ML20134H357
| ML20134H357 | |
| Person / Time | |
|---|---|
| Site: | Pilgrim |
| Issue date: | 08/13/1985 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20132D050 | List: |
| References | |
| NUDOCS 8508280384 | |
| Download: ML20134H357 (5) | |
Text
g Pf G UNITED STATES 8
. NUCLEAR REGULATORY COMMISSION o
r, wAsmNGTON, D. C. 20555
\\...../
SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION 4
RELATED TO REQUESTS FOR RELIEF FROM INSERVICE INSPECTION REQUIREMENTS BOSTON EDISON COMPANY PILGRIM NUCLEAR POWER STATION DOCKET NO. 50-293
1.0 INTRODUCTION
~
Technical Specification 4.6.G for the Pilgrim Nuclear Power Station states that inservice examination of ASME Code Class 1, 2 and 3 components shall be performed in accordance with Section XI of the ASME Boiler and Pressure Vessel Code and applicable Addenda as required by 10 CFR 50.55a(g) except whers specific written relief has been granted by the Commission. Certain
~
vequirements of later editions and addenda of Section XI are impractical to perform on older plants because of the plants' design, component geometry, and materials of construction. Thus, 10 CFR 50.55a(g)(6)(1) authcrizes the Commission to grant relief from those requirements upon making the necessary findings.
By letters dated December 3, 1982, August 4, and December 1, 1983, June 28, 1984 and February 12, 1985, the Boston Edison Company (BEco, the licensee) i.
submitted its inservice inspection program, revisions, and additional information related to its requests for relief from certain Code requirements which were considered impractical to meet on the Pilgrim Station duri.ng the second.10-year inspection interval. The program is based on the requirements of the 1980 Edition through Winter 1980 Addenda of Section XI of the ASME-Code, and remains in effect until December 8, 1992' unless the program is modified or changed prior to the interval end j
I' date.
2.0 EVALUATION Request for relief from the requirements of Section XI which the licensee considers impractical to perform have been reviewed by the staff's contractor, Science Applications, Inc. The contractor's evaluations of the licensee's requests for relief and his recommendations are presented in the enclosed Technical Evaluation Report (TER). The staff has reviewed the t
TER and agrees with the evaluations and recommendations. A summary of the determinations made by the staff is presented in the following Table 1 (Class I components) and Table 2 (Class 2 components). No religf was requested relative to Class 3 components, component supports, or' pressure tests. Subject to the provisions therein, we have determined tKat all of the relief requests should be granted except for those assocta;ted with pressure retaining welds in 89.10 through B9.40 and C5.10 through C5.32.
L i
8508200384 850013 ADOCK 050 g 3 DR
2-
3.0 CONCLUSION
Based on our review, we conclude that:
(1) granting relief where the ASME Code examination and testing requirements are impractical is authorized by law and will not endanger life or property or the common defense and security, and is otherwise in the public interest considering the burden that could result if they were imposed on the facility, and (2) the alternate methods imposed through this document give reasonable assurance of the piping and component pressure boundary and support structural integrity.
Principal Contributor:
G. Johnson Dated:
August 13, 1985 N
b.
e o
-E
=
.me g
m.
- e e
. aw' a
h 9
t l
l l
I
~
g 1, I
[
4 TABLE l'
?
CLASS 1 COMPONENTS LICENSEE PROPOSED IWB-2500-1 IWB-2500-1 SYSTEM OR AREA TO BE REQUIRED ALTERNATIVE RELIEF REQUEST ITEM NO.
EXAM. CAT.
COMPONENT EXAMINED METHOD EXAMINATION STATUS Bl.11 B-A Reactor 100% of Volumetric Requirements ~
Granted Vessel Circumfer-of 1974 Edition ential of Section XI, Beltline 5% of Length Region Weld Bl.12 B-A Reactor 100% of Volumetric Requirements Granted Vessel Longitudinal of 1974 Edition Beltline of Section XI, Region Weld 10% of Weld 81.22 B-A Reactor Bottom Head Volumetric Examine From Granted Vessel Circumfer-One Side ential Welds Only 83.90 B-D Reactor 100% of Volumetric Examine Granted Vessel Nozzle-To-To Extent Vessel Welds Practical
'!.' ? '
l f
4
I I
l.i.'
I 4
TABLE 1
, CLASS 1 COMPONENTS (C0lGINUED)
LICENSEE PROPOSED IWB-2500-1 IWB-2500-1 SYSTEM OR AREA TO BE REQUIRED ALTERNATIVE RELIEF REQUEST ITEM NO.
EXAM. CAT.
COMPONENT EXAMINED METHOD EXAMINATION STATUS B9.10 B-J Piping Circumfer-Volumetric Visual of Granted Pene-ential Area during provided B9.21 trations:
Welds in Surface Hydrostatic First X-12 triple-flued (89.10)
Testing pressure-X-51A,B ; Head retaining X-17 Pehetration Surface weld outside X-53
- is examined X-14 to code X-42
- Requirements X-9A,B X-7A,B,C,0 X-52
- (Penetrations Covered Under Item No. B9.21) 89.10 B-J Class 1 Pressure Surface Volumetric Not Granted thru Piping Retaining and 89.40 Welds Volumetric or Surface B12.20 B-L-2 Recir-Internal Visual Visual Granted culation surfaces during when pump
' 'i Et '.?
- Pump Ten-Year is disassem-Interval bled for maintenance B12.40 B-M-2 Valves
. Valve Body Visual Visual when Granted Internal valves are I siirfaces disassembled for maintenance h
pa,
~
I s
.I 1, t i
TABLE 2
, CLASS 2 COMPONENTS LICENSEE PROPOSED IWC-2600-1 IWC-2520-1 SYSTEM OR AREA TO BE REQUIRED ALTERNATIVE RELIEF REQUEST ITEM NO.
EXAM. CAT.
COMPONENT EXAMINED METHOD EXAMINATION STATUS C5.10 C-F Class 2 Pressure Surface Volumetric Not Granted thru Piping Retaining and C5.32 Welds Volumetric (C5.21 &
C5.22)
Surface (Other Items)
C5.11 C-F Containment Pressure Surface Visual Granted Atmospher-Retaining During C5.12 ic Welds Pressure Control Tests I
y,,..
,,e t*
g g