ML20154F039

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Requests Granting of Two Addl Relief Requests Involving Rev of Technical Requirements for Hydrostatic Test Pressure by 890307.Required Fees for Review of Inservice Insp Program Submitted by Ltr
ML20154F039
Person / Time
Site: Farley Southern Nuclear icon.png
Issue date: 09/09/1988
From: Hairston W
ALABAMA POWER CO.
To:
NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM)
References
NUDOCS 8809190229
Download: ML20154F039 (28)
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Text

A!:bt.ma Pe $f Company 600 North itr n Street Post Offace Box 2641 B4rmingham Alabama 352914400 T,,tephone 205 250-1837 W. G. Hairsson,111 Senks v<e President Nuclear Operations AlabamaPower the sourhem ekttrc system SEP 0 9 en 10CFR50.55a(g) l 1

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Docket No. 50-348 U. S. Nuclear Regulatory Commission Attention: Document Control Desk Vashington, D. C. 20555 Centlement Joseph M. Farley Nuclear Plant - Unit 1 Second Ten-Year Interval Inservice Inspection Program for ASME Code Class 1, 2 and 3 Components Alabama Pover Company previously submitted Revision 0 of the subject hservice Inspection (ISI) Program to the NRC by letter dated November 23,

  1. 87. By letter dated December 10, 1987, the NRC granted interim approval G r the relief requests submitted with Revision 0 of the ISI Program.

M 1oving the implementation of this program on December 1, 1987, two a bitional relief requests requiring NRC approval and numerous additional chu ges have been identified. These are being incorporated in Revisions 1 and 2 to the subject program and are included as Enclosures 1 and 2, respectively. The cover sheat for each enclosure summarizes the changes.

Revistori 1 is being submitted for information purposes as it was previously issued and contains only editorial changes which clarify the application of the ASME Code requirements to the Farley Nuclear Plant ISI Program.

Revision 2 also contains editorial changes ar. vell as revisions to relief requests RR-1, RR-26, RR-30 and RR-34. These changes incorporate a component description, line number and several subscripts which vere previously omitted. Finally, Revision 2 adds two new relief requests concerning the performance of hydrostatic tests.

Relief request RR-45 concerns the hydrostatic test pressure required by the ASME Code for certain Class 2 and 3 low pressure components which have a significant change in elevation.Section XI, IVC-5222(a) and IVD-5223(a) specify the minimum hydrostatic test pressure for Class 2 and 3 systems, respectively. IVA-5265(b) requires that the imposed pressure on any component, including static head, not exceed 106% of the specified system test pressure. In certain lov pressure systems which have significant elevation changes, setting the system test pressure at the highest point of the system equal to the minimum code required test pressure vill cause the pressure at the lowest point in the system to exceed 106% of the system test pressure due to static head. Since this is an unnecessary challenge to component integrity, the system test pressure vill be set to approximately 106% at the lovest point in the systee to meet the f7 0809190229 890909 sl PDA ADOCK 05000340 0 PNU

U. S. Nuclear Regulatory Commission Page 2 i

requirement of IVA-5265(b). Therefore, the system test pressura sctually achieved in the higher elevations of the system may not in all case ).eet the minimum test pressures required by IVC-5222(a) and IVD-5223(b!. 14e actual test pressure achieved vill, however, be in excess of the vo w.i operating pressure. This vill permit verification of structural integrity

through satisfactory performance of the hydrostatic test without unnecessary challenges which could occur if components were over-pressurized.
Relief request RR-46 concerns the schedular requirements of the ASME Code for performance of hydrostatic tests.Section XI, Tables IVC-2500-1 and IUD-2500-1, require that performance of hydrostatic tests during subsequent intervals be scheduled during the same inspection period used in the previous interval or that hydrostatic tests be deferred to the end of the ten-year interval. D'. ' 8ng the first ten years of operation, Farley Nuclear Plant deferrsd a number of hydrostatic tests to near the end of the interval. To more eveni' distribute the performance of tests during the j second interval, Alabama Power Company desires to reschedule the tests to be performed more equally during each of the three inspection periods. In no case vould the performance of any given test during the second interval i be scheduled more than approximately ten years from the date that the first j interval test was completed. It should be noted that this relief is schedular and all code required hydrostatic tests as described in the ISI j Program Wil be performed.

f 1 It is respectfullp requested that the reliefs included in Revision 2 of the i ISI Program be granted by March 7, 1989. The required fees for review of j the ISI Program vere submitted by letter dated May 27, 1987; therefore, no

, additional fees are included.

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Respectfully Submitted i

i ALABAMA PG'wdR COMPANY l W.A k h nc~

V. G. Hairston, III j

l VGH/ STB : p r-8. 27 Enclosures

! cci Mr. L. B. Long j Dr. J. N. Grace

Mr. E. A. Reeves
Mr. G. F. Daxvell l

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bct Mr. Bill M, Guthrie Mr. R. P. Mcdonald Mr. J. D. Woodard Mr. J. W. McGowan Mr. D. N. Morey w/1 enclosure

! Mr. W. B. Shipman l

Mr. R. D. Hill Mr. C. D. Nesbitt Mr. R. d. Berryhill Mr. Scott Fulmer Mr. D. B. Hartline w/l enclosure Mr. D. E. Mansfield Mr. J. E. Gatlington Mr. K. W. McCracken Mr. D. M. Varner Mr. J. R. Crane Mr. K. C. Gandhi Mr. J. T. Brantley Mr. D. E. Dutton Mr. T. N. Epps w/1 enclosure Mr. G. Johnson w/l enclosure Ceaunitment Tracking System (2)

FNP Document Control i rile: K-22.1 l

ENCLOSURE 1 TNP-1-H-043

' Sumary of Revision 1 to the J. M. Farley Nuclear Power Plant Unit No.1.

- Second Ten Year Inservice Inspection Program for ASME Code Class 1, 2, and 3 Components.,

Page No./ Description,Heason for Change

1. Page 1-3, Section 1.7.1: Added "as amended by Code Case N-98." to end of -

first paragraph per TCN OA. To officially incorporate the prt. visions of ASME Section XI Code Case N-98 as allowed by Regulatory Guide 1.147, Rev. 4.

2. Page 1-3, Section 1.7.6: Corrected word "lead" to "load" per TCN OA, Editorial correction.

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FNP-1-M-043 The 1974 Edition of Section XI of the ASME Boiler and Pressure I Vessel Code, with Summer 1975 Addenda, Appendix I, was used for the design of the existing ultrasonic calibration blocks for ferritic vessels 2-1/2 inches and greater in wall thickness.

Existing'c'alibration blocks for piping and thin-w&iled vessels under 2-1/2 inches in wall thickness were designed to the 1974 Edition of Section V, with Summer 1975 Addenda, Article 5, as l amended by Code Case N-98. l Because of the impracticality of some of the requirements of Article 5 of Section V, the 1977 Edition of Section XI, Appendix III was also used for guidance. This provided alternative machined notches for reference reflectors in lieu of side-drilled holes.

1.".2 RADIOGRAPHY Radiographic techniques will be used to supplement ultrasonic examination as required.

1.7.3 EDDY CURRENT Eddy current examinations will be performed on the steam generator tubing in accordance with the provisions of Appendix IV of Section XI and the plant Technical Specifications.

1.7.4 LIQUID PENETRANT

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Dye penetrant examinations will be used whenever a surface examination is required on nonferrous components.

1.7.5 MAGNETIC PARTICLE Magnetic particle tests will usually be used when surface examination of ferrous components is required.

1.7.6 VISUAL The following visual examinations will be employed as appropriate:

  • VT-1: To detect detrimental condition (s) of parts, components, or on examined surfaces.
  • VT-2: To locate evidence of leakage duzing a system or functional test.
  • VT-3: To determine the general mechanical and structural condition of components and their supports, and also to determine conditions that I could affect operability or functional adequacy of snubbers, and constant load and spring type l supports.

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03801 1-3 Rev. 1

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FN P-1 -M-043 Sumary of Revision 2 to the J. M. Farley Nuclear Power Plant Unit 1 Second Ten-Year Inservice Inspection Program for ASME Code Clast 1, ?, and 3 Components Page No./ Description / Reason fcr Change
1. Page 1-2, Section 1.7: Added training and examination requirement for personnel perfoming nondestructive examination methods other than those covered by SNT-TC-1A per APC letter FNP-88-0502 dated 7/8/88 from D. N.

Morey to J. D. Woodard. Clarification.

2. Pages 1-3 and 1-4: Sections 1.7.1 and 1.7.6 (VT-3) relocated to pages 1-3 arid 1-4 respectively. Editorial .
3. Pace 3-7: Ltdwn. H.X. , C2.33; Page 3-8: Ex. Ltdwn. H.X. , C2.33; Page 3-9: Regen. H.X. , C2.33; Page 3-10: S.W.R. Fitr. , r2.33; Page 3-11 : VCT, C2.33; Page 3-12: Ltdwn. Reht. H.X. , C2.33; Page 3-12 : S.W. H.X. , C2.33; Page 3-13: S.G. , C2.33; Page 3-14: R.C. F1tr. , C2.33; Page 3-15: Ltdwn.

Delay Tks., C2.33; Page 3-16: Ex. Ltdwn. Delay Tks., C2.33; Page 3-16:

B.I.T., C2.33; Deleted YT-2 examinations per APC letter FNP-88-0502 dated 74/88 f rom D. N. Morey to J. D. Woodard. Not applicable.

4 Page 3-8 and 3-9, Re anerative Heat Exchangers: Changed word "Exchangers" to " xc anger" per APC letter FNP-88-0502 dated 7/8/88 f rom D. N. Morty to J. D. Woodard. Editorial correction.

5. Page 3-16, Boron Injection Tank: Deleted comment "N/A to FNP".

Editorial cerection.

6 Page 6-4, Added new Relief Requests RR-45 and RR-46 per APC letter FNP-88-0502 dated 7/8/88 f rom D. N. Morty to J. D. Woodard.

7. Page 6-5, Component or Relief Arta: Added calibration block AFR-7 for examination of the Boron Injection Tank and also added Boron Injection Tank to applicability for calibration block ALA-RV-1. Examination of component during second ten-year interval using existing calibration blocks.
8. Page 6-39, Component or Relief Arec: Changed "no." to "nos." and added line HCB-99 per AFC letter FNP-88-0502 dated 7/8/88 from D. N. Morey to J. D. Wooda rd. Omission.
9. Page 6-43 Basis for Relief: Changed "P" to "Pd" per APC letter FNP-88-0502 dated 7/8/88 f rom D. N. Morey to J. D. Woodard. Editorial omission.
10. Page 6-43, Alternate Examination: Chinged "P" to "Psy" and "Pd " per APC letter FNP-88-0502 dated 7/8/88 f rom D. N. Morey to J. D. Woodard.

Editorial omission.

Page 1 of 2

FN P-1 -M-043

11. Page 6-47, Basis for Relief: Change "P" to "P FNP-88-0502 dated 7/8/88 from D. N. Morey to JIy" per D. Wooda rd. APC letter Editorial omission.
12. Page 6-59, RR-45 : New Relief Request to provide for the pressure differential that is evident In low pressure systems during system hydrostatic testing when the system has a large change in elevation per APC letter FNP-88-0502 dated 7/8/88 f rom D. N. Momy to J. D. Woodard.

Field encountered pmblem area.

13. Page 6-60, RR-46: New Relief Request to provide for a more even 1 distribution of system hydrostatic tests between the three periods during '

the second interval per AFC letter FNP-88-0502 dated 7/8/88 from D. N.

Morey to J. D. Woodard.

14 Page 7-3, Items 14 thru 17: Ad6 additional refennce letters per APC l letter FNP-88-0502 4ted 7/8/E8 f rom D. N. Morey to J. D. Woodard.

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i FN P-1 -M-043 mqui mwnts. The component design codes remain as stated in the Final Safety Analysia Report (FSAR).

1.4 SUBSEQUENT IS! Mt0 GRAM REVISIONS In accordance with the existing regulations of 10 CFR 50.55a, the inservice examination program for Class 1, 2, and 3 components will be reviewed near the end of each 120-month interval. At this time the pmgram will be modified, as required, to bring it into corpliance with the latest NRC-appmved version of Section XI.

1.5 RESPONSIBILITY

! Alabama Power Company bears the overall responsibility for the perfomance of the inservice examinations. Certain nondestmetive examinations may be

, perfonned by a qualified examination agency. The msults of such examinations would be mported to Alabama Pbwer Company for final evaluation and disposition.

, 1.6 RECORDS Records and documentation of all infomation and inspection results, which

provide the basis for evaluation and which facilitate comparison with results from pmvious and subsequent inspections, will be maintained and will be available for the active life of the plant in accordance with Section XI, IWA-6000.

I 1.7 METH005 0F EXAMINATION The method of examination planned for each area is delineated in subsequent i sections. Mrsonnel perfoming nondestructive examinations will be trained in j accordance with the American Society for Nondestmetive Testing (ASNT) l "Recomended Practice SNT-TC-1 A, Supplements and Appendices," as applicable

for the technique and method used. For methods not covend by SNT-TC-1 A, personnel shall be trained to comparable levels of competence by subjection to comparable examinations on the particular method involved, e.g. VT-1.

! hrsonnel perfoming visual examinations outside the scope of nondestructive examinations shall be trained to the mquimments of ANSI N45.2.6 l

"Qualifications of Inspection, Examination, and Testing krsonnel for Nuclear Powe r Pl ant" .

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FN P-1 -M-043

1. 7.1 ULTRASONIC Ultrawnic examir.ations will be conducted in accordance with the pmvision of Appendix III of Section XI and Articles 4 and 5 of Section V as required by Paragraph IWA-2232.

The 1974 Edition of Section XI of the ASME Boiler and Pressure Vessel Code, with Summer 1975 Addenda, Appendix I, was used for the design of the existing ultrasonic calibration blocks for ferritic vessels 2-1/2 inches and gmater in wall thickness. Exiting calibration blocks for piping and thin-walled vessels under 2-1/2 inches in wall thickness were designed to the 1974 Edition of Section V, with Sumer 1975 Addenda, Article 5, as amended by Code Case N-98. .

Because of the impracticality of some of the requimments of Article 5 of Section V, the 1977 Edition of Section XI, Appendix !!! was also used for guidance. This provided alternative machined notches for mfennce mflectors in lieu of side-drilled holes.

1. 7. 2 RADIOGRARiY Radiographic techniques will be used to supplement ultrasonic examination as requi md.
1. 7. 3 EDDY CURRENT Eddy current examinations will be perfonned on the steam generator tubing in accordance with the provisions of Appendix !Y of Section XI and the plant Technical Specifications.
1. 7. 4 LIQUID ENETRANT Dye penetrant examinations will be used whenever a surface examination is required on nonferrous components.
1. 7. 5 MAGNETIC PARTICLE Magnetic particle tests will usually be used when surface examination of ferrous components is required.
1. 7. 6 Y!SUAL The following visual examinations wii. be employed as appropriate:

VT-1: To detect detrimental condition (s) of parts, components, or on examined surfaces.

. YT-2: To locate evidence of leakage during a system or functional test.

0380L 1-3 Gen. Rev. 2

1 FN P-1 -M-043

. YT-3: To detemine the general mechanical and structural condition of components and their supports, and also to detemine conditions that could affect operability or functional adequacy of snubbers, and constant load and spring type supports.

1.8 EVALUATION OF EXAMINATION RESULTS Examination results of evaluated in accordance with IWA-3000, IWB-3000, and IWF-3000 of the ASME Code,Section XI. Articles IWC-3000 and IWD-3000, titled "Acceptance Standards for Flaw Indications," are in the course of pmparation I and, as yet, are not available for use. Themfore, the results of IWB-3000 l may be utilized for IS! Class 2 and 3 components.

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1.9 REPAIR AND REPLACEMENT FROGRAM Alabama Power Company's repair and mplacement program is defined in various plant administrative and departmental procedures. The detailed program for welding and related activities is defined in the Special Processes Manual, FN P-0-M-23, 1.10 LIMITATIONS OF EXAMINATIONS Limitations may occur for the examination of piping system cirtumfemntial butt welds (Categories B-J and C-F) when the welds occur at geometric discontinuities such as pipe-to-vessel welds, pipe-to-fitting welds, or fitting-to-fitting welds. The volume of weld and base material mqired to be examined for piping welds has changed significantly fmm the first 10-year inspection interval. Limitations evident during the first interval may no longer be relevent.

For pipe-to-fitting or pipe-to-vessel nozzle welds, examinations can be perfomed to the extent required by III-3230 of Section XI from the pipe su rf ace. Examination from the fitting side would be dependent upon the geometric configuration. Where elbows or tees am concerned, examinations can be perfonned from the fitting side except where the intrados of the fitting pmvents adequate ultrasonic coupling. No examinations can be perfomed f rom the fitting side when it is a valve or a flange. In all cases, the requimd volume of the weld and base material will be examined. Whem limitations am encountemd and ultrasonic examinations cannot be perfomed on the mquimd volume of the weld and base material, surface or visual examinations may be perfonned to supplement limited volumetric examination.

In instances when the locations of pipe supports or hangers restrict the access available for the examination of pipe welds as required by IWB-2500, examinations will be perforwed to the extent practical unless remowl of the support is pemissible without unduly strissing the system.

0380L 1-4 Gen. Rev. 2

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I NP- t 04 3 Imricy Nuclear Pf arit Unit No. 1 Inservice l esspec t iore t a ts le IWC-254m-1 t samitaation Categories C-H, PR1550HI MLI AISIIIeG 8e07/11 WitDS IN Vl55f t s Ixtent send tmanination fresquency or stem Requirements / [xamination Accertance (faminatign"

  • Relier No u faE1 Lifanitied . Figure 100. Metteod _11andard Second lette rva l R_qtgue. gig @ ts l'!Ldown HeaLhtysad C2.40 sentiles in vessels 51/2 i ts . Nominal thickness C2.11 flott le- to-5fie l l (or Head) Weld IWC-2$00-3 II/A N/A II/A -

N/A to fler C2.20 peoizles witfeout Neitsforcing Plate in vessels > I/2 in. 8eominal th ckness C2.21 flott l e- to-Sise l l f or He:ad) Weld I WC-2*>00-4( a ) II/A N/A II/A -

SI/A to INF or (b)

C2.22 06eirie inside Radia.& Mction 8 WC-2*>00-4( a ) 81/A II/A N/A -

II/A to INP

> 12. in. IIPS or (Is)

C2.30 feotiles with Meinforcing Plate in Vessels > l/2 in, eeominal t hic ktie s s C2.31 Reinforcing Plate Welds to S WC-2*>00-4( c ) N/A N/A N/A -

N/A to fl8P Nortle and Vessel C2.32 mazzIe-to-SheiI (or head) WeId5 IWC-2500-4(c) N/A II/A N/A -

N/A to iNP wtaen inside of Vessel is Accessitale C2.33 Norele-to-se. ell (or t cad) we.en N/A N/A N/A N/A -

N/A to dip E Inside of Vessel is inaccessitale

( scess letdown _ Heat Inct_wnge_r C2.lo peozzles in vessets 51/2 in.

seominal thicsness C2.Il Nortle-to-Shell (or locad) Weld I WC-2*AMF 3 II/A II/A N/A -

N/A to f88P C2.20 eforz tes withoest Heinforcing Plate in Vessels > I/2 in. Seeminal thickness 04028 3-1 RtV.2

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f a r ley Muclea r Plant Urs e t No. I f leP- t -N-04 3 inse rvice Inspec t iers table IWC-2* ADO- 1 [xaminatiots Categories C-8, PRESSURE REI AINIIIG IIOZILL WELDS IN VESSILS Entent and Emmeination f requevicy of Item Requirements / Examinatiers Acceptatsce (,5pej fsetjor)* Relier l ANauett Coecestts

Ilh_ ferit_Lr!alted f(eure 100. tee thod_ _11ande rd . Second Inttryal i i= cess ield_2wr,Heet [= change [ (Con't) 1 1 C2.21 80erz le-to-SN i l (or Head) odeld IWC-2SOO-4(a) N/A II/A N/A -

N/A to falP 4 or (b)

C2.22 Isorzle Inside Radius Section SWC-2SOO-4(a) N/A 88/A N/A -

N/A to IIsr

> 12 in. NPS or (b)

C2.30 86orztes witte Mainforcing Plate in Vessels > I/2 in. Ilominal Itaickness C2.33 Heinforcing Plate Welds to Itozzle IWC-2SOO-Is(c) Is/A N/A Is/A -

II/A to IIIP and vessel C2.32 Noizie-to-SIsell (or Head) Welds IWC-2SOO-4(c) N/A 81/A N/A -

88/A to f air wisen Inside of Vessel is Accessible .

Cz.33 Isoiz i e-to-She l l (or Head) wtsen N/A N/A N/A N/A -

N/A to FNP 5 Inside of Vessel is Iriaccessible l'eSe8Mratlye Heat t >chasyge[, 3 C2.10 NoIIIes its Vessels SI/2 in. ,

Nominal ilsickness C2.11 Isozz le-to-Stee l l (or Head) Weld SWC-2SOO-3 31/A N/A N/A -

N/A to f8tP C2.20 Nortles w6 ttsonst Reiseruacing Plate les Vessels > I/2 in. Moeinal fisickness C2.28 Isott le-to-Stee l l (or head) Weld SWC-2SOO-4(a) 88/A N/A II/A -

N/A to INP or (b)

C2.22 Ilotzte Inside Radius Serction I WC-2*>OO-4( a ) N/A N/A N/A -

N/A to IllP

> 12 in. NPS or (b)

C2.30 Nozzles with Reinforcing Plate iss Vessels > I/2 in. Isominal Ilsickness 08 028 3-a MtV.2

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Iar8ey IsucIcar P1anL Unit No. I f NP-1-90-04s 3 8 nseiry ice i rasssec t ion Imble IWC-2SOO-1 tuaainst son Categories C-tl, THtS5 Ult [ ME TAIN181G IIOZIt[ Wf LDS IN Vf 55tLS

[mtent and Emmainatson fregesency or stem Meguirements/ [mmeination Acceptaace hgejsetLjoeg* Metier .

8)o m faniheineJ rieu.e 100. plethod Standard- Second Interval fleevest Cmis

!Leelatiye weat is mirge.2 (Can't) E C2.31 Reiserorciseg Plate Wolds to 8WC-2$00-4(c) II/A II/A II/A -

II/A to INP 800E2Ie sted VesseI IWC-2SOO-4(c) N/A N/A Sf/A - Og/A to (pgP C2.32 teoirle-to-Sheel (or teoad) Wolds wesen enside or Vessel is Accessible C2.33 sesiz 8 e-to-She s I (or lesad) when N/A N/A N/A N/A -

N/A to FNP S Inside or Vessel is Inoccessible ftuliltaal_ ten t (=chaeme W 21 C2.10 peozzles in Vessels 51/2 in.

Isomina l lleichness C2.18 90cIZfe-to-$ hell (or lesa4) Weld IWC-2SOO-3 N/A II/A II/A -

88/A to late C2.?O horites witteout keinforciseg Plate in Vessels > I/2 in. Isominal thickness C2.21 8eott le-to-58ee l l (or Head) Weld IWC-2$00-4(a ) N/A II/A N,.* 4 -

N/A to fler ar (a.)

C2.22 teoille Inside Radium Se ; tion IWC-2*Av.3-4( a ) 18/A 1/A N/A -

N/A to fasP

> 12 in. IIPS or (b)

C2,30 stoIIIes witts Iteinrorciseg Plate ese Vessels > 1/2 in. 80oeinal thicksness C2.31 Reini'ercitig Plate We):Is. to IWC-2$00-4(c) Sur, ladG-3000 At 8 800.Eles at .

Motzle and vessel (2) tereisne s end' or piping runs'.

horzle-to-Stee88 (or stead) Walds IWC-2$00-4(c) II/A N/A N/A -

N/A to INP C2.32 weseos ins 6de of Vesses is Accessible secte $ VI-2 No . A t t teori t es a t - state 6 C2.33 seoiz s e-to-She s I (or 8eead) when Inside of Vzsse2 is $*naccessible Leehage terminal end' or 8tequired pip 8pg runs *. each pe riod.

3-1 atV. 2 04021

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f arley Nuclear Plant Unit 800 1 INP-t-M-043 Intervice Inspectices Tatste IWL-2*>OO-1 Examination Categories C-8, FRt550R[ Ril AINSNG soollit WitDS les VLSM LS Extent aged fxamination freguevacy or stem Requirements / [maelsta t ion Ac. . .ance [> ami na tige}* Reiser .

lF L fffL1_[fashigil _f_igure 300. lee tt.od Jtt A rd _ Second interval legg m 1 h ts b?ti YaltC EtLurn fiIttr .

C2.10 soorzses in vessets 51/2 in.

Ilominal Ihickreess C2.11 8eort le-to-50se l l (or Hesed) Weld SWC-2SOO-3 II/A N/A N/A -

N/A to IIer C2.20 NoI28es without Reinforcitig Plate in vessels > 1/2 in. Isominal Ihickness C2.21 GeoE2 0 e-to-50se l l (or Head) Wold IWC-2SOO-4( a ) N/A II/A N/A -

as/A to INP or (b)

C2.22 Isorile Isaside Radius Section 4WC-2$00-4(a) 88/A FA# N/A -

N/A to (for

> 12 tre. serS or (b)

C2.30 Nozzles witte Reinforcitig Plate esa Vessels > 1/2 ire. Isomissal Itaickness C2.31 Reinforcing Plate Welds to IWC-2$00-4(c) II/A II/A N/A -

as/A to INP teoirIe and yesseI sow ise-to.5nes3 (or Head) Wedds 4WC-?$00-4(c) N/A 88/A SE/A N/A to INP C2.32 wtsen Inside of Vessel is Accessets:e C2.33 seoizie-to-Stell (or Head) wfeess N/A N/A N/A N/A -

N/A to FNP 3 9nside of Vessel is inaccessible YoLuet_ feat rnLle!! 54 c2.:o uozzses en vessels ss/2 in.

Nomin.: s t.icknes s .

C2.8% foors t e-to-Sho l t (or Head) Weld IWC-2SOO-3 II/A II/A II/A -

N/A to IIIP C2.20 Muzzles we tteuut Maisitorciseg Plate ess Yesset s > 1/2 dra. Stomissal

tsickseess 3-30 MtV. 2 04023

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8 s riey 86uclear Plant Ureit Geo. I II6P-1-M-043 Inse rvice I risgec t ion Table IWC .'S00-1 faaminatiose Ca srses C-8, Pkt55unt at[IAINileG NOII1L wtLS5 888 VISSEL5

[mtent ased imanination frequency of 8 tem Requirements / [xamination Acceptance [mee_ingtLog*

  • Res ier .

81 % f!ELLLE!*iPef f iGMfe 100. mthod _11anda rd Second Interval Recogst Comments yoLune Coejirol iank (Con'tj C2.21 900Elle-LO-5fg88 (or Stead) Wald SW-2SOO-4(a) N/A N/A 88/A -

N/A to faer or (b)

C2.22 860ttle Inside Radius Section lWC-2SOO-4( a ) N/A N/A st/A -

N/A to INP

> 12 in. seP5 or (b)

C2.30 Isorztes with Reinforcitag Plate in Vessels > 1/2 in. Isomitial Iteicksness C2.31 Reitsforcing Plate Welds to IWC-2500-4(C) 88/A N/A II/A -

N/A to falP NoI2fe asad Vessel C2.32 Nort le-to-Stee l l (or Head) Welds SWC-2$00-4(c) II/A N/A 81/A -

N/A to fler whess 8seside of Vessel is ,

Accessihte C2.33 Isorit e-to-She 8 8 (or Head) wfeen N/A N/A N/A N/A -

N/A to FNP $

inside or vessel is inaccessible Letdow!L84 deca ttes!LinLianger C2.10 Noizles its Vessels i'/2 in.

Ison s tea l Ihicksness C2.11 tsozz le-to-Sinel l (or teead) Weld SWC-2500-3 N/A II/A SI/A -

88/A to (ISP C2.20 floIIIes willeout Reinforcing Plate iss Vesse l s > 1/2 in. 160mina l Iteickness C2.21 Itortle-to-58ee 8 8 (or head) Weld SWC-2500-4(a) E/A SI/A N/A -

88/A to 188P or (b)

C2.22 Nortie Inside Radius Sectiore IWC-2*p00-4( a ) N/A II/A as/A -

N/A to fler

> 12 in. 06P5 or (b)

C2.30 Isoffles witta feeinforcing Plate ise vessels > 1/2 ise. Stuminal s teickness o4o28 3-11 Rtv. 2

FIsr.3.pg.04:3 farley nuclear Plant Unit 800 1 Inservice ins 5,ec t ion Table IWC-2SOO-1 fmamination Categories C-8, PHL55UNE NEIAINING II0lILE Wil_DS Ist VESSELS

[xtent and Emanination frequency or 8 tem Reaguirements/ Examination Acceptance kapinatieg*

  • Roller .

f levre 100. Method Standard Second laterval flequelt COGNepts A Pa rtit_1 m as.i reed ifL & vn f4ffstet f>cf)Lngfr 109f1'1)

C2.31 Reinforcing Plate Wolds to teorzte IWC-2'poJ-4(c) II/A II/A (. ' A -

N/A to IIsP and Vessel C2.32 86oiz le-to-She l l (or teoad) Wolds SWC-2500-4(c) N/A II/A N/A -

N/A to falP wteen inside of Vessel is Accessible C2.33 esozz le-to-Ste l l (or Head) when N/A N/A N/A N/A -

N/A to FNP 5 Inside or Vessel is Sneccessible LyaLWater Hegt [>chanegr C2.10 8ecirles in Vessels 51/2 in.

I60minal thickness C2.11 Isois t e-to-Stee l l (or Head) Weld IWC-2$00-? SI/A N/A II/A -

N/A to IIIP C2.20 86ozzles witinout Reinforcing Plate in vessels > l/2 in. Inominal Italcktents C2.21 860ill e- to-Stie l i (or Head) Weld 8 WC-2*pOO-4 ( a ) N/A II/A II/A -

N/A to fler or (b)

C2.22 86oIIIe inside Radius Section SWC-2500-4(a) N/A N/A al/A -

88/A to IIIP

> 12 in. IIPS or (b)

C2.30 Norries witte Reinforcing Plate in vessels > 1/2 in. Isominal 18 sickness C2631 keinforcing Plate Wolds to teozzte IWC-2500-4(c) II/A N/A II/A -

II/A to fler and Vessel C2.32 86erile-to-58 eel e (or Head) Welds B WC-2*p00-4( c ) N/A II/A N/A -

N/A to IISP wtaen Inside or Vessel is Accessable C2.33 Noizle-to-Stiell (or Head) weien N/A N/A N/A N/A N/A to FNP S Inside or Vessel is Inaccessible 04o71 3-12 H[V. 2

.__.m _.__ _ _

_ _ _ _ _ _m. _ _ _ _ _ _ . _ . _ __ _ m . .._ ____.m __._ ._._m

  • i i

.. i

~

  • f ar6ey asuclear Plant Unit No. 1 fler- t-se-043 Inservice Issspec t ion Imble 8 WC-2*Am-1 [mmelnation Categories i

I C-8, PR[55URL REIAlalIIIG IIOllL[ W(LDS III VLSS(LS Extent said 1maaination frequesecy or i

1 Itee Meeguirements/ Imasination Acceptance (made ngjgg*

  • Relier .

tenLLrealned rieure see. Peett ed _.11ende rd . second enterves siveuest coeNeots mm itemeDSrners (31 1

! C2.30 Noir. s in vessels si/2 in.

)

alomina l Ihickness C2.tt teoizie-to-She l l (or Head) Wold I WC-2*>00- 3 II/A II/A N/A -

II/A to fler C2.20 teoizies witteout Reinforcing Plate

in Vessels > 1/2 in. Stooinal t

Ihickness J C2.23 peozz le-to-Stee l 8 (or Head) Weld (2) IWC-2SOO-4(a) Vol. 8WC-3OOO A8 8 seozzles at or (b) Sur. terminal ends' of piping runs'.

=1 C2,22 esozzle Inside Radius Section IWC-2SOO-4(a) Vol. 8WC-3OOO All teorztes at sta-28 -

> 12 in. NPS (2) er (b) termina8 ands' a of piping runs ,

C2.30 NoirleS wILto Reisitorcirog P8 ate in Vessels > t/2 in. Noe.inal linicksness Heiseforcing Plate Welds to teotzte I WC-2*>00-4 ( c ) II/A N/A II/A - N/A to iper C2.31 arid Vessel i

j C2.32 Nort le-to-Sise 8 8 (or Head) Welds IWC-2$00-4(c) 88/A N/A SI/A -

81/A to INP

< weien inside or vessed is Accessible C2.33 Isoir s e-t o-Stee l l (or Head) wtsen N/A N/A N/A N/A -

N/A to FNP g snsido or vesses is enaccessible

. Frannr_C8Mlant_LU ME C2.lu alotiles in Vessels 11/2 in.

Nominal lisicksness 88/A to f alp C2.18 8eoit le-to-51se l l f or Head) Weld I WC-2*>00- 3 II/A II/A 88/A -

n4028 3-33 Rtv. 2

- ~ . -_ - _ .. _- - _.,- ___-__ __-,_-___-_-_-___. . - , _ __ - _ __ ... - . - -. . - -

  1. 86P-1-pt-04s 3 **

f arley 86uclear Plant Ussit too. 3 Isise rvice Inssnect ius table IWC-2Soo-1 [masination Categories C-8, PHtSSUM[ RETAINigeG 98022t[ WitDS IN VESS(ts

[mtent and ImanInation Iroguency ar stegui remerits/ Lxamination Acceptance Lapoine_Lj_e_n_*

  • Netier .

8 tee 81%_ D ru.LE!* f fet4 f leure 300- Peethod .113t!de rd _ Second Interval sneeu'St fdLeontu Enster_MnLant f i sier f est'(1 C2.20 Notztes wittsout Reinforcing Plate in Vessels > 1/2 in. IIoninel Itsickness C2.21 alotzle-to-Liset t (or Head) ndeld SWC-2$00-4(a) II/A 81/A N/A -

II/A to IISP or (b)

N/A N/A - II/A to IIgP C2.22 8eozz a se Inside Radius Section IndC-2SOO-4( a ) N/A

> 12 in. sers or (b)

C2.30 Noizies with Reinforciseg Plate in Vessels > 1/2 in. Isominal iteickseess C2.38 Reinforcisig Plate Welds to llotzte IWC-2SOO-4(c) SI/A N/A 88/A N/A to fler and Vessel C2.32 8eorile-to-Steel l (or tocad) Wolds IWC-2$00-4(c) Is/A 88/A N/A -

II/A to fler wteers enside of vesses is Accessibse C2.33 8eorile-to-see s (or t.ead) when N/A N/A N/A N/A - N/A to FNP S snside or vessel is snaccessibse t_ettl9w'LIMify_.f anha_121 C2.10 Noriles iss vessels $1/2 in.

86ominal Itaicksness C2.11 Slot 21 e-to-Stee l 8 (or isead) Weld 8WC-2$00-3 II/A N/A N/A -

SI/A to fler C2.20 86oirles w.stsout Reisiforcing Plate iss Vessels > t/2 in. Isomina l itsickssess I6erite-to-58se8 8 (or Beemd) Weld IWC-2$00-4(a) 98/A to/A 8t/A -

88/A to (86F C2.25 or (b)

C2.22 16ortie aseside kadius Section IWC-2Soo-4( a ) N/A Ig/A 88/A -

II/A to (Isr

> 12 in. sers or (b)

?

3-84 aty. 2 04021

. . c, .

l .

f arley Isuclear Plant Unit Sto. 1 (NF-t-N-043 enservice Irispection table 8bdC-2$00-1 [masination Categories C-8, PHL550RE RETAIIlleIG 800llLE nd(LDS Ist V[55ELS Eatent and Emaaination frequency or stem seguirements/ Emasinetion Acceptavoce heehigen*

  • Res ier .

l tegm f_gris_ Ese(ped J_ inure No. Method Standard Second.intstvat .

Peevelt G9seepts i Lfidi'vf1_D9_19Y Ie95s i2i !E9dil C2.30 asoisses with seinforcing Plate in vessels > 1/2 in. 80esinal thickness C2.31 meinforcireg Plate beelds to seoisle 8WC-2500-4(c) II/A N/A II/A -

II/A to f MP and Vessel l C2.32 Isori t e-to-Stee l l (or Moed) ndelds IWC-2500-4(c) N/A N/A II/A -

N/A to INP I winen Inside or vesset is

! Accesseble l

i C2.33 Isorise-to-58.es a (or Head) weien N/A N/A N/A N/A -

N/A to FNP 5 i enside or vesses is snaccessible l

l L"EflLif1fowfLDeinder*s f 21

, C2.10 Isorites ire Vessels 11/2 in.

Nominal lhickness .

C2.18 Isotile-to-Stee l f (or l ead) Weld IndC-2$00-3 N/A as/A N/A -

as/A to tsar C2.20 Notiles wittsout Heinforcing Plate in Vessels > 1/2 in. Nominal I tsickne ss C2.21 Isois s e-to-58se l l (or Head) ndeld IWC-2$00-4( a ) II/A Il/A N/A -

81/A to INP i

or (b) l C2.22 06erste Inside Radius Section IWC-2500-4(a) 81/A II/A IE/A -

N/A to INF

> 12 in. NPS or (b)

C2.30 Nois ses witte Maintercing Plate in Vessels > 1/2 in. Iloeista t i

I ite2c ksness C2.33 Heinforcing Plate Wolds to teotile IWC-2500-4(c) 88/A 88/A II/A -

II/A to INF and vessel C2.32 Isoille-to-Stee l l (or Head) ndelds IWC-2SOO-4(c) N/A $8/A N/A -

N/A to (WP wtses Iriside or Vessel is l

Accessible 04n28 3-13 REV. 2

. - . _ _ . _ . - _ _ ~ . _ _ . - _ ._ .

4 f arley Iksclear Plant Unit 800 1 I MP- t 04 3 inservice inspec tiore J

Imble IndC-2*AMJ-l taseination Categories C-8 PAISSUM[ M[TAIN4IIG IIOllt[ ndtLDS 8Il VESSEt 5

] ,

[xtent and

! Emmeinstion t reasesency or stem Meaguirements/ [mmeination Acceptance (maetne_tigg*

  • Helier .

IL ter_1 L izam L A fleure leo. Peethod 11anda rd second Inte rva l pientit Comments Lucess tgtiss yn Delay Tanks (2)

C2.33 anoizse-to-thes s (or Head) when N/A N/A N/A N/A -

N/A to FNP $

inside or Vesses is sneccessible ik)fE!Ljff.jggt Lon iaok C2.10 Mozzles in Vessels $1/2 in.

Num e ria l Ihickness C2.11 stori t e-to-She l l (or Head) neeld ledC-2SOO-3 N/A N/A 88/A -

II/A to INP i C2.20 seozzles wittsout Meinforcing Plate in vessels > 1/2 in. Iteeina l Ihickness C2.23 Isof t le-to-She I I (or Head) ideld 8tdC-2$00-4( a ) Vol. 8tdC-3000 All Isoftles at - -

l or (b) Sur. terminal ends' or piping runs'.

I C2.22 Georite traside Radius Section 8 ndC-2SOO-4( a ) st/A st/A II/A -

as/A to fler 1 > 12 in, sePS or (b)

C2.30 Isoriles with Heisiforcing Plate -

in Vessels > 8/2 in. Itoe s na l 4 Ilsickswss

}

l C2.3% Reisaf'orcing Plate %delds to Itozzle 16dC-2*,00-4(c) II/A II/A II/A -

al/A to ISIP I and Vesset C2.32 Norile-to-Shell (or Head) % deeds lidC-2$00-4(c ) 18/A N/A II/A -

N/A to fler j

wisers Isaside or vessel is Access 8ble C2.33 morise-to-5s.e g s (or Head) we.ees N/A N/A N/A N/A - N/A to FNP S snside of Vesses is snaccessibse J

4 o4u2: 3-16 StV. 2 1-------.----v---w- ,..+--,,--+.m----------_ww.- - - - - - - - , - - -r - -- --- , y--- -- . .e-w -. , - - - - - - -, , -

l FN P-1 -M-043 l

l RELIEF REQUESTS l

FN P-1 Relief kJquest No. Examination Arde RR-35 Hydmstatic testing of Class 3 buried piping in the service water system.

RR-36 Visual (VT-2) examination of the tubes in the Class 3 component cooling water heat exchangers.

l RR-37 Visual (VT-2) examination of condenser l coils (tubes) in Class 3 coolers.

RR-38 Hydrostatic testing of Class 3 portions of l auxiliary steam piping.

RR-39 Hydrostatic testing of Class 3 auxiliary '

feedwater pump minimum flow piping. ,

I RR-40 Hydrostatic testing of all Class 2 br2n:h pipe lines from VCT to first valve.

l RR-41 Break away drag test for hydraulic  ;

snubbers. l t

RR-42 Additional sample testing mquirements for snubbers.

RR-43 Hydrostatic testing of Class 2 portions of the RCS head vent lines. ,

RR-44 Operational monitoring of the Class 3

  • spent fuel pool cooling heat exchangers. l RR-45 Hydrostatic testing Class 2 and 3 low pressure systems where a large change in elevation exists. t i

RR-46 Schedule adjustment for seven (7) system l hydmstatic tests.  !

I 0380L 6-4 Rev. 2  !

L

FN P-1 -M-043 RELIEF REQUEST FN P-1 RR-1 Component or Aelief Area: Relief from the material requirements for calibration blocks used to perfom ultrasonic examination of the following:

A PR-6 : Steam generator channel head-to-tubesheet welds.

AMt-7: Boron injection tank head-to-shell lI circumferential welds and nozzle-to-head welds.

ALA-RV-1: Reactor vessel lower head-to-lower, shell weld and all lower head welds. Boron injection tank lI head-to-shell circumferential welds.

ALA-RV-3: Reactor vessel shell-to-nozzle welds and top head welds.

Requirement from which Reitef is Requested: Section XI,1963 Edition with Addenda through Summer 1983, paragraph IWA-2232 requires that ultrasonic examination of vessel welds in ferritic materials greater than 2 in. in thickness be perfomed in accordance with Article 4 Section Y. Paragraph T-434.1.1(3), Article 4 requires that the material from which calibration blocks are fabricated be of the same material specification, product forn, and heat treatment as one of the materials being joined.

Basis for Relief: Ouring fabrication of the Farley Unit I nuclear steam supply system vessels, the calibration blocks used to perform examinations by the vessel manufacturer were fabricated to the requirements of American Society of Mechanical Engineers (ASME)Section I!!. When ASME Section XI was issued for inservice inspection, the new requirements for vessel calibration blocks rendered the existing blocks unacceptable for use. The original blocks had to be replac6d but some vessel materials wert no longer available. The vessel calibration biccks had to be refabricated to the Section XI requirements appitcable at that time.

04061 6-5 REY 2

FN P-1 -M-043 RELIEF REQUEST FNP-1 RR-26 Component or Relfef Area: Hydrostatic testing of portions of Class 2 piping systems isolated from the test boundary by closed check valves.

Affected lines are as follows: Reference drawing D351116, Sheet 2 of 4.

A. Charging pump suction piping from the chemical mixing tank between valve Q1E21V186 and check valve Q1E21V187 (line No. HCB-11).

B. Hydrtgen and nitrogen supply piping to the VCT from check valve QlE21V201 to isolation valves Q1E21V202, Q1E21V583, and Q1G21V260 (line Nos. HCB-68 and l HCB-99). E C. Charging pump suction piping from volume contrtl tank between check valve QlE21Y211 and locked closed valve Q1E21Y212 (Line No. 2" HCB-16).

D. Charging pump suction piping from boric acid blender between check valve Q1E21Y210 and normally closed valve Q1E21Y264 Requirement from which Relief is Requested: Category C-H, Table IWC-2500-1 of ASME Section XI, requirts a hydrostatic test for all Class 2 pressure retaining components once every 10-year inspection interval in accordance with IWC-5222 Basis for Reifef: Pressurization of the portions of system piping listed above cannot be assured due to the position of the check valves. The check valves listed prevent flow frem the test fill point to the specified boundary valves.

Alternate Examination: Portions of the above mentioned Class 2 piping will be visually examined during the Class ? system functional test.

04061 6-39 Rev. 2

f FN P-1-M-043 i

RELIEF REQUEST FN P-1 RR-30 ,

Component or Relief Area: Hydrostatic testing of the Class 2 portion of the steam generators and associated piping. Reference drawings D351110, sheet 1 of 2 and D351122, sheet 1 of 3. ,

I Requi rement f rom which Relief is Requested: Item No. C7.10, Category C-H, Table IWC-2500-1 of ASME Section XI, requires a system hydrostatic test of Class 2 ,

pressure retaining pressure vessel once every 10-year  !

inspection interval, in accordance with IWC-5222. Also, saragraph IWA-5213(d) requires a 4-hour holding time for iydrotest of the insulated system.

Basis for Relief: In order to prevent undue stress on the steam generators, I Westinghouse reconnends that the hydrostatic test of the secondary side of the steam generators be conducted at 1.25 Pd for a minimum of 10 minutes and a maximum of 30 l l minutes, and then reduced to operating pressure,1.0 P de for the balance of the 4-hour holding period. The related l l Class 2 piping is hydrostatically tested along with the -

steam generator. l c

Al te rnate Examination: The Class 2 portions of the steam generator and related f piping will be hydrostatically tested at 1.25 Psv for a l l minimum of 10 minutes and a maximum of 30 minutes. The l test pressure will then be reduced to 1.0 Pd for the remainder of the required 4-hour holding time.

l l

[

I i

f t

l l

0406! 6-43 Rev. 2 l l

i i

I

FN P-1 -M-043 RELIEF REQUEST t FN P-1 RR-34 Component or ,

Relief Area: Hydmstatic testing of Class 3 spray additive piping and components in the containment spray system (reference drawing 0351115, Sheet 3).

Requirement from  ;

which Relief is  !

Requested: Paragraph IWD-2510 and Table IWD-2500-1 of ASME Section XI [

mquire that all Class 3 pmssure retaining components be subjected to visual examination (VT-2) in conjunction with i the system pressure test of IWD-5000.  !

I Basis for Relief: While in service these spray additive lines have an l operating pressure of 15 psig and temperatum of 100*F,  ;

which is well below the design conditions of 210 psig r pressurt and 300'F temperaturt. Therefore, a system hydrostatic test at 1.25 Psy would not provide a meaningful test. In addition, the hydrostatic test will l

involve handling of highly corrosive sodium hydmxide, l which is undesirable and hazardous to personnel safety.

Al ternate  !

Examination: A measured flow test in accordance with plant Technical Specification paragraph 4.6.2.2d will be conducted periodically to assure the leaktightness of these Class 3 components. l l

(

l l

l

\

0406! 6-47 Rev. 2  !

t l l l l

'e. ,

1 FN P-1 -M-043 RELIEF REQUEST FN P-1 RR-45 Component or Relief Area: Hydrostatic testing of Class 2 or 3 low pressure systems where the system under test has a large change in elevation and the test boundaries cannot be reduced due to plant configuration:

Requirement from Which Relief is Requested: IWC-5222(a) and IWD-5223(a) specify the minimum required pressure to be applied during system hydrostatic testing.

However, IWA-5265(b) also requires that when testing a group of components or a multi-component system, the imposed pressure on any component, including static head, will not exceed 106% of the specified test pressure for the system.

Basis for Relief: The minimum requirtd pressure to be applied during system hydrostatic testing is based on design conditions of the piping to be tested. When considering a system where a large change in elevation is encountered, the hydrostatic pressure throughout the system would be reduced proportionally as elevation increased. During hydrestatic testing of these systems, this 1061 upper limit on test pressure will prtduce a condition where the minimum test pressure required by IWC-5222(a) and IWD-5223(a) cannot be achieved in the higher elevations of the test circuit.

Al te rnate Examination: Where this is a concern hydrostatic testing will be conducted with the lowest point in the system at 10n of the specified test pressure per !WA-5265(b) and the pressure at the highest location may fall below the minimum test pressure required by IWC-5222(a) or IWD-5223(a).

04061 6-59 Rev. 2

i FN P-1 -H-043 RELIEF REQUEST FN P-1 RR-46 Component or Relief Area: Scheduling for the performance of Class 2 and 3 system hydrostatic tests to be accomplished during the second ten-year inspection interval.

Requi rement f rom Which Relief is Requested: Table IWC-2500-1. Examination Category C H, Note 5 and Table IWD-2500-1. Examination Categories D-A, D-B, and D-C, Note 2 require that system hydrostatic tests be conducted at or near the end of the inspection interval or during the same inspection period of each inspection interval for Inspection Program B.

Basis for Relief: The system hydrostatic tests are scheduled on a periodic basis in accordance with Inspection Program B. As a result of performing additional tests during the first ten-year interval, it is necessary to move eight (8) hydrostatic tests forward one period. The original schedule for performing hydrostatic testing was based on dividing the systems to be tested into eighteen (18) procedures. Due to ope',ational conditions during the course of the interval, several procedures were divided resulting in additional hydrostatic testing procedures to be performed. At the end of the interval twenty five (25) procedures existed to cover the systems to be tested.

Al ternate Examinations: All twenty five (25) hydrotest procedures will be performed during the second inspection interval. They will be scheduled to distribute the testing evenly between the three (3) periods for the second interval.

0406! 6-60 Rev. 2

FN P-1 -M-043

12. Relief Requested from Inspection Requirements for Certain Pressure-Retaining Valve Body Welds and Internal pressure Boundary Surfaces, Letter dated March 11, 1986, f rom R. P. Mcdonald, AN, to L. S.

Rubenstein, USNRC.

13. Nuclear Regulatory Comission Notice of Granting Relief for Pmssure-Retaining Valve Body Welds and Internal Pressum Boundary Surfaces, letter dated June 19, 1986, f rom D. G. Mcdonald, USNRC, to R. P. Mcdonald, AK.
14. Relief Requested from Inspection Requirements of Steam Generator primary side Nozzle Inner Radiused Sections. Letter dated January 13,1987 f rom R. P. Mcdonald, AN to L. S. Rubenstein, USNRC.
15. Nuclear Regulatory Comission Notice of Granting Relief for Steam Generator primary side Nozzle Inner Radiused Sections. Letter dated July 8,1987 f mm E. G. Adensam, USNRC to R. P. Mcdonald, AK.
16. Second Ten-Year submittal of the Inservice Inspection Program, letter dated May 27, 1987 f rom R. P. Mcdonald, AN, to USNRC.
17. Second Ten-Year submittal of the Inservice Inspection Program, letter dated November 23, 1987 f rom R. P. Mcdonald, AK, to USNRC.
18. Nuclear Regulatory Comission Notice of granting Interim Approval for tho Second Ten > Year Inservice Inspection Program. Letter dated December 10, 1987 f rom E. G. Adensam, USNRC to R. P. Mcdonald, AN, 0404! 7-3 Rev. 2
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