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{{#Wiki_filter:consumers Power                                                   David W. Rogers Plant Safety and Licensing Director POWERINii NllCHlliAN"S PROliRESS Palisades Nuclear Plant: 27780 Blue Star Memorial Highway, Covert, Ml 49043 July 7, 1993 Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 DOCKET 50-255 - LICENSE DPR PALISADES PLANT - REQUEST FOR RELIEF FROM SPECIFIC CODE REQUIREMENTS - SERVICE WATER SYSTEM LEAKAGE - ADDITIONAL INFORMATION Our July 1, 1993 letter submitted for NRC review and approval a relief request from certain provisions of Section XI of the ASME Boiler and Pressure Vessel (B&PV) Code. Attachment 2 to that letter, provided the calculation and drawing for the temporary non-Code repair for the 16-inch service water line.
{{#Wiki_filter:consumers Power POWE RI Nii NllCHlliAN"S PROliRESS Palisades Nuclear Plant:
In the same letter we indicated that the calculation and drawing for the temporary non-Code repair for the 4-inch service water line would be submitted under a separate cover letter, as soon as they were finalized. The attachment to this letter contains the calculation and drawing for the non-Code repair for the 4-inch service water line.
27780 Blue Star Memorial Highway, Covert, Ml 49043 July 7, 1993 Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 David W. Rogers Plant Safety and Licensing Director DOCKET 50-255 - LICENSE DPR PALISADES PLANT - REQUEST FOR RELIEF FROM SPECIFIC CODE REQUIREMENTS - SERVICE WATER SYSTEM LEAKAGE - ADDITIONAL INFORMATION Our {{letter dated|date=July 1, 1993|text=July 1, 1993 letter}} submitted for NRC review and approval a relief request from certain provisions of Section XI of the ASME Boiler and Pressure Vessel (B&PV) Code. to that letter, provided the calculation and drawing for the temporary non-Code repair for the 16-inch service water line.
David W. Rogers Safety and Licensing Director CC: Administrator Region Ill, USNRC Resident Inspector, Palisades Attachment 1301Z2 A CMS' ENER5Y COMPANY f/O'f1 11 I
In the same letter we indicated that the calculation and drawing for the temporary non-Code repair for the 4-inch service water line would be submitted under a separate cover letter, as soon as they were finalized.
The attachment to this letter contains the calculation and drawing for the non-Code repair for the 4-inch service water line.
David W. Rogers Safety and Licensing Director CC: Administrator Region Ill, USNRC Resident Inspector, Palisades Attachment 1301Z2 A CMS' ENER5Y COMPANY f/O'f1 11 I  


ATTACHMENT Consumers Power Company Palisades Plant Docket 50-255 REQUEST FOR RELIEF FROM SPECIFIC CODE REQUIREMENTS SERVICE WATER SYSTEM LEAKAGE ADDITIONAL INFORMATION July 7, 1993
ATTACHMENT Consumers Power Company Palisades Plant Docket 50-255 REQUEST FOR RELIEF FROM SPECIFIC CODE REQUIREMENTS SERVICE WATER SYSTEM LEAKAGE ADDITIONAL INFORMATION July 7, 1993  


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-ISADES NUCLEAR PLANT ANALYSIS CONT,NUATION SHEET
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    @*M--                              -ISADES NUCLEAR PLANT AKAL YSIS CONTINUATION SHEET Sheet
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:3P-o.33 /(o-cxe, V                  Rev # .-0'------
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Reference/Comment 2
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ANALYSIS CONTINUATION SHEET                    Sheet ~              Rev 1 ~O~--
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        ~. ANAL.,y'.SI~ (CoNTl!\/UGD )
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Form 3650 10-91  


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                                      ~SADES NUCLEAR PLANT ANALYSIS CONTINUATION SHEET         Sheet 8        Rev IO_
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Reference/Comment 2
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e.ISADES NUCLEAR PLANT 1- sP-on1re -OLe ANALYSIS CONTINUATION SHEET               Sheet q*  Rev# O,_~---
.ADES NUCLEAR PLANT ANALYSIS CONTINUATION SHEET ee SP- 03 Jl<O - Ck:>
Reference/Comment 3
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30 31 32 33 34 35 36 37 38 L--------------------------------------------------------------~
Form 3650 10-91


                                        -SADES NUCLEAR PLANT
                                                                    -    -SP-o J.3/(q -o~
ANALYSIS CONTINUATION SHEET        Sheet / /        Rev 1 -""O"'-------
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30                            -** .* -I 31 32 33 34 35 36 37 38 Form 3650 10-91
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Form 3650 10-91
 
2 3
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10 11 12 13 14 15 16 17
. 18 19 20 21 22 23 24 25 26 27 28 29 30 31 32 33 34 35 36 37 38
~SADES NUCLEAR PLANT ANALYSIS CONTINUATION SHEET E.-SP -03~1'2 -0~
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Reference/Comment L--------------------------------------------------------------~
Form 3650 10-91  


l J, A-SP-D3310-~
2 3
1.
4 5
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                                                                        / oF .:S Examiner ;C,Al.P~LL          J..JL L  L..S            Level    Jr        Date 6-~ -?3                               Sheet No.~u.1- o~
8 9
CONSUMERS POWER COMPANY NONDESTRUCTIVE TESTING SERVICES                              Examiner.Afi/,'J>    #ecK..sL l..                    Level __::iz=_      NOT Company _,C""-'--'. -=-*
10 11 12 13 14 15 16 17 18 19 20 21 22 23 24 25 26 27 28 29 30 31 32 33 34 35 36 37 38
                                                                                                                                                                          #L.*  _,,~=-=P~-- - - - - - -
-SADES NUCLEAR PLANT ANALYSIS CONTINUATION SHEET
THICKNESS MEASUREMENT                                Proiect No.~'19.3 /.5 ~~~s~
-SP-o J.3/(q -o~
EXAMINATION REPORT Job Location    At ,:s...,~t:.s AJu~Lbf,e_ A."'~ r                          Total Hours Worked      ~/A
Sheet / /
~**--------------.J.:::.::....:====~~======~==~::::::::::::::::::::::::::::::::===-__:_:::=-:~~if'J';;;.,MJ~=-==z=================4 NOT Procedure N.PT- ~r- o:L                                            Rev -...5 - - Ultrasonic Equipment4u...1n,-csd4'>&#xa3; f Serial No...17&#xa5;- ,po..3..S:.S Cal Due ?-/0 -:&1
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M~(.,).~GMIZ'l\\JT IEXAMJNA..TICYV
                                    ...______________                                      Ultrasonic Couplant        S&deg;*N11 rAAc=L              fo              Batch Number              t? 9 /O LY
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ITEM No.
MIN.
QUAN                       BILL OF MATERIALS I        PIPE SLEEVE 5' DIA. SCH. B0 <A-106 GR. 81 CUT LATERALLY 2 PLCS.
ITYP.I ELEVATION LOOKING WEST LEG SIZE TO BE INCREASED BY SIZE OF THE GAP BETWEEN SLEEVE ANO PIPE HB-23-4' ITEM No.
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B A
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REV.
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THREAOOLET 8-3X
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A~* 4-           e         TECHNICAL BEYIEV CHEcgA Proc No 9.11 Attachment 5 Revision 5 EA - SP- o 1 ~I le- O(. REV.   .o           Page 1 of 1 This checklist provides guidance for the review of engineering analyses.
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Answer questions Yes or No, or N/A if they do not apply. Document all corrments on a 3110 Form. Satisfactory resolution of corrments and completion of this checklist is noted by the Technically Reviewed signature on the Initiation and Review record block of Fona 3619.
4-e TECHNICAL BEYIEV CHEcgA EA -
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. o Proc No 9.11 Revision 5 Page 1 of 1 This checklist provides guidance for the review of engineering analyses.
: 3. Are all inputs and assumptions valid and the basis for their use documented?                                             '(
Answer questions Yes or No, or N/A if they do not apply.
: 4. Is Vendor information used as input addressed correctly in the analysis?                                                       ~
Document all corrments on a 3110 Form.
: 5. If the analysis argument departs from Vendor Infonaation/Reconaendations, is the departure justification documented?                                         NA.
Satisfactory resolution of corrments and completion of this checklist is noted by the Technically Reviewed signature on the Initiation and Review record block of Fona 3619.
: 6. Are assumptions accurately described and reasonable?             '{
: 1.
: 1. Has the use of engineering judgement been docW11nted and Justified?
Have the proper input codes, standards and design principles been specified?
: 8. Are all constants, variables and formulas correct and properly applied?                                                   '(
: 2.
: 9. Have any minor (ins1gnif1cant) errors been 1dentif1ed? If yes; Identify on the 3110 Form andljusttfy their                   y instgniftcance.                     (
Have the input codes, standards and design principles been properly applied?
: 10. Does analysts involve welding? If Yes; verify the following tnformatton ts accurately represented on the analysts drawtnt (Output doc&1111nt).
: 3.
Are all inputs and assumptions valid and the basis for their use documented?
: 4.
Is Vendor information used as input addressed correctly the analysis?
: 5.
If the analysis argument departs from Vendor Infonaation/Reconaendations, is the departure justification documented?
: 6.
Are assumptions accurately described and reasonable?
: 1.
Has the use of engineering judgement been docW11nted and Justified?
: 8. Are all constants, variables and formulas correct and properly applied?
: 9.
Have any minor (ins1gnif1cant) errors been 1dentif1ed?
yes; Identify on the 3110 Form andljusttfy their instgniftcance.
(
: 10.
Does analysts involve welding? If Yes; verify the following tnformatton ts accurately represented on the analysts drawtnt (Output doc&1111nt).
* Type of Veld
* Type of Veld
* Size of Veld
* Size of Veld
Line 450: Line 676:
* Thfclcness of Material Being Joined
* Thfclcness of Material Being Joined
* Loenion of Weld(s)
* Loenion of Weld(s)
* ApprQpr1ate Weld Symbology
* ApprQpr1ate Weld Symbology in If (Y, N,
: 11. Has the objective of the analysts been *t?                           '1
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: 12.
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Latest revision as of 07:55, 6 January 2025

Provides Calculation & Drawing for Temporary non-code Repair for 16 Inch Svc Water Line
ML18058B922
Person / Time
Site: Palisades 
Issue date: 07/07/1993
From: Rogers D
CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.)
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NUDOCS 9307150160
Download: ML18058B922 (22)
v • d • e


Text

consumers Power POWE RI Nii NllCHlliAN"S PROliRESS Palisades Nuclear Plant:

27780 Blue Star Memorial Highway, Covert, Ml 49043 July 7, 1993 Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 David W. Rogers Plant Safety and Licensing Director DOCKET 50-255 - LICENSE DPR PALISADES PLANT - REQUEST FOR RELIEF FROM SPECIFIC CODE REQUIREMENTS - SERVICE WATER SYSTEM LEAKAGE - ADDITIONAL INFORMATION Our July 1, 1993 letter submitted for NRC review and approval a relief request from certain provisions of Section XI of the ASME Boiler and Pressure Vessel (B&PV) Code. to that letter, provided the calculation and drawing for the temporary non-Code repair for the 16-inch service water line.

In the same letter we indicated that the calculation and drawing for the temporary non-Code repair for the 4-inch service water line would be submitted under a separate cover letter, as soon as they were finalized.

The attachment to this letter contains the calculation and drawing for the non-Code repair for the 4-inch service water line.

David W. Rogers Safety and Licensing Director CC: Administrator Region Ill, USNRC Resident Inspector, Palisades Attachment 1301Z2 A CMS' ENER5Y COMPANY f/O'f1 11 I

ATTACHMENT Consumers Power Company Palisades Plant Docket 50-255 REQUEST FOR RELIEF FROM SPECIFIC CODE REQUIREMENTS SERVICE WATER SYSTEM LEAKAGE ADDITIONAL INFORMATION July 7, 1993

_ --ALISADES NUCLEAR PLANT

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CONSUMERS POWER COMPANY NONDESTRUCTIVE TESTING SERVICES THICKNESS MEASUREMENT EXAMINATION REPORT Examiner ;C,Al.P~LL J..JL L L..S Examiner.Afi/,'J> #ecK..sL l..

Proiect No.~'19.3 /.5 ~~

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Level Jr Date 6-~ -?3 Sheet No.~u.1-o~

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NOT Company _,C""-'--'. #L.*

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Job Location At,:s...,~t:.s AJu~Lbf,e_ A."'~ r Total Hours Worked ~/A

~**--------------.J.:::.::....:====~~======~==~::::::::::::::::::::::::::::::::===-__:_:::=-:~~if'J';;;.,MJ~=-==z=================4 Ultrasonic Equipment4u... 1n,-csd4'>£ f Serial No...17¥-

,po..3..S:.S Cal Due ?-/0 -:&1 NOT Procedure N.PT- ~r-o:L Rev...5 ---

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Reterence Documents --~,..M-'...__ ___________ _

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Search Unit Size/Fr~uency

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Serial Number / U 0 9 Ultrasonic Couplant S°*N11 rAAc=L fo Batch Number t? 9 /O LY Mechanical Equipment 1.M Serial No.

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2" 3

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ITYP.I ELEVATION LOOKING WEST LEG SIZE TO BE INCREASED BY SIZE OF THE GAP BETWEEN SLEEVE ANO PIPE HB-23-4' ITEM No.

I 2

3 4

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QUAN BILL OF MATERIALS PIPE SLEEVE 5' DIA. SCH. B0 <A-106 GR. 81 CUT LATERALLY 2 PLCS.

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4-e TECHNICAL BEYIEV CHEcgA EA -

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REV.

. o Proc No 9.11 Revision 5 Page 1 of 1 This checklist provides guidance for the review of engineering analyses.

Answer questions Yes or No, or N/A if they do not apply.

Document all corrments on a 3110 Form.

Satisfactory resolution of corrments and completion of this checklist is noted by the Technically Reviewed signature on the Initiation and Review record block of Fona 3619.

1.

Have the proper input codes, standards and design principles been specified?

2.

Have the input codes, standards and design principles been properly applied?

3.

Are all inputs and assumptions valid and the basis for their use documented?

4.

Is Vendor information used as input addressed correctly the analysis?

5.

If the analysis argument departs from Vendor Infonaation/Reconaendations, is the departure justification documented?

6.

Are assumptions accurately described and reasonable?

1.

Has the use of engineering judgement been docW11nted and Justified?

8. Are all constants, variables and formulas correct and properly applied?
9.

Have any minor (ins1gnif1cant) errors been 1dentif1ed?

yes; Identify on the 3110 Form andljusttfy their instgniftcance.

(

10.

Does analysts involve welding? If Yes; verify the following tnformatton ts accurately represented on the analysts drawtnt (Output doc&1111nt).

  • Type of Veld
  • Size of Veld
  • Material Betnt Joined
  • Thfclcness of Material Being Joined
  • ApprQpr1ate Weld Symbology in If (Y, N,

'i

'(

~

NA.

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y

11.

Has the objective of the analysts been *t?

'1

12.

H*ave adlltnistrattve requirements such as nUllberint and.

format been satisfied?

Y N/A)

MICW#'I :

FfMll NUCLEAR OPERATIONS DEPARTMENT A1Tl40f1"1tJNI S-Document Review Sheet l10<ument Title~~ /10N-ColJd ~/A

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