ML20042F105
| ML20042F105 | |
| Person / Time | |
|---|---|
| Site: | Perry  |
| Issue date: | 04/25/1990 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20042F098 | List: |
| References | |
| NUDOCS 9005070225 | |
| Download: ML20042F105 (9) | |
Text
,
l omo of o
UNITED STATES
'g NUCLEAR REGULATORY COMMISSION n
5 WASHINGTON. D. C. 20$$$
e
%...../
SAFETY EVALUATION BY 1HE OFFICE OF NUCLEAR REACTOR REGULATION 0F THE FIRST 10-YEAR INTERVAL INSERVICE INSPECTION PROGRAM PLAN i
THE CLEVELAND ELECTRIC ILLUMINATING COMPANY, ET AL.
PERRY NUCLEAR POWER PLANT. UNIT 1 DOCKET NUMBER 50-440 l
1.0 INTRODUCTION
By letters dated March 31, 1987, April 12 and November 18, 1988 and January 6, l
1989, the Cleveland Electric Illuminating Company, Duquesne Light Company, Ohio Edison Company, Pennsylvania Power Company and Toledo Edison Company l
(the licensees) submitted the first 10-year interval Inservice Inspection Program Revision 0, associated relief requests and responses to the NRC staff
' requests for additional information'for the Perry Nuclear Power Plant, Unit No. 1.
Technical Specification 4.0.5 for the Perry Nuclear Power Plant Unit 1, states that the surveillance requirements for Inservice Inspection and Testing of the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code Class 1, 2, and 3 components shall be applicable as follows:
In-service inspection of ASME Code Class 1, 2, and 3 components shall be performed in accordance with Section XI of the ASME Code and applicable Addenda as requiredby10CFR50.55a(g),exceptwherespecificwrittenreliefhasbeen granted by the Commission pursuant to 10 CFR 50.55a(g)(6)(i).
Pursuant to 10 CFR 50.55a(g)(4), ASME Code Class 1, 2, and 3 components (including supports) shall meet the requirements, except the design and access provisions and the preservice examinatinn requirements, set forth in the ASME Code,Section XI, " Rules for Inservice Inspection of Nuclear Power Plant Components," to the extent practical within the limitations of design, geometry, and materials of construction of the components.- The regulations require that inservice examination of components and system pressure tests conducted during the initial 10-year interval comply with the requirements i
l in the latest edition and addenda of Section XI of the ASME Code incorporated by reference in 10 CFR 50.55a(b) on the date 12 months prior to the issuance of the operating license,(subject to the limitations and modifications listed therein. The components including supports) may meet the requirements set forth in subsequent editions and addenda of the ASME Code incorporated by reference in 10 CFR 50.55a(b) subject to the limitations and modifications listed therein.
Pursuantto10CFR50.55a(g)(5),ifthelicenseedeterminesthatconformance with an examination requirement of Section XI of the ASME Code is not practical for his facility, information shall be submitted to the Commission in support of that determination and a request made for relief from the ASME Code requirement. After evaluation of the determination, pursuant to 9005070220 900425 PDR ADOCK 05000440 g
a 2
10 CFR 50.55a(g)(6)(1), the Commission may grant relief and may impose alternative requirements that are determined to be authorized by law, will not endanger life or property or the common defense and security, and are otherwise in the public interest, giving due consideration to the burden upon the licensee that could result if the requirements were imposed.
The licensees have prepared the Perry Nuclear Power Plant, Unit 1, first 10-Year Interval Inservice Inspection (ISI) Program Plan, Revision 0, to meet the requirements of the 1983 Edition, Summer 1983 Addenda, of Section XI of the ASME Boiler and Pressure Vessel Code, except that the extent of examination for Class 2 piping welds has been determined by ASME Code Case N-408 as allowed by NRC Regulatory Guide 1.147. The staff, with technical assistance from its contractor, the Idaho National Engineering Laboratory (INEL), has evaluated the first 10-Year Interval Inservice Inspection Program Plan, Revision 0, additional information related to the Program Plan, and the requests for relief from certain ASME Code requirements determined to be impractical for Perry Nuclear Power Plant, Unit 1, during the first inspection interval.
2.0 EVALUATION The 151 Program Plan has been evaluated for (a) application of the correct Section XI Code edition. and addenda, (b) compliance with examination and systempressuretestrequirementsofSectionXI,(c)acceptabilityofthe examination sampla, (d) compliance with prior ISI commitments made by the licensee, (e) correctness of the application of system or component examination exclusion criteria, and (f) adequate information in support of requests for relief from impractical Section XI Code requirements. The staff has determined that the licensees' ISI Program Plan reflects compliance with the requirements listed above.
The information provided by the licensees in support of requests for relief from impractical requirements has been evaluated and the bases for_ granting relief from those requirements are documented in the attached INEL Technical Evaluation Report EGG-MS-8378. We concur with and adopt the findings and reconmendations contained in the subject report.
Table 1 presents a summary of the reliefs requested and the status of the requests as determined by the staff.
3.0 CONCLUSION
The staff concludes that the Perry Nuclear Power Plant, Unit 1, first 10-Year Interval inservice Inspection Program Plan, Revision 0, with the additional Information provided and the specific written relief, constitutes the basis for compliance with 10 CFR 50.55a(g) and Technical Specification 4.0.5 and is, therefore, acceptable. With respect to the relief granted, the staff hasdetermined,pursuantto10CFR50.55a(g)(6)(1),thattherequirementsof
3 the code are impractical and, based on the alternative requirements imposed, the relief is authorized by law, will not endanger life or property or the '
connon defense and security and is otherwise in the public interest, giving due consideration to the burden that could result if the requirements were imposed on the facility.
Attachments:
1.
Table 1 - Sunnary of Reliefs 2.
Technical Evaluation Report EGG-MS-8378 December 1989 4
+
Perry Nucle:r Power Plant, Unit 1 Page~1 of 6
~
TABLE 1
~
SUPMARY OF RELIEF REGIFSTS Relief Licensee Request System or
. Exam.
Item Volume or Area Required Proposed Relief Request Number Comoonent Cat.
No.
to be Examined Method Alternative Status IR-001 Reactor B-A B1.11 Circumferential shell Volumetric Mone.
Granted (part 1 Pressure welds:
(Volumetric Volumetric of 3)
Vessel 1-B13-AA 1-B13-AB and surface examination to 1-BI3-AC 1-B13-AD for Item maximum extent Bl.40 practical and welds) 100% surface Bl.12 Longitudinal shell welds:
examination of 1-B13-BA I-B13-BB weld 1-B13-AG l-Bl3-BC 1-813-BE l-B13-BG I-B13-BJ 1-B13-BK 1-B13-BN l-813-BP l-813-BR Bl.21 Circumferential head weld I
l-B13-AH Bl.22 Meridional head welds:
1-813-DG l-Bl3-DH
[
Bl.40 Head-to-flange weld i
1-B13-AG i
i l
~,,
~.
~..
... ~....
l'
- Perry Nuclear Power P1ent, Unit-I l
.'Page 2 of 6
[
TABLE 1
"~
SUPMARY OF RELIEF REQUESTS l
j -
Request System or Exam.
Item Volume or a a?
Required Proposed Relief Request Relief l_icensee i
Number Comoonent Cat.
No.
to be Examined Method Alternative Status IR-001 Reactor B-D B3.90 Nozzle-to-vessel welds:
Volumetrit
- None.
Granted I
(part 2 Pressure 1-313-NIA-KA, -NIB-KA, Volumetric of 3)
Vessel
-NZA-KA, -N28-KA,
. examination to
-N2C-KA, -N20-KA,
- maximum extent
-N2E-KA, -N2F-KA,-
-- practical-
-N2G-KA, -N2H-KA,
-N2J-KA, -N2K-KA, i
-N4A-KA, -N48-KA,
-N4C-KA, -N40-KA,
-N4E-KA, -N4F-KA,
-NSA-KA, -NSB-KA,
-N6A-KA, -N6B-KA,
-N6C-KA, -N7-KA,
-N8-KA, -N9A-KA, 1
-N98-KA,--N15-KA B3.100 Nozzle-inside radius sections:
1-B13-NIA-IR, -NIB-IR,
-N2A-IR, -N2B-IR,
-N2C-IR, -N20-IR, I
-N2E-IR, -N2F-IR,.
-N2G-IR, -N2H-IR,
-N2J-IR, -N2K-IR,.
-N4A-IR, -N40-IR,
-N40-IR,.-N4F-IR,
-N7-IR, -N8-IR,
-N9A-IR, -N98-IR i
a-
,%y
,y
,.v.-s r
,m.~.-
...,s
= rm
Perry Nuclear Power Plcnt, Unit 1 Page 3 of 6 TABLE 1 SUPMARY OF REllEF REQUESTS Re1ief Licensee Request System or Exam.
Item Volume or Area Required Proposed Relief-Request' Number Component Cat.
No.
to be Examined Method Alternative Status IR-001 Class 1 B-F B5.10 RPV nozzle-to-safe er,d Volumet-ic Mone.
100%
Granted (part 3 Piping welds:
.and surface surface of 3) 1-B13-N2A-KB, -N28-KB, examination and
-N2C-KB, -N2D-KB,
' volumetric
-N2E-KB, -N2F-KB, examination.to
-N2G-KB, -N2H-KB, maximum extent
-N2J-KB, -N2K-KB, practical
-N4A-KB, -N48-KB,
-N4C-KB, -N40-KB,
-N4E-KR, -N4F-KB,
-NSA-KB, -NSB-KB,
-N6A-KB, -N68-KB,
-N6C-KB IR-002 Reactor B-G-1 B6.180 Studs I through 16 Volumetric-None.
Granted 1
Recirc.
Volumetric exam.
Pump B to maximum
-exter.t practical-
~
IR-003 Reactor B-G-1 B6.40' Threads in the RPV flange
' Volumetric Mone.
Granted i
Pressure' Volumetric exam.-
l Vessel to maximum extent practical IR-004 NS, RHR, B-J 89.11 Circumferential welds:
Volumetric None.
100%
Granted HPCS, and 1-821-0025
.1-B21-0133 Gnd surface
. surface exam.
RCIRC 1-B33-0062 1-E12-0406 and volumetric.
System 1-E12-0880 1-E22-0012 exam. to maximum
' Piping-
' extent practical 89.12
-Longitudinal weidst (partial surface 1-821-0122U exam. of weld 1-833-0027U1 l-B33-0027UI, see RR 1R-006) a.
a-
,a
Perry Nuclear Power Plent,' Unit 1 Page 4 of 6 TABLE 1
~ - '
SUPMARY OF RELIEF REQUESTS Relief.
Licensee' Request System or Exam.
Item Volume.or Area Required
-Proposed Rellef Request Number Component
- Cat.
- No.
to be Examined Method-
-Alternative-Status IR-005 Reactor B-J 89.11 Circumferential welds:
Volumetric None.
100%-
Granted Recirc.
1-833-0027, -0038, -0043, and surface surface-Piping
-0049,.-0054, -0056, examination and
-0059, -0074, -0076, volumetric i
-0081, -0088,. 0097, examination to
-0100, -0105, -0111, maximum extent:
?
-0116, -0118, -0121
~ practical-t IR-006 Reactor B-J 89.12 Longitudinal weld Volumetric None. -Surface-
' Granted Recirc.
1-833-0027U1 and surface and volumetric Piping exams. to-maximum extent practical (see Relief Request.
IR-004)
IR-007 Class 1 B-K-1
'B10.10 Penetration-to-process
' volumetric examination to.
Surface or None. Surface l Granted
- Piping
- pipe' attachment welds:
Integrally.
1-E12-P411-WA, -P421-WA, maximum extent Welded
-PRB2635-WA,.
practical Attachments.
-PRB2036-WA,
-PRB2044-WA 1-E21 Pil2-WA,.
.-PRB3046-WA 1-E22-P410-WA,.
-PRB3052-WA 1-E51-P123-WA,~-P422-WA 1-N27-P121-WA, -P414-WA 1
1-G33-P131-WA 3
1-N22-P423-WA 1-B21-P122-WA, -P124-WA,
?
-P',15-WA, -P416-WA 7
4
. 2 r
..______;______s___
,-w'-
9V--
s-l-
"- ~ -
w--~--"f"*
- e e
r"'
2 arv'
-*m'--
ha-"-%e r
T
~
u v
e. w 'n '
u:[ W
Perry Nuclear Power Plant, Unit 1 I..t Page 5 of 6 TABLE 1 SUMMA R OF REllEF RECUESTS
~
-Relief Licensee
' Request System or'
-Exam.
Item Volume or Area-Required Proposed Relief Request Number Component Cat.
No.
to be Examined Method Alternative Status IR-008 Class 1 B-M-1 812.40 Valve body welds:
Volumetric None.-
Granted Valves 1-E12-F019.
. Volumetric 1-E12-F042A examination to 1-E21-F005
~ maximum ~ extent l-E22-F036 practical l-E51-F064-
. i 1-E51-F013 l-G33-F004 1-G33-F100 1R-009 Control B-0 B14.10 Housing-to-flange welds Volumetric
- None.. Surface Grani.ed -
Rod Drive (4 welds)'
or surface examination of--
Housings
~ six welds to-maximum extent
- practical IR-010 RHR Heat.
C-A C1.26 Shell cylinder-to-head Volumetric Mone.
Granted Exchanger examination to weld 1-E12-8001A-003 Volumetric maximum extent-practical IR-Oll RHR Heat C-B C2.21 Inlet nozzle welt ~
Volumetric None. 100%
Granted l
Exchanger 1-E12-B001A-004 and surface surface
_ examination and-
- volumetric examination to maximum' extent.
practical
.=.....
. m
. 1 h
1 mr
- + - -
v
- ,r e,r~.
-w r.
.c
-c-s
~.e E%r-e-
Perry Nuclear Power Plant, Unit I Page 6 of 6.
s TABLE 1
SUMMARY
OF REllEF REQUESTS
~
Relief Licensee.
Request System or.
Exam.
Item Volume or Area Required Proposed Relief Request _
_flumber ComDonent
_ Cat.
Mo.
to be Examined Method
-Alternative-Status IR-012 RHR Heat C-C.
C3.10 Seismic lugs:
Surface
.None. Surface Granted Exchanger 1-E12-8001A-SLI, -SL2, examination to
-SL3, -SL4 maximum extent practical for Class 1 C3.20 Integral attachment-all welds Piping welds:
except:
i 1-E12-H173-WA, -H289-WA,
.1-Nil-H221-WA
-H290-WA, -H359-WA, 1-Nil-H222-WA
-H360-WA, -H368-WA 1-Nil-H223-WA
-H369-WA.
1-Nil-H224-WA 1-E22-H087-WA 1-N27-H031-WA
' Nil-H221-WA, -H222-WA, 1-N27-H032-WA i
-H223-WA, -H224-WA 1-N27-H031-WA, -H032-WA i
t IR-013
~RHR, HPCS, C-G C6.10. Casing welds:
Surface Surface' exam. of.
Granted and LPCS 1-E12-C002A, -C002C weld I.D. if.
Pumps 1-E21-C001.
pumps 1-E22-C001 disassembled IR-014 HPCS C-G C6.20 Valve body weld
. Surface None. Surface Granted System 1-E22-F003-SEAM examination to Check maximum extent Valve' practical t
IR-0IS Class 2 C-C C3.20.
Penetration-to-process Surface None. Surface Granted Piping pipe attachment welds:
examination to
. Integrally 1-E12-P105-WA,.-P407-WA.
. maximum extent i
Welded 1-E21-Pil3-WA, -P412-WA practical Attachments' l-G33-P132-WA
, - ~..,.