ML20034B773
| ML20034B773 | |
| Person / Time | |
|---|---|
| Site: | Sequoyah  |
| Issue date: | 04/19/1990 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20033E006 | List: |
| References | |
| NUDOCS 9004300357 | |
| Download: ML20034B773 (7) | |
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ENCLOSURE SAFETf-EVALUATION REPORT BY THE OFFICE OF NUCLEAR REACTOR REGULA FIRST TEN-YEAR INTERVAL INSERVICE: INSPECTION PROGRAM, REVISION 13 AND FOURTEEN ASSOCIATED REQUESTS FOR-RELIEF
' TENNESSEE VALLEY AUTHORITY SEQUOYAH NUCLEAR PLANT, UNIT 2 DOCKET NO. 50-328
1.0 INTRODUCTION
Technical Specification 4.0.5 for the Sequoyah Nuclear Plant.-Unit 2 states that the surveillance requirements for inservice inspection and testing of the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code (Code) Class 1, 2.-and 3 components shall be applicable as follows:- Inservice Inspection of ASME Code Class 1, 2, and 3 components...., shall be perfonned in-accordance with Section XI of the ASME Boiler and Pressure Vessel. Code and 1
applicable Addende as required by 10 CFR 50.55a(g), except where a specific 1
written request for relief has been granted by(1) 10CFR50.55a(g)(6)(1)or10CFR50.55a(a)(3) the Commission pursuant to 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 3
Section XI, of editions and addenda.that become effective in the i
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the extent practical within the limits of design, geometry, and materials of construction of the components.
The regulations require that inservice examination of components shall comply with the requirements in the latest-edition and addenda of Section XI of the Code -incorporated by reference in 10 CFR 50.55a(b) on the date 12 months prior to the date of eissuance of the operating license.
Pursuant to 10 CFR 50.55a(g)(5), if the licensee determines that conformance k
with an examination requirement of Section XI of the Code is not practical-for its facility, information shall be submitted to the Commission in' support of the determination (s) and a request made for relief from'the Code require-After evaluation of the determination (s), pursuant to 10 CFR ment.
t 50.55a(g)(6)(1), the Copmission may grant relief and may impose alternative requirements that 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.
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- o. Pursuant to 10 CFR 50.55a(a)(3), if the licensee detemines that=an.
L alternative.to the ASME Code requirements would provide an acceptable level of quality and safety, information shall be submitted to the Comission in support of the determination (s) and a request made for relief from the Code requirements.
After evaluation of the determinations, pursuant to:10 CFR 50.55a(a)(3)(1), the Comission may grant relief from the Code.'
l The licensee Tennessee Valley Authority, (TVA)~ has prepared the Sequoyah.
Nuclear Plant, Unit 2, first 10-Year Interval Inservice Inspection (ISI) Pro-gram, Revision 13, to meet the requirements of the 1977 Edition, Summer 1978--
Addenda of Section XI of the Code with the following. exception:
the extent of, examination for Code Class 11 piping welds have been determined by the'1974 1
Edition through Summer 1975 Addenda as required _by 10 CFR 50.55a(b).1 The staff, with technical assistance from its contractor, Science Applications {
l International Corporation (SAIC), had evaluated the first'10-year Interval ISI Program, Revision 13, including additionalainformation'related to the plan, for Unit 2 and the requests for relief from certain ASME-Code requirementst which were determined to be impractical at Unit 2 during the.first' inspection' interval.
This Program was described in the TVA submittal dated November 9.-
1988 for Revision 13 and the response dated May 5,.1989 to the staff's ques-tions. TVA submitted Revision 14 of the Unit 2 ISI Program in its letter--
dated June 12, 1989 but the changes to the program were not significant.-
l 2.0 EVALUATION
-l The ISI Program has been evaluated for..(a) application of the correct Sec-l tion XI Code edition and addenda, (b) compliance with examination and test
)
requirements of Section XI, (c) acceptability of the examination sample, (d):
compliance with prior ISI commitments made by _TVA, (e) correctness of the application of system or component examination exclusion criteria, and (f) adequate information to support requests for relief from Section XI Code requirements.
The information'provided by the licensee in support of requests q
for relief from impractical requirements or for alternative requirements i
providing acceptable levels of quality and safety has been evaluated and the bases for granting relief from those requirements are documented in the attached SAIC Technical Evaluation Report (TER) SAIC-89-1473. A list of all the applicable TVA submittals is given in the TER. The-NRC staff concurs with and adopts the findings and recomendations contained in the TER.
Table 1 presents a sumary and status of the relief requests as determined by l
the staff. The 14 relief requests have been reviewed-and all are acceptable except for ISI-2, ISI-7, ISI-11, and ISI-12. One relief request was with-;
drawn (ISI-11), one request is not needed (ISI-12), and two requests are -not needed at this time anq are postponed (ISI-2 and ISI-7). The. table lists the restrictions, if any, on each relief request that is acceptable. Where the a
relief request status is " Granted with augmented requirements", the augmented l:
requirements are as' recomended in the SAIC TER. The granting of these relief requests by the Comission, as specified in Table 1, is contingent upon all other requirements of Section XI being met for inservice tests and system pressure tests of the components affected by these relief requests, j
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Of the ten relief requests which are acceptable,-two requests provide alterna--
tive requirements which give an acceptable level of quality and safety at 1
Unit 2.
These are. requests ISI-9 and 151-14. Of the remaining eight. requests,-
1 151-1, ISI-3 to ISI-6,'ISI-8 ISI-10 and 151-13, the Code requirements are impractical to perform at Unit 2 and the alternative requirements will-nott.
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- endanger life or property, or the common defense and securi1;y, and are in the'-
A public interest considering the burden that could result on TVA:if the Code -
requirements were imposed on Unit 2.
The acceptability. of the alternate requirements and the burden on TVA if the Code requirements were imposed on:
Unit 2 are discussed in the attached TER.
3.0 CONCLUSION
4 s
The staff concludes that the Sequoyah Nuclear Plant, Unit 2 first 10-Year 4
Interval Inservice Inspection Program, Revision 13, with the additional-infonnation the program'provided and the specific written reliefs constitute the basis ofs com a
fication 4.0.5 and is, therefore, acceptable.
For the Unit 2 ISI Program, TVA submitted 14 requests for relief from the requirements of the Code:
151-1 to ISI-14
.As discussed above, the staff has determined that these requests are acceptable except for the following four requests:
ISI-2, ISI-7, ISI-11, and ISI-12.
Granting relief from Code -
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requirements is authorized by law where (1) the proposed alternative would 50.55a(a)(3)(1)ptable level of quality and safety (pursuant.to 10 CFR) and (2) t provide an acce
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tive requirement will not endanger life or property, or the common c'efense and security,andisinthepublicinterest(pursuantto10:CFR50.55a(g)(6)(1)).
For two requests, ISI-9 and ISI-14, the staff concludes that the-proposed alternatives to the Code requirements will provide an acceptable level:of-t quality and safety at Unit 2.
For the remaining eight: requests, ISI-1,1 151-3 to ISI-6 ISI-8, ISI-10, and ISI-13, the staff concludes that the Code-require-ments are impractical to perform at Unit 2 and the alternative requirements 1
will not endanger life or property, or the common defense ard security, and are in the public interest considering the burden that could result on TVA if the Code requirements were imposed on Unit 2.
L Therefore,pursuantto10CFR50.55a(a)(3)(1)and10CFR50.55a(g)(6)(1)of the Commission's regulations, TVA should be granted the following requested relief from the Code:
requests for relief ISI-I,-ISI-3 to ISI-6, ISI-8 to ISI-10, ISI-13, and ISI-14. Where the relief request status is " Granted with augmented requirements", the augmented requirements are as recommended in the attached TER. The granting of these relief requests is contingent upon all other requirements of Section XI being met for inservice tests.and system pressure tests of the components affected by these relief requests.
7 The staff also concludes that the Sequoyah Unit 2 Inservice Inspection Program, l
Revision 13, with the additional information in the May 5, 1989 letter and the l
reliefs granted constitute part of the basis for TVA meeting the requirements l
of 10 CFR 50.55a and the Unit 2 Technical-Specifications at Unit 2.
With reliefs granted, the staff concludes that Unit 2 is is compliance with the Code of record for Unit 2, cited above in Section 1.0.
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4.0 REFERENCE 1.
Science Applications International Corporation,' "First Interval Inservice
- Inspection Program,- Sequoyah Nuclear Station Unit 2", Technical Evaluation-
. Report SAIC-89/1473, Idaho Fallsi, Idaho, July 1989.
- 2.
Letter from R. Gridley (TVA) to NRC,
Subject:
Augmented and-Accelerated =
In-Service Inspection Program for Unit 2.' dated November 9,1986.-
3.
Letter. from C. H. Fox'(TVA) to NRC,
Subject:
Response to NRC Request for Additional-Information, dated May -5,1989.
Principal Contributor:
D. Smith Dated:-
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I SEQUOYAH NUCLEAR PLANT, UNIT 2 Page.1 of 3 TABLE 1 SUPMARY OF RELIEF REQUESTS (SYSTEM / COMPONENTS)'
Relief Licensee.
Request Item Exam.
System or.
Volume'or Area Required
. Proposed Relief Request:
Number No.
Ca t.
Component to be Examined Method.
Alternative Status 9
10 CFR 50.55a(g)(6)(1) Requests 151-1 B12.20 B-L-2 Pumps
' Internal Pressure Visual
' Visual exam Granted with augmented Boundary Surfaces of surfaces if -
pump opened for-requirements maint.
If not.
UT thickness-L from exterior ISI-2 B12.40 B-M-2 Valves Internal Pressure-Visual.
Norr Postponed until.
Boundary Surfaces specific relief l requests are presented.towards end of interval ISI-3 B5.50 B-F Binetal
-Pressure. retain-Surface' Inspect to ex-Granted with
-Welds ing bimetallic Volumetric-tent possible'
. augmented
. welds in piping:
requirements' 89.10 8-J Welds Pressure retain-Surface.
Inspect to ex -
Granted with i.
B9.20
' ings. welds in
~ Volumetric' tent possible augmented 89.30-piping.
. requirements ISI-4 C1-10 C-A-
' Steam LClass 2 Circum.
Volumetric ~ ' Inspect to ex-Granted with l
Generator-
.-shell welds tent possible augmented requirements 4
151-5 Bl.21 B-A.
Reactor Bottom head
-Volumetric Inspect to ex-
-Granted with-Vessel Circum. weld tent possible
. augmented trequirements i
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SEQUOYAH NUCLEAR PLANT, UNIT 2 Page 2 of 3 TABLE I SupetARY OF RELIEF REQUESTS (SYSTEM / COMPONENTS) 1 Relief Licensee Request Item Exam.
System or Volume or Area Required Proposed Relief Request Number No.
Cat.
Component to be Examined
' Method Alternative Status ISI-6 Bl.14'O B-D
-Steam Nozzle inside Volumetric Postpone until Granted with generator radium section next interval augmented requirements ISI-7 B9.10 B-J Piping Reactor coolant Volumetric None Postponed until 1
i loop piping welds
' fourth interval' ISI-8 B12.10-B-L-1 Pumps Pressure retain-Surface Surface exam Granted with'-
ing welds on pump.:
Volumetric only
. augmented casings requirements-151-10 Bl.30 B-A Reactor Flange to upper Volumetric-Delay volume.
. Granted-vessel hell-weld at Table
-tric to end of s
IWB-2412-1 interval frequency.
ISI-11 Withdrawn 151-12' C1.10 C-A-Pressure ~
Shell weld at Volumetric' None Relief not
~
C1.20 C-C vessels
- structural dis-Volumetric:
required:
C1.30.
C-C continuities and
~ Volumetric.
C3.10
-C-E attachments
. Surface a
A CB Pressure RHR HTEX nozzel
. Surface Surface exam Granted '
ISI-13 C2.20 vessels to vessel' welds Volumetric :
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9 SEQUOYAH NUCLEAR PLANT, UNIT 2 Page 3 of 3 TABLE 1
SUMMARY
OF RELIEF REQUESTS (SYSTEM / COMPONENTS)~
~
Relief Licensee Request Volume or Area Proposed Relief Request Number Item to be examined Alternative Status 10 CFR 50.55a(a)(3)'(1) Requests ISI-9 UT cal-Use of 5-percent Continue use of Granting provided ibration notches-in' lieu existing blocks existing blocks block of side-drilled
. seet applicable
- holes Code requirements ISI-14 Exam.
Table IWB-2412-1 Accelerated Granted schedule and IWC-2412-1 inspections for piping welds.
change the and supports and schedule major. component supports T
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