ML20236T198
| ML20236T198 | |
| Person / Time | |
|---|---|
| Site: | Farley  |
| Issue date: | 11/23/1987 |
| From: | Mcdonald R ALABAMA POWER CO. |
| To: | NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM) |
| Shared Package | |
| ML20236T199 | List: |
| References | |
| NUDOCS 8712010070 | |
| Download: ML20236T198 (9) | |
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4 Alabama Power Company '.
.t 600 North 18th Street Post Office Box 2641.
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Birmingham, Alabama 35291-0400
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. Telephone 205 250-1835 j
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- $n";,Tc,"g,,,,n, AlabarTia Power.
Docket No. 50-348 the southem electnc system
'l 10CFR50.55a(g) l 1
1 November 23, 1987 1
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l U. S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, D. C.
20555 l
Gentlemen:
1 Joseph M. Farley Nuclear Plant - Unit 1 Second Ten-Year Interval Inservice Inspection l
Program for ASME Code Class 1, 2 and 3 Components
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By letter dated May 27, 1987, Alabama Power Company submitted the Inservice Inspection (ISI) Program for the-Second Ten-Year Interval of Unit 1 j
operation. During a conference call of November 4,1987,- Alabama Power i
Company informed the NRC that several: technical changes and editorial corrections to this program were required. The-ISI Program has-been revised and is herewith submitted as Enclosure 1 for final NRC. review -and granting of relief requests. This program supersedes the program previously, submitted by the May 27, 1987 l e tter.
A detailed summary of these changes is provided for convenience. The technical changes are summarized as
'l follows:
l 1.
A detailed listing of Class 3 systems or portions of systems whose component supports are exempt from visual examination is included in Section 4.1.2.
1 2.- Exemption of open-ended portions of Class 3 systems from hydrostatic test requirements was added as Section 4.1.3.
3.
The River Water System was deleted from the Class 3 table and Relief Requests RR-31.and RR-35 based on a design evaluation which concluded that the system was optionally classified to Class 3 design requirements. Therefore, this system is not subject to examination under the' requirements of Section XI based lon the provisions of-paragraph IWA-1320(e).
Deletion' of the' River Water System from the Inservice Testing Program was also.
discussed in APCo's. submittal of September' 30, 1987 and additional justification for this' deletion'was provided therein.
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U. S. Nuclear Regulatory. Commission November 23, 1987 Page-2 4.
The shell sides of the Excess Letdown and Reactor Coolant Drain Tank Heat Exchangers.were deleted from-the Class 3 table based on a design' evaluation which concluded. that these portions' of the CCW System were optionally -
classified to Class 3 design requirements. Therefore, these portions of the CCW System are not subject to examination under the requirements of Section XI based on the provisions of paragraph IWA-1320(e).
5.
The Spent Fuel Pool Cooling Heat Exchangers were deleted from Relief Request RR-36 and a separate Relief Request RR-44 was added which proposes a. different alternative examination method.
6.
The Post-Accident Containment Vent and Sampling System was added to the Class 3 table.
The NRC requested a listing correlating the First Ten-Year Interval ISI Program relief requests to the Second Ten-Year. Interval ISI Program relief requests. This list is provided as Enclosure 2.
Since the information provided herein supersedes that previously submitted by the May 27, 1987 letter, no additional application fees are required.
It is respectfully requested that the relief requests included in Enclosure 1 by granted by December 1,1987.
If there are any questions, please advise.
Respectfully submitted, ALABAMA POW PANY (3 4by R. P. Mcdonald RPM / STB:csl-2 Enclosures cc:
Mr. L. B. Long, w/o enclosure Dr. J. N. Grace, w/1 enclosure Mr. E. A. Reeves, w/1 enclosure Mr. W. H. Bradford, w/o enclosure
y ENCLOSURE:1 1
FNP-1.-M-043 Summary of Changes-to Draft Revision 0'of the -
J. M. Farley Nuclear Plant'. Unit No.1' Inservice Inspection Program for. ASME Code. Class 1,' 2 and 3 Components-
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Page No./ Description / Reason. for Change s
1.
Page 1-1, Section 1.1 Scope, last paragraph: Added"1975", the year of the ASME Section XI Code used for Class.2. exemption criteria, between I
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words'" Summer" and " Addenda" in the last sentence.
Editorial -
clarification.
l 2.
Page 1-2, Section 1.7 Methods of Examination: Added. requi rements-for :
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training of personnel performing visual: examinations outside the scope of NDE (VT-2 and VT-3).
Editorial clarification.
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3.
Page 1-3, Section 1.7.4 Liquid Penetrant: Deleted the word "usually" between words "will" and "be."
Editorial correction.
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4.
Page 1-5, Section 1.7.6, last paragraph:
Changed the words " inspectors" and " inspections" to " examiners" and'" examinations", in the first sentence. Editorial correction.
5.
Page 2-8, Table B-E, Examination Method:. Added the number "1" after the word " Method." Editorial omission.
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6.
Page 3-1, paragraph 3.1.1 D: Changed line numbers 8"'HCB-142,12" i
HCB-52, and 16" HCB-142 to 8" HCB-42,12" HCB-152, and 16" HCB-42, respectively.
Editorial correction.
7.
Page 3e20 Table C-C, Item No. C3.30: Added supplemental "VT-3" under "Sur." to reflect the commitments of Relief Request-20.
Editorial 9
omission.
8.
Page 4-1, Exem)t Components: Added reference "IWD-5223" and the applicable ASME Code reference. Editorial omission.
9.
Page 4-2, Section 4.1.2, second paragraph:
Deleted the follo' wing components:
Post-accident combustible gas control system -
Line numbers - 8" HCC-267 two loops of hydrogen dilution for discharge.
6" HCC-239 Added the following exempt components:
Service Water System Components - Control Room A/C Condensers (2)-tube sido,
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Component Cooling Water
.I Components - CVCS Letdown HX. - shell side Spent-fuel Pool HX. (2) - shell side Post-accident combustible gas control system.
I Line number - 6" HCC-250 Technical correction.
10.
Page 4-2,. paragraph 4.1.3: Added new paragraph to address exemptions from hydrostatic testing for the Post-Accident Combustible Gas Control System. Technical correction.
11.
Page 4-5, Table D-8, River Water Systeml: Deleted entire River Water
-j Syste:n from scope of ISI.
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12.
Page 4-9, Table D-B,. Item No. D2.10: Deleted CVCS Excess Letdon HX. -
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shell side from scope of ISI.
13.
Page 4-10, Table D-8, Item No. D2.10: Deleted RC Drain Tank HX. - shell side from scope of ISI.
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14.
Page 4-11, - Table D-B,. Item D2.10:
Corrected spelling of " Storage" in
" Condensate Storage Tank." Editorial correction.
15.
Page 4-11, Table D-8, Item D2.10: Add.the required components of tne Post-Accident CTMT Venting and Sampling System. Technical-. correction.
j 16.
Page 4-16, Table D-C, Item No. D3.10:. Corrected ASME Code. references under "Tegt and Examination Requirements" column from "IWD-5222 " to 5
"IWD-52213. " Editorial correction.
17.
Page 6-4, RR-36, Examination Area: Revised description to apply only to component cooling water heat exchangers.
Revised scope of relief.
18.
Page 6-4, RR-44, Examination Area: Added new Relief Request to listing for spent fuel pool cooling heat exchangers.
Additional Relief Request.
19.
Page 6-14, RR-9, Component or Relief Area:
Corrected weld numbers referenced on drawing ALAl-2100B from "1 through 6" to "9 through 14."
Editorial correction.
20.
Page 6-23, RR-14, Component or Relief Area: Corrected drawing reference from "ALAl-TTOP to "ALA1-1100A and ALAl-1300." Editorial correction, i
21.
Page 6-44, RR-31 : Deleted all references to River Water System.
Removed from ISI scope.
22.
Page 6-46, RR-33: Deleted all references to River Water System.
Removed from ISI scope.
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Page 6-46,. RR-33; Component or. Relief Area:. Corrected drawing reference :
)1 for component cooling water drawing D351103 to add sheet 3.
Editorial omission..
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24.
Page 6-48, RR-35: Deleted all: references to River Water System.
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Removed from ISI scope.
j 25.
Page 6-49, RR-36, Component or Relief Area: Corrected component coolingL water heat exchanger TPNS-No. - reference from "HX-Q1P7 to "HX-Q1P17."
-Editorial correction.
I 26.
Page 6-49, RR-36, Component or Relief Area:' Removed spent fuel pool cooling heat exchangers from Relief Request.
See RR-44.
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- 27.
Page 6-54, RR-40, Component or Relief Area: Correct'ed reference for
.i drawf ug 0351107 from " sheet 1 of.1" to " sheet 1 of 3."
Editorial
..y Correction.'.
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l 28.
Page 6-58, RR-44: New Relief Request to perform in-line monitoringLfor l
tube leakage from the spent fuel pool cooling heat exchangers.
Improved.
' detection capability.
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i EllCLOSURE 2 CORRELATION OF FIRST AllD SECOND TEN-YEAR INTERVAL l
ISI PROGRAM RELIEF REQUESTS FIRST INTERVAL SECOND INTERVAL DESCRIPTION 2.5.1 RR-8 Volunetric examination of the Reactor Vessel bottom head meridional weld 2.5.3 RR-9 Volumetric examination of nozzle-to-vessel welds in the Pressurizer l
2.5.4 RR-10 Volumetric examination of primary nozzle-to-safe end welds in Steam j
i Generators 2.5.7 RR-13 Volumetric examination of pressure retaining branch connection welds in Class 1 piping
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I 2.5.14 RR-14 Volumetric examination of the Reactor t
Vessel flange ligaments 2.5.15 RR-15 Visual examination of the Reactor Coolant Pump internal pressure boundary surfaces l
l 2.5.17 RR-16 Visual examination of the internal i
pressure boundary surfaces of Class 1 valves 2.5.18 RR-11 Volumetric examination of primary nozzle inner radiused sections in Steam Generators 3.5.1 RR-18 Volumetric examination of pressure retaining welds in the Regenerative Heat Exchanger 3.5.3 RR-19 Volumetric examination of pressure retaining welds in thin wall Class 2 pressure vessels j
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Page 2 of 4
.r FIRST INTERVAL SECOND INTERVAL DEXrIPTION s
3.5.7 RR-20 Surface examination of integrally
. welded attachments to Class 2 Charging Pumps
'3.5.8 RR-22 Hydrostatic testing of portions of Class 2 components at reduced pressure 3.5.8 RR-40 Hydrostatic testing of all-Class 2 branch pipe lines from VCT to the' first valve i
I 3.5.9 RR-23 Hydrostatic testing of portions of Class 2 piping to the connecting Class 1 test requirements-3.5.11 RR-24 Hydrostatic testing of the relief-line I
discharge headers to the Pressurizer l
Relief Tank (line No. HCB-62) 3.5.12 RR-25 Hydrostatic test for the Class 2 Reactor Vessel flange seal leak-off j
line (line No. CCB-36) 3.5.13 RR-26 Hydrostatic testing of portions of Class 2 piping systems isolated from the test boundaries by closed check valves 3.5.14 RR-27 Hydrostatic test for Class 2 waste gas drain filter line to Volume Control Tank (line NO. HCB-92) 3.5.17 RR-29 Hydrostatic testing of boron injection recirculation discharge piping (line I
No. CCB-62) l 3.5.18 RR-23 Hydrostatic testing of portions of Class 2 piping to the connecting Class 1 test requirements
9 Page 3 of 4 FIRST INTERVAL SECOND INTERVAL DESCRIPTION 3.5.19 RR-30 Hydrostatic testing of the secondary portion of the Steam Generator (4-hour hold time) 4.1.1 RR-31 Visual (VT-2) examination for leakage of Class 3 Service Water Pumps 4.1.2 RR-32 Visual -(VT-2) examination for leakage in encased piping.in the Spent Fuel Pool Cooling System 4.1.3 RR-33 Hydrostatic testing of portions of Class 3 piping and components which operate continuously during all modes -
of plant operation b
4.1.3 RR-34 Hydrostatic testing of Class 3 spray additive lines in the Containment Spray System 4.1.3 RR-38 Hydrostatic testing of Class 3 portions of Auxiliary Steam System piping 4.1.4 RR-33 Hydrostatic testing of portions of Class 3 piping and components which operate continuously during all modes of plant operation 4.1.5 RR-33 Hydrostatic testing of portions of Class 3 piping and components which operate continuously during all modes -
of plant operation 4.1.6 RR-35 Hydrostatic testing of Class 3 buried piping in.the Service Water System 4.1.7 RR-33 Hydrostatic testing of portions of Class 3 piping and components which 4
operate continuously during all modes I
of plant operation
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