ML20213E025
| ML20213E025 | |
| Person / Time | |
|---|---|
| Site: | Columbia  |
| Issue date: | 02/19/1982 |
| From: | Johnston W Office of Nuclear Reactor Regulation |
| To: | Tedesco R Office of Nuclear Reactor Regulation |
| References | |
| CON-WNP-0472, CON-WNP-472 NUDOCS 8203050139 | |
| Download: ML20213E025 (13) | |
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4 FEB 1 9 1982
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Docket No. 50-397 kQN
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MEMORANDUM FOR: Robert L. Tedesco. Assistant Director
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Division of Licensing FROM:
William V. Johnston, Assistant Director for Materials a Qualifications Engineering Division of Engineering
SUBJECT:
WPPSS, Washington Nuclear Project No. 2 SER Input Plant Name: Washington Nuclear Project No. 2 (WNP-2)
Suppliers: General Electric; Burns & Roe Licensing Stage: OL Docket Number:
50-397 Responsible Branch and Project Manager: LB #1; R. Auluck Reviewer:
M. R. Hum (J. F. Cook & B. Brown. INEL)
Requested Completion Date: February 12, 1982 Description of Task: Review of the Preservice and Inservice Inspection l
(a) Preservice Inspection Program - Confimatory Issue Programs Review Status:
(b) Inservice Inspection Program - To Be Reviewed After OL The Inservice Inspection Section, Materials Engineering Branch, Division of Engineering, has completed the review of the available infomation concerning
.the WUP-2 Inspection Programs. Standard Review Plans 5.2.4 and 6.6 require that we review the applicant's Preservice Inspection (PSI) Program and Inservice Inspection (ISI) Program. The applicant has submitted a PSI Program through Amendment 3 dated December 30, 1981. The PSI Program is based on a voluntary updating to Section XI of the ASME Code,1974 Edition including Addenda through Sumer 1975. We have reviewed this document and find it acceptable contingent upon completion of the balance of the examina-tions and identifying all limitations to examination with a supporting technical justification.
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Lv FEB 191982 Robert L. Tedesco The applicant has completed approximately 90% of the preservice examinations and expects to complete the remaining inspections before June 1982. Some of the limitations to future examinations have been identified. One area of particular significance relates to the design of the mechanized reactor vessel equipment. Examination of the reactor vessel shell welds will be conducted from pole tracks that are located near the longitudinal seam welds. Although a manual preservice examination was perfonned on essentially 100% of the reactor vessel welds, existing design limitations result in approximately 35% of the circumferential shell welds and 90% of the longitudinal shell welds accessible for inservice inspection. The applicant has committed to identify all impractical ASME Code examination require-ments with a supporting technical justification. We will complete our evaluation of requests for relief from impractical examinations in a SER supplement after the applicant provides this information.
The applicant has not submitted the ISI Program because the regulation requires that this document be based on the edition of Section XI of the ASME Code in effect twelve months prior to issuance of the operating license. Therefore, we will evaluate the initial ISI Program after licensing, but before the first refueling outage, when the applicable Section XI Edition can be identified based on 10 CFR 50.55a(b).
Our SER input for Sections 5.2.4 and 6.6, with a discussion of the SRP, is attached.
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William V. Johnston, Assistant Director for Materials & Qualifications Engineering Division of Engineering
Attachment:
As stated DISTRIBUTION:
cc:
R. Vollmer R. Auluck y
D. Eisenhut D. Heist, I&E, Region V MTEB Reading File W. Johnston
- 8. Brown INEL MTEB RE 1-1 WPPS B. Youngblood J. Cook, INEL C. Cheng T. Taylor, PNL W. Hazelton ISI Section Members R. Klecker
Contact:
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ATTACHMENT WASHINGTON PUBLIC POWER SUPPLY SYSTEM WASHINGTON NUCLEAR PROJECT NO. 2 SAFETY EVALUATION REPORT MATERIALS ENGINEERING BRANCH INSERVICE INSPECTION SECTION 5.2.4 Reactor Coolant Pressure Boundary Inservice Inspection and Testing This section was prepared with the technical assistance of DOE contractors f rom the Idaho National Engineering Lbboratory.
5.2.4.1 Compliance with the Standard Review Plans The July 1981 edition of the " Standard Review Plan for the Review of Safety Analysis Reports for Nuclear Power Plantsi (NUREG-0800) includes Section 5.2.4r " Reactor Coolant Pressure Boundary Inservice Inspection and Testing." Our review is continuing because the applicant has not completed all preservice examinations.
Our review to date was conducted in accordance with Standard Review Plan (SRP)
Section 5.2.4 except as discussed below.
Paragraph II.4r " Acceptance Criteriar Inspection Inte rvalse" has not been reviewed because this area applies only to inservice inspection (ISI)r not to the PSI.
This subject will be addressed during review of the ISI program af ter licensing.
Paragraph II.5r " Acceptance Criteria, Evaluation of Examination Resultsr" has been reviewed and the applicant has incorporated ASME Code Section IWB-3000r " Standards for Examination Evaluation" into his PSI Program.
Howeverr ongoing NRC generic activ.ities and research projects indicate that the presently specified minimum ASME Code procedures may not always O
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' be capable of detecting the maximum acceptable size flaws specified in the IWB-3000 acceptance standards.
For exampler ASME Code procedures specified for volumetric examination of reactor vessels, bolts and studs, and piping have not proven to be capable of detecting the maximum acceptable size flaws in all cases. We will continue to evaluate development of improved procedures and will require that these improved procedures be made a part of the inservice examination requirements. We have not reviewed the applicant's repair procedures based on ASME Code Section IWB-4000r "Repai r Procedures." Repairs are not generally necessary in the PSI program. This subject will be addressed during our review of the ISI program.
Paragraph II.8r " Acceptance Criteriar Relie f Requestsr" has not been completed because the applicant has not identified all limitations to examination.
Specific areas where ASME Code examination requirements cannot be met will be identified as performance of the PSI progresses.
Our complete evaluation of the PSI program will be presented in a supplement to this Safety Evaluation Report af ter the applicant submits the required examination information and identifies all plant specific areas where ASME Code Section XI requirements cannot be met and provides supporting technical justification.
5.2.4.2 Examination Requirements General Design Criterion 32, " Inspection of Reactor Coolant Pressure Boundary," Appendir A of 10 CFR Part 50 requires, in part, that components which are part of the reactor coolant pressure boundary O
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w be desiDned to permit periodic inspection and testing of important areas and features to assess their structural and leak-tight integrity.
To ensure that no deleterious defects develop during servicer selected welds and weld heat-affected zones (HAZ) will be inspected periodically at WNP-2.
The design of the ASME Code Class 1 and 2 components of the reactor coolant pressure boundary incorporate provisions for access for inservice inspectionsi as required by Paragraph IWA-1500 of Section XI of the ASME Code. Section 50.55a(g)r 10 CFR Part 50 defines the detailed requirements for the preservice and inservice programs for light water cooled nuclear power facility ccmponents.
Based upon the construction permit date of March 19e 1973r this section of the regulations requires that a preservice inspection program be developed and implemented using at least the Edition and Addenda of Section XI of the ASME Code in ef fect six ' months prior to the date of issuance of the construction permit.
Alsci the initial ISI program must comply with the requirements of the latest Edition and Addenda of Section XI of the ASME Code in ef fect twelve months prior to the date of issuance of the operating licenser subject to the limitations and modifications listed in Section 50.55a(b) of 10 CFR Part 50.
502.4.3 Evaluation of Compliance with 10 CFR 50.55aCg)
We have reviewed the information in the FSAR and the Preservice Inspection Program through Amendment 3 dated December 30, 1981. The preservice examination was discussed at a public meeting on October 16r 1981.
In a letter dated December 23, 1981r the applicant provided supplemental
. in format i on.
Based on the above informations we find the applicant's Preservice Inspection Program to be acceptable.
4 The applicant has performed approximately 90 percent of the preservice examination which is based on the 1974 Edition of Section XI of the ASME Coder including Addenda through Summer 1975.
This represents a voluntary updating by the applicant f rom the 1971 Edition of Section XI including Addenda through Winter 1971 required by the regulation. The applicant has incorporated into the~ PSI Program requirements from later editions oi Section XI re ferenced in 10 CFR 50.55a(b) as permitted 4
by the regulation.
The most significant alternative provisions that the applicant is using from later code editions are listed as follows:
1.
The ultrasonic examination procedures for piping welds is based on ASME Code Section XIe Appendix IIIe entitled " Ultrasonic Examination Method for Class 1 and 2 Piping Systems Made f rom Ferritic Steelse" which was introduced with the Winter 1975 Addenda to 1974 Edition.
2.
Pressure retaining bolting exceeding 2" diameter will be examined using a volumetric method when examined in placer and using 1
volumetrier surfacer and visual methods when examined after removal.
Pressure retaining botting less than or equal to 2"
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nominal diameter will be examined using a visual method. The botting will be examined to ASME Code Section XI, 1977 Edition, Summer 1978 Addenda.
Reactor Pressure Vessel closure studs and nuts will be examined to the 1977 Editioni Summer 1978 Addenda.
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Class 2 piping branch cnnnection welds will be examined to 1977 Editione Summer 1978 Addenda.
4.
Class 2 piping with wall thickness < 1/2" will be examined to 1977 Editioni Summer 1978 Addenda.
5.
The exclusion f rom examination provisions in Section XI, Paragraph IWC-1220(2), the pressure temperature exemption of 275 psi and 200=Fr respectively, was applied to RHR and ECCS lines where the actual design temperature is 212 F.
The design
' pressure is less than 275 psi in all cases.
Later Code rules allow the use of operating temperature whiche in the case of WNP-2r is much lower than 200'F for the lines exempted.
6.
RHR pump casing welds will be examined with a surface examination frcm the I.D. in lieu of a volumetric examination based on the 1977 Editione Summer 1978 Addenda.
7.
Class 1 piping less than 4" nominal pipe size will be examined by a surface in lieu of a volumetric method based on the 1977 Editione Summer 1978 Addenda.
We have reviewed the above exceptions to the 1974 Editione Summer 1975 Addenda of Section XI and find the exceptions to be acceptable alternatives since they are based on later editions of the Code referenced by 10 CFR 50.55a(b).
The applicant has identified several limitations to examination. One area of particular significance relates to the design of the mechanized reactor vessel equipment.
Examination of the reactor vessel shell welds are conducted from pole tracks that are located near the longitudinal seam welds.
Existing design limitations result in approximately 35%
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A preservice manual UT was performed on the top and bottom head welds and the nczzle safe end welds after installation. The
. applicant has committed to identify all impractical ASME Code examination requirements with a supporting technical justification.
We will complete our evaluation of requests for relief f rom impractical examination requirements in a supplement to this SER.
The initial inservice inspection program has not been submitted by the applicant. We will evaluate the program afte'r the applicable ASME Code Edition and Addenda can be determined based on Section 50.55a(b) of 10 CFR Part 50, but before the first refueling outage when ISI commences.
S'.2 : 4. 4 Conclusions The conduct of periodic inspections and hydrostatic testing of pressure retaining components of the reactor coolant pressure boundaryr in accordance with the requirements of Section XI of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code and 10 CFR Part S0r will provide reasonable assurance that evidence of structural degradation or loss of leaktight integrity occurring during service will be detected in time to permit corrective action before the safety functions of a component are compromised.
Compliance with the preservice and inservice t
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, inspections required by the Code and 10 CFR Part 50 constitutes an acceptable basis for satisfying the inspection requirements of Criterion 32 of the General Design Criteria.
5.2.4.5 References 1.
NUREG-0800, Standard Review Planse Section 5.2.4r " Reactor Coolant Boundary Inservice Inspection and Testinge" July 1981.
2.
Code of Federal Regulations, Volume 10, Part 50.
3.
American Society of Mechanical Engineers Boiler and Pressure
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Vessel Coder Section XI 1971 Edition, through Winter 1971 Addenda 1974 Editioni through Summer 1975 Addenda 1977 Editione through Summer 1978 Addenda 6.6 Inservice Inspection of Class 2 and 3 Components This section was prepared with the technical assistance of DOE contractors from the Idaho National Engineering Laboratory.
6.6.1 Compliance with the Standard Review Plans The July 1981 Edition of the " Standard Review Plan for the Review of Safety Analysis Reports for Nuclear Power Plants," (SRPr NUREG-0800) includes Section 6.6 " Inservice Inspection of Class 2 and 3 Components."
Our review is continuing because the applicant has not completed al't preservice examinations.
Our review to date was conducted in accordance with Standard Review Plan Section 6.6 except as discussed below.
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. Paragraph II.4, " Acceptance Criteriar Inspection Intervalsi" has not been reviewed because this area applies only to ISIr not to PSI. This subject will be addressed during review of the ISI program after licensing.
Paragraph II.5, " Acceptance Criteria, Evaluation of Examination Results,"
has been reviewed and the applicant has incorporated ASME Code Sections IWC-3000 and IWD-3000r " Standards for Examination Evaluatio " i tn o his n
PSI program. liowever, ongoing tJRC generic activities and research projects indicate that the presently specified minimum ASME Code procedures may not always be capable of detecting the maximum acceptable size flaws specified in these standards.
For exampler ASME Code procedures specified for volumet ric examination of vessels, bolts and studsr and piping have not proven to be capable of detecting maximum acceptable size flaws 'in all cases.
We will continue to evaluate development of improved procedures and will require that these improved procedures be made a part of the inservice examination requirements.
We have not reviewed the applicant's repair. procedures based on ASME Code Sections IWC-4000 and IWD-4000, " Repair Procedure's." Repairs are not generally necessary in the PSI program. This subject will be addressed during our review of the ISI program.
Paragraph II.9, " Acceptance Criteriar Relief Requests," has not been completed because the applicant has not identified the limitations to examination.
Specific areas where ASME Code examination requirements cannot be met will be identified as performance of the PSI progresses.
i C r complete evaluation of the PSI program will be presented in a o
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supplement to this SER after the applicant submits the required examination information and identifies all plant specific areas where ASME Code Section XI requirements cannot be met and provides supporting technical justification.
6.6.2 Examination Requirements General Design Criteria 36, 39, 42, and 45, Appendix A of 10 CFR Part 50, requi rer in part, that the Class 2 and 3 components be designed to permit appropriate periodic inspection of important components to ensure system integrity and capability.
Section 50.55a(g) of 10 CFR Part 50 defines the detailed requirements for the PSI programs for light water cooled nuclear power f acility components.
Based upon the construction permit date of March 19, 1973, this section of the regulations requires that a PSI program for Class 2 and 3 components be developed and implemented using at least the Edition and Addenda of Section XI of the ASME Code in ef fect six months prior to the date of issuance of the construction permit.
Also, the initial Inservice Inspection program must comply with the requirements of the latest Edition and Addenda of Section XI of the ASME Code in ef fect twelve months prior to the date of issuance of the operating licenser subject to the limitations and modifications listed in Section 50.55a(b) of e
6.6.3 Evaluation of Compliance With 10 CFR 50.55a(g)
L We have reviewed the information in the FSAR and the Preservice Inspection program through Amendment 3 dated December 30, 1981. The preservice examination was discussed at a public meeting on October 16, 1981.
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ember 23,1981, t above inf ormation, w a letter dated DecBased on the ac ceptable.
informatio.
Program to be ervice In n
supplemental rvice Inspection 90 percent of the pres h
applicant's Prese rced approximately of Se tion XI of t e c
rfo Edit oin the represents has pe the 1974 This applicant uhich is based on mmer 1975 of The Su Edition h ough 1971 examinat on including Addenda t r from the d by the i
applicant Winter 1971 require ASME Coder by the voluntary updating Addenda throughinto the PSI program in inct'uding has incorporated re f e renced a
Section XI applicant of Section XI most significant Code The re gul ation.
editions The m later regulation.
for ASME Code fro the requireme ts as permitted by n
using is have 10 CFR 50.SSa(b) applicant We ions that Section 5 2.4.3 the da in SER Summer 1975 Ad altern tive provisnents is discusse 1974 Editioni alternatives d
a Class 2 co po xceptions to the acceptable CTR SO.5 m
exceptions to be e
10 reviewed these find the referenced by net will @
d editions cannot of Se tion XI an d on later requi rements applicant be c
he cince they are base where the are perf ormed.where th Code The are as spe ific examinations areas l justf c
The identified af ter thetify all plant-sp pporting technica ecific ce committed to idenmet and provide su of requests for cannot evaluation to this S@
be requirements wiLL complete supplement our relief.
requirements in submittet a
We not been for tion program has applicable impractical examinainservice inspection after the 2
The initial valuate the program d based on S will e when II can be determinefueling ou We applicant.
and Addenda Code Edition before the first re 50, but Part 10 CFR
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6.6.4 Conclusions Compliance with the preservice and inservice inspections required by the American Society of Mechanical Engineers Code and 10 CFR Part 50 i
constitutes an acceptable basis for satisf9ing applicable requirements of General Design Criteria 36, 39, 42, and 45.
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6.6.5 Re ferences l
1.
NUREG-0800, Standard Review Plan, Section 6.6, " Inservice
>b Inspection of Class 2 and 3 Components," July 1981.
2.
Code of Federal Regulations, Volume 10, Part 50.
3.
American Society of Mechanical Engineers ' Boiler and Pressure i
Vessel Coder Section XI 1971 Edition, through Winter 1971 Addenda l
1974 Editions through Summer 1975 Addenda 1977 Editioni through S'ummer 1978 Addenda r
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