPH/SW BLDG I

SERVICE WATER PUMP X

X 8/CWPH/SW BLDG I

SERVICE WATER PUMP X

X 8/CWPH/SW BLDG I

K-2B lA COMPRESSOR INLET SOLENOID X

G-02 ROOM I

K-2A lA COMPRESSOR INLET SOLENOID X

8/CB/AIR COMP RM I

SWEL1-2 SWEL1-2 SWEL1-2 SWEL1-2 SWEL1-2 SWEL1-2 SWEL1-2 SWEL1-2 SWEL1-2 SWEL1-2 SWEL1-2 PB PB PB PB PB PB PB PB PB POINT BEACH NUCLEAR PLANT, UNIT 2 12Q0114-R-002, REVISION 0 y

0 sw 8a y

0 sw 8a 0

sw 8a 0

VNBI 10 y

y 0

VNDG 9

y y

0 VNDG 9

2 y

16 2

y 16 0

y 14 2

125V 2

2 125V 2

0 125V 14 y

0 125V 15 0

125V 16 0

125V 16 SW-02869 SW-02870 SW-02890 SW-02891 W-086 W-184B W-184C 2DY-01 2DY-02 DY-OA Y-203 2SAF-04000 2SAF-04001 2SMS-02019 2SMS-02020 2SMS-02082 D-04 D-106 D-108 D-109 B-45 NORTH HEADER TO WEST HEADER X

26/PAB/CENTRAL I

SOUTH HEADER TO WEST HEADER CROSSCONNECT X

26/PAB/CENTRAL I

NORTH HEADER TO SOUTH SUPPLY HEADER CROSSCONNECT X

X 8/CWPH/SW BLDG I

SOUTH TO NORTH SUPPLY HEADER CROSSCONNECT X

X 8/CWPH/SW BLDG I

PAB BATTERY AND INVERTER ROOM VENT FAN X

X X

35/PAB/D-106 ROOF I

G-04 EDG RM LARGE CAPACITY EXHAUST FAN X

X X

50/DGB/G-04 FAN RM I

G-04 EDG RM SMALL CAPACITY EXHAUST FAN X

X X

50/DGB/G-04 FAN RM I

RED 125V DC/120V AC INVERTER X

X X

26/CB/CSR I

BLUE 125V DC/120V AC INVERTER X

X X

26/CB/CSR I

RED 125V DC/120V AC ALTERNATE INVERTER X

X X

26/CB/CSR I

WHITE 120V INVERTER DISTRIBUTION 26/CB/CSR WEST PANEL X

X X

WALL I

2P-29 AFP DISCH 2HX-1B SG INLET !SOL MOVSTARTER X

X X

8/CBNSG EQUIP RM I

2P-29 AFP DISCH 2HX-1A SG INLET !SOL MOVSTARTER X

X X

8/CBNSG EQUIP RM I

HX-1 B SG HDR P-29 AFP STEAM SUPPLY MOVSTARTER X

X X

8/CBNSG EQUIP RM I

HX-1A SG HDR P-29 AFP STEAM SUPPLY MOVSTARTER X

X X

8/CBNSG EQUIP RM I

8/CB/AFP RM 2P-29 P-29 AFP OVERSPEED TRIP STARTER X

X X

CUB I

26/PAB/INVERT RM 125V DC DISTRIBUTION PANEL X

X X

EAST I

26/PAB/D-1 06 BATT 125V DC STATION BATTERY X

X X

RM I

26/PAB/INVERT RM D-106 DC STATION BATTERY CHARGER X

X X

EAST I

26/PAB/INVERT RM SWING STATION BATTERY CHARGER X

X X

WEST I

PB PB PB PB PB PB PB PB PB PB PB PB PB PB PB PB PB PB PB PB POINT BEACH NUCLEAR PLANT, UNIT 2 1200114-R-002, REVISION 0 2

480V 1

2 480V 1

0 AF 18 2

cc 8a 2

cc 21b 0

DA 21a 0

DG 20 B336A-P-1 OA RHR PUMP NORMALIAL T TRANSFER B958B SWITCH D-09 SWING STN BATTERY CHARGER B42-391 TRAIN A CONTACTOR D-107 STATION BATTERY CHARGER TRAIN B42-394 ACONTACTOR D-08 STATION BATTERY CHARGER TRAIN B42-491 B CONTACTOR B429A-P-1 OB RHR PUMP NORMALIAL T TRANSFER B958B SWITCH RK-25B P-38B SSGP INSTRUMENTATION RACK 2CC-2HX-11A RHR HX SHELL SIDE OUTLET 00736A RELIEF 2CC-2HX-11 B RHR HX SHELL SIDE OUTLET 00736B RELIEF 2CC-00738A 2HX-11A RHR HX SHELL SIDE INLET 2CC-00738B 2HX-11 B RHR HX SHELL SIDE INLET 2CC-00759A 2P-1A RCP CC OUTLET MOV COMPONENT COOLING WATER HEAT 2HX-012D EXCHANGER COMPONENT COOLING WATER HEAT HX-012B EXCHANGER G-01 EDG STARTING AIR RECEIVER T-060A (RIGHT BANK)

G-01 EDG STARTING AIR RECEIVER (LEFT T-060D BANK)

G-02 EDG STARTING AIR RECEIVER T-061 B (RIGHT BANK)

G-02 EDG STARTING AIR RECEIVER T-061C (RIGHT BANK)

G-02 EDG STARTING AIR RECEIVER (LEFT T-061E BANK)

T-170C G-03 EDG STARTING AIR RECEIVER G-02 EDG DC POWER TRANSFER C-079 CONTROL PANEL B-46 X

X X

8/PAB/COL P-11 I

X X

X 8/CBNSG RM 2B-39 I

X X

X 8/CBNSG RM 2B-39 I

X X

X 8/CBNSG RM 2B-49 I

X X

X 8/PAB/COL P-12 I

8/CB/AFP RM P-38B X

X X

CUB I

X X

X 8/PAB/PIPEWAY #3 I

X X

X 8/PAB/PIPEWAY #3 I

X X

X 8/PAB/PIPEWAY#3 I

X X

X 8/PAB/PIPEWAY #3 I

X X

X 8/PAB/PIPEWAY#3 I

X X

X 46/PAB/CC HX AREA I

X X

X 46/PAB/CC HX AREA I

X X

X 8/CB/G-01 RM I

X X

X 8/CB/G-01 RM I

X X

X 8/CB/G-02 RM I

X X

X 8/CB/G-02 RM I

X X

X 8/CB/G-02 RM I

X X

X 28/DGB/G-03 RM I

8/CB/G-02 RM N X

X X

WALL I

PB PB PB PB PB PB PB PB PB PB PB PB PB PB PB PB PB PB PB PB POINT BEACH NUCLEAR PLANT, UNIT 2 1200114-R-002, REVISION 0 0

DG 9

2 MMS 20 2

MS 8a 2

RH 21b 2

RH 5

2 RH 7

2 Sl 8a 2

Sl 8a 2

sw 7

0 sw 8b 0

VNBI 10 2

y 14 W-181A3 G-03 EDG HX-265A RADIATOR FAN SECONDARY SYSTEM POWER SUPPLIES 2C-105 PANEL 2MS-HX-1 B SG HEADER P-29 AFP STEAM 02019 SUPPLY MOV 2MS-HX-1A SG HEADER P-29 AFP STEAM 02020 SUPPLY MOV RESIDUAL HEAT REMOVAL HEAT 2HX-011A EXCHANGER RESIDUAL HEAT REMOVAL HEAT 2HX-011 B EXCHANGER 2P-010A RESIDUAL HEAT REMOVAL PUMP 2RH-00624 HX-11A RHR HX OUTLET CONTROL 2RH-00625 HX-11 B RHR HX OUTLET CONTROL 2SI-00825A T-13 RWST OUTLET TO P-15AIB Sl PUMP 2SI-P-10A RHR PUMP SUMP B SUCTION 00850A-M MOTOR/PUMP 2SI-P-10B RHR PUMP SUMP B SUCTION 00850B-M MOTOR/PUMP 2SI-P-10A RHR PUMP SUCTION FROM 00851A CONTAINMENT SUMP B 2SI-P-10B RHR PUMP SUCTION FROM 00851B CONTAINMENT SUMP B 2SI-HX-11A RHR HX OUTLET TO P-15A Sl 00857A PUMP SUCTION 2SI-00896A P-15A Sl PUMP SUCTION 2SW-HX-12D CC HX OUTLET TEMPERATURE 00012D CONTROL SW-02832B-S K-3B SA COMPRESSOR INLET SOLENOID PAB BATTERY AND INVERTER ROOM W-086 VENT FAN 2Y-02 BLUE 120VVITAL INSTRUMENT PANEL B-47 50/DGB/G-03 RADTR X

X X

RM I

X X

X 44/CB/CR I

X X

X 46/PAB/BAST AREA I

X X

X 46/PAB/BAST AREA I

X X

X

-5/PAB/RHR HX CUB I

X X

X

-5/PAB/RHR HX CUB I

X X

X

-19/PAB I

-5/PAB/EAST WALL.

X X

X OVHD I

-5/PAB/EAST WALL X

X X

OVHD I

8/PAB/SPRAY PUMP X

X X

AREA I

X X

X 8/PAB/PIPEWAY #3 I

X X

X 8/PAB/PIPEWAY #3 I

-5/PAB/RHR X

X X

PIPEWAY I

-5/PAB/RHR X

X X

PIPEWAY I

X X

X 8/PAB/SI PUMP AREA I

X X

X 8/PAB/Sl PUMP AREA I

X 46/PAB/CC HX AREA I

X G-02 ROOM I

X X

X 35/PAB/D-106 ROOF I

X X

X 44/CB/CR WEST I

PB PB PB PB PB PB PB PB PB PB PB PB PB SWEL2 SWEL2 SWEL2 SWEL2 SWEL2 SWEL2 SWEL2 SWEL2 SWEL2 PB PB POINT BEACH NUCLEAR PLANT, UNIT 2 1200114-R-002, REVISION 0 2

y 14 2

y 14 0

125V 14 0

125V 15 y

1 480V 1

y 2

480V 1

y 2

cv 5

y 2

cv 5

2 Sl 21a 0

VNDG 9

0 VNDG 9

0 SF 21b 0

SF 21b 0

SF 5

0 SF 5

0 SF 0

0 sw 8a 0

sw 8a 0

SF 21a 0

y 14 43/Y-01 43/Y-02 D-301 D-305 1B-42 2B-42 2P-002A 2P-002B 2T-013 W-012A W-012B W-012C W-012D HX-013A HX-013B P-012A P-012B SF-00785B SW-02927A SW-02927B SW-02930A SW-02930B SFP Y-204 B-48 2Y-01 RED 120V AC VITAL INST PNL PWR SUP TRANSFER SW X

X X

44/CB/CR WEST I

2Y-02 BLUE 120V AC VITAL INST PNL PWR SUP TRANSFER SW X

X X

44/CB/CR WEST I

26/CB/SWBD CHGR SWING BATIERY DISTRIBUTION PANEL X

X X

RM I

26/CB/D-305 BA TI SWING STATION BATTERY X

X X

RM I

480V MOTOR CONTROL CENTER PAB SAFEGUARDS X

X X

26/PAB/C-59 AREA I

480V MOTOR CONTROL CENTER PAB SAFEGUARDS X

X X

26/PAB/C-59 AREA I

CHARGING PUMP (Pump Only as Pressure 8/PAB/U2 CHG PUMP Boundary)

X X

X AREA I

CHARGING PUMP (Pump Only as Pressure 8/PAB/U2 CHG PUMP Boundary)

X X

X RM I

REFUELING WATER STORAGE TANK W/6 IMMERSION HTRS X

X X

U2F I

G-01 ROOM EXHAUST FAN X

X X

26/CB I

G-01 ROOM EXHAUST FAN X

X X

26/CB I

G-02 ROOM EXHAUST FAN X

X X

26/CB I

G-02 ROOM EXHAUST FAN X

X X

26/CB I

SPENTFUELPOOLHEATEXCHANGER 46/PAB/SFP HX AREA I

SPENT FUEL COOLING PUMP 46/PAB/SFP HX AREA I

P-9 HUT RECIRC PUMP SUCTION FROM 8/PAB/P-9 HUT AREA TRANSFER CANAL WEST I

HX-13A SFP HX INLET 46/PAB/SFP HX AREA I

HX-13B SFP HX INLET 46/PAB/SFP HX AREA I

HX-13A SFP HX OUTLET 46/PAB/SFP HX AREA I

HX-13B SFP HX OUTLET 46/PAB/SFP HX AREA I

SPENT FUEL POOL 46/PAB/SFP HX AREA I

YELLOW 120V INVERTER DISTRIBUTION 26/CB/CSR WEST PANEL X

X X

WALL I

Point Beach Nuclear Plant, Unit 2 1200114-R-002, Revision 0 Seismic Walkdown Checklist (SWC)

Sheet 1 of 2 Status: [YJ N U

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%

of SWEL items requiring such verification)?

2.

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

3.

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

4.

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

5.

Is the anchorage configuration consistent with plant documentation? (Note:

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 potentially adverse seismic conditions?

Yes Yes Yes Yes Yes Yes C-66

Point Beach Nuclear Plant, Unit 2 1200114-R-002, Revision 0 Seismic Walkdown Checklist (SWC)

Sheet 1 of2 Status: [Y] N U 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%

of SWEL Items requiring sUch verification)?

2.

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

3.

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

4.

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

5.

Is the anchorage configuration consistent with plant documentation? (Note:

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 potentially adverse seismic conditions?

Yes Yes Yes Yes Yes Yes C-86

Point Beach Nuclear Plant, Unit 2 1200114-R-002, Revision 0 Seismic Walkdown Checklist (SWC)

Sheet 1 of 2 Status: [YJ N U 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%

of SWEL Items requiring such verification)?

2.

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

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?

4.

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

5.

Is the anchorage configuration consistent with plant documentation? (Note:

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 potentially adverse seismic conditions?

Yes Yes Yes Yes Yes Yes C-116

Point Beach Nuclear Plant, Unit 2 1200114-R-002, Revision 0 Seismic Walkdown Checklist (SWC)

Sheet 1 of2 Status: [Y] N. U 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%

of SWEL Items requiring such verification)?

2.

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

3.

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

Some corrosion on SE corner baseplate anchor: washer and baseplate corner.

No Yes Yes 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:

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 potentially adverse seismic conditions?

Not Applicable Yes C-146

Point Beach Nuclear Plant, Unit 2 1200114-R-002, Revision 0 Seismic Walkdown Checklist (SWC)

Sheet 1 of2 Status: I:YJN u 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%

of SWEL Items requiring such verification)?

2.

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

3.

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

4.

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

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:

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 II thru bolts and one anchor welded to tan embed plate.

Calculation N-90-043, Rev. 0, Attachment 2 shows analysis for 518 11 mounting bolts for tank and 1 11 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 potentially adverse seismic conditions?

Yes Yes Yes Yes Yes Yes C-162

Point Beach Nuclear Plant, Unit 2 1200114-R-002, Revision 0 Seismic Walkdown Checklist (SWC)

Sheet 1 of2 Status*: [Y] N U 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%

of SWEL Items requiring such verification)?

2.

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

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?

4.

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

Minor cracks In grout are judged to be acceptable.

5.

Is the anchorage configuration consistent with plant documentation? (Note:

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 potentially adverse seismic conditions?

Yes Yes Yes Yes Yes Yes C-172

Point Beach Nuclear Plant, Unit 2 1200114-R-002, Revision 0 Area Walk-By.Checklist (AWC)

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

Instructions for Completing Checklist Sheet 1 of2 Status: [Y] N U 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 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 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 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 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 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 that could cause a fire In the area?

7.

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

Yes Yes Yes Yes Yes Yes Yes D-30

E Point Beach Nuclear Plant, Unit 2 1200114-R-002, Revision 0 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 Location Reason for Scheduled Component ID Description Inaccessibility Completion 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 Location Reason for Scheduled Component ID Description Inaccessibility Completion 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

v t e Letter Sequence Request
TAC:MF0161, (Approved, Closed)
Initiation Request, Request, Request Acceptance Administration Questions 2 August 2013 Answers Results Approval Other: ML13130A045, ML13312A911, ML14072A253
MONTHYEAR2013-02-05 [Table View]

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

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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

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