ML20210S273

Safety Evaluation Re Inservice Insp Program & Requests for Relief

ML20210S273
Person / Time
Site:	Hatch
Issue date:	09/29/1986
From:	Office of Nuclear Reactor Regulation
To:
Shared Package
ML20210L276	List: ML20210L271 ML20210S266 ML20210S273
References
NUDOCS 8610080069
Download: ML20210S273 (13)

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/  %, UNITED STATES 8 o NUCLEAR REGULATORY COMMISSION 5 g WASMNGTON, D. C. 20565

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SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO THE INSERVICE INSPECTION PROGRAM AND REQUESTS FOR RELIEF GEORGIA POWER COMPANY HATCH NUCLEAR PLANT, UNITS 1 AND 2 DOCKETS NOS. 50-321 AND 50-366 INTRODUCTION

. The Technical Specification for the Hatch Nuclear Plant, Units 1 and 2 states that the 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 where specific written relief has been granted by the Commission. Some plants were designed in conformance to early editions of this Code Section, consequently, certainirequirements of later editions and addenda of Section XI are impractical to perform because of the plants' design, component geometry, material of construction or the need for extensive temporary modifications and the resultant substantial exposure to plant personnel. Regulation 10 CFR 50.5ba(g)(6)(1) authorizes the Commission to grant relief from those requirements upon making the necessary findings.

By letters dated June 25, 1986, and February 7, 1986, Georgia Power Company (GPC) submitted its inservice inspection program, and additional information related to requests for relief from certain Code requirements determined to be 1mpractical to perform on the Hatch Nuclear Plant, Units 1 and 2 during the 2nd inspection interval. The program is based on the requirements of the 1980 Edition through Winter 1981 Addenda of Section XI of the ASME Code, and remains in effect until January 1,1996, unless the program is modified or changed prior to the interval end dates.

EVALUATION The inservice inspection program and the results for relief from the requirements of Section XI that have been determined to be impractical to perform have been reviewed by the staff's contractor, Science Applications International Corporation (SAIC). Presented in Attachment 2 is the contractor's Technical Evaluation Report (TER), which is their evaluation of the licensee's inservice inspection program plan and relief requests. Also, included in the TER are their conclusions and recommendations. The staft has reviewed the TER and agrees with and adopts the evaluations. The TER conclusions and recommendation to the staff concerning some of the relief requests include conditions for granting the relief which in many cases are redundant in that the condition is already required, or that the staft has determined it is not a true condition for granting specific relief, i.e., "the licensee should keep abreast of the improvements in state-of-the-art NDE 8610000069 860929 1 DR ADOCK 0500 1

techniques." The staff has determined that only certain of the recommended conditions for granting relief should be required. These required conditions are speci.fied explicitly in the relief request determinations in Attachment 1.

Except for those recommended conditions that are not specified in the relief requests determinations in Attachment 1, the staff adopts the TER's conclusions. A summary of the relief request determinations made by the staff is presented in the tables of Attachment 1. The granting of relief is based upon the presumption that the licensee will fulfill any commitments made in its basis for the relief request, the alternate proposed examination, and other commitments made in the ISI program and all the code required examinations not specifically granted relief by the Commission.

CONCLUSION Based upon the review cf the inservice inspection program and relief requests summarized, the staff concludes that relief granted from the Code required examination and testing requi.rements with the alternate methods imposed through this document, will still provide reasonable assurance of the piping and component pressure boundary and support structural integrity. The staff nas determined, pursuant to 10 CFR 50.55a(g)(6)(1), that the granting of the requested relief is authorized by law and will not endanger life or property, or the common defense and security. The staff has also concluded that granting relief is otherwise in the public interest considering the burden that could result if the requirements were imposed on the facility. During the review of the licensee's inservice inspection plan the staff has not 1dentified any significant misinterpretation or omissions of Code requirements.

Thus the inservice inspection plan is acceptable for implementation.

Attachments:

As stated Dated:

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ATTACHMENT 1 TABLE 1 CLASS 1 COMPONENTS LICENSEE PROPOSED IWB-2500-1 IWB-2500 SYSTEM OR AREA TO BE i REQUIRED ALTERNATIVE RELIEF REQUEST ITEM NO. EXAM. CAT. COMPONENT EXAMINED i METHOD EXAMINATION STATUS (RQ No.2.1.1) 81.11& B-A Reactor Circumfer- Volumetric Examination Granted Bl.12 (Unit 1 Vessel ential and to extent with only) Longitudinal possible conditions.

Shell Welds See Note 1.

(RQ No.2.1.3)

B.3.90 B-D Reactor Nozzle-to- Volumetric 85% of exam Granted, Vessel Vessel volume. provided Listed nozzles exam performed B.3.100 Nozzle In- cannot receive to extent side Radius full-Code exam. practical.

Section Unit 1 N2A N2D N2G N2K N2B N2E N2H N4B N2C N2F N2J N4D Unit 2 2N4A 2N4C

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• TABLE 1 CLASS 1 COMP 0NENTS (CONTINUED)

LICENSEE PROPOSED IWB-2500-1 IWB-2500 SYSTEM OR AREA TO BE REQUIRED ALTERNATIVE RELIEF REQUEST ITEM NO. EXAM. CAT. COMP 0NENT EXAMINED METHOD EXAMINATION STATUS (RQ No.2.1.6)

B5.20 B-F Reactor Dissimilar Surface Remote visual. Granted Metal Welds Examined for Nozzle-to- leakage during Safe End. hydrostatic Welds 1 testing. Nozzles 4 in dia. affected:

Unit 1 H1D N12B N11A N16A N12A N16B N11B Unit 2 2N10 2N12A 2N11A 2N128 2N11B 2N16A 2N16B

.c , e TABLE 1 CLASS 1 COMPONENTS (continued)

LICENSEE i PROPOSED IWB-2500-1 IWB-2500 SYSTEM OR AREA TO BE REQUIRED ALTERNATIVE RELIEF REQUEST ITEM NO. EXAM. CAT. COMPONENT EXAMINED METHOD EXAMINATION STATUS (RQ No.2.1.5)

B8.10 B-H Reactor Integrally Volumetric Exam area A-B Granted Vessel Welded or surface, fig. IWB-2500-13 Attachments as applic- will be 100%

able surface.

Ultrasonic to extent practical.

(RQ No.2.1.7) 89.11 B-J Piping Welds within Surface Visual exam Granted (Unit 1 only) > 4 in. containment and volu- when leakage Circum- penetrations. metric test prior ferential 12 welds to startup Welds after refueling.

All pipe-to-penetration welds outside contain-ment exam volu-metric. Surface exam accessible j

welds of pene-tration assembly.

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-n., e TABLE 1 CLASS 1 COMPONENTS (continued)

LICENSEE PROPOSED IWB-2500-1 IWB-2500 SYSTEM OR AREA TO BE REQUIRED ALTERNATIVE RELIEF REQUEST ITEM NO. EXAM. CAT. COMPONENT EXAMINED METHOD EXAMINATION STATUS (RQ No.2.1.8) External B12.20 B- L-2 Pump Internal Visual, visual during Granted Casings surfaces VT-3 hydro provided any valve (s)

B12.50 B-M-2 Valve Internal Visual, or pump (s)

Bodies, surfaces VT-3 disassembled Exceeding have visual 4 in. examination (RQ No.2.1.9)

B14.10 B-0 Reactor Welds in Volumetric Visual during Relief not Vessel Control or surface hydrostatic in required.

Rod Drive accordance with Components Housing IWB-5000 meet exemption requirements IWB-1220(a)

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. TABLE 2 CLASS 2 COMPONENTS LICENSEE PROPOSED IWC-2500 IWC-2500 SYSTEM OR AREA TO BE REQUIRED ALTERNATIVE RELIEF REQUEST ITEM NO. EXAM. CAT. COMPONENT EXAMINED METHOD EXAMINATION STATUS (RQ No.3.1.1) Pressure Retaining C1.10 C-A Residual Shell and Volumetric Volumetric to Granted C1.20 Heat Head Circum- the extent C1.30 Removal (RHR) ferential possible.

heat Welds. Tube- Surface except exchanger sheet to-Shell shell weld.

Weld Visual during system test per IWC-5000 (RQ No.3.1.2) C-C Pere- Piping Surface Visual Granted only C3.20 trations Integrally RCIC (IE51) into torus Welded and HPCI (1E41) by suction Attachments Hatch 1 provided lines for surface exam RHR, Core (mag particle)

Spray, HPCI, on attachment RCIC plates. Denied core Spray (1E21)

& RHR (IEll)

. Hatch 1 and all welds at Hatch 2.

Insufficient justification.

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. TABLE 2 j CLASS 2 COMPONENTS (continued)

LICENSEE PROPOSED IWC-2500 IWC-2500 SYSTEM OR AREA TO BE REQUIRED ALTERNATIVE RELIEF REQUEST l ITEM NO. EXAM. CAT. COMPONENT EXAMINED METHOD EXAMINATION STATUS i (RQ No.3.1.3) Pressure C6.10 C-G Pumps Retaining Surface Visual when Granted (Hatch 2 Core Spray Pump Casing disassembled i

only) and RHR Welds for main-tenance.

Visual during hydro

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TABLE 3 CLASS 3 COMPONENTS LICENSEE -

l PROPOSED IWD-2500-1 IWD-2500 SYSTEM OR ITEM TO BE REQUIRED ALTERNATIVE RELIEF REQUEST ITEM NO. EXAM. CAT. COMPONENT EXAMINED METHOD EXAMINATION STATUS

(RQ No.4.1.1)

D1.10 D-A Pressure Pressure Visual, Accessible Relief denied

, D2.10 D-B Retaining Retaining; VT-2 Piping < 2 in. for system j D3.10 0-C Components Boundary Visual under pressure test.

normal operating pressure.

IWD-5000 LICENSEE PROPOSED SYSTEM OR PRESSURE TEST ALTERNATIVE RELIEF REQUEST j COMPONENT REQUIREMENT TEST STATUS (RQ No.4.1.3)

D1.10 D-A Plant IWD-5223 of 1980 Hydrostatic test Granted i D2.10 D-B Service requires Plant on portions of

D3.10 D-C Water Service Water system which have i System be hydrostat- butterfly valve ically tested 10 inch or greater, at a pressure will be at normal 1.10 times operating pressure.

design pressure 4

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TABLE 4 STANDARDS FOR EXAMINATION EVALUATIONS LICENSEE PROPOSED RELIEF SYSTEM OR ~ ALTERNATIVE RELIEF REQUEST REQUEST NO. COMPONENT REQUIREMENT EXAMINATION STATUS 5.1.1 Spring Supports Proper hot Visual to verify Granted or snubbers or cold indicator in position operational per design range 5.1.2 Snubbers In preparation Functional No relief required.

50 kips or testing require- Testing per T.S.

greater ments of Techni- should meet Code cal Specification requirements if 3/4.6L for Unit 1 Licensee ensures

! Snubbers Representative 3/4.7.4 for that 10% of all

less than sample of 10% Unit 2. snubbers rated

{ 50 kips tested each less than 50

inspection kips are examined.

period.

3 8.1.4 Containment 10CFR50.55a None No relief required i does not impose

} requirements of

! subarticle IWE 1

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TABLE 5 VOLUMETRIC EXAMINATION METHODS l

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! LICENSEE PROPOSED RELIEF j ALTERNATIVE EXAMINATION REQUEST i

SUBJECT REQUIREMENT METHOD STATUS (RQ No.8.1.1) Ultrasonic examina- Calibration block with Granted Ultrasonic tion shall be con- diameters thickness Calibration ducted in accordance and side drilled holes Blocks with Appendix III or in accordance with 1974 Section V Code Edition.

(RQ No.2.1.4) Ultrasonic Examina- Austenitic and dissimilar Relief Ultrasonic Exam tion Requirements piping welds will be not Requirements of shall be in accord- examined in accordance required i

Austenitic and ance with Article 5 of with Appendix III.

Dissimilar Metal Section V amended, Piping Welds Appendix III Supple-ment 7 amended.

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GENERAL RELIEF REQUESTS i

i LICENSEE PROPOSED RELIEF ALTERNATIVE REQUEST SUBJECT REQUIREMENT PROCEDURE STATUS i

! (RQ No.8.1.5) IWA-6320 requires Owner's report will be Not granted i

Due Date for Owner's Data shall filed with NRC within Owners ISI be filed with NRC 120 days of completion Report, Form within 90 days of of outage in which in-NIS-1 completion of spections are performed j inservice inspection.

1 (RQ No.8.1.2) Inspection intervals ISI plan for Hatch 2 will Granted 4 Hatch Unit 2 shall be each 10 nove ahead by 40 months i

Change Start years following to allow common interval j Date 2nd 10- initial start of dates for Hatch 1 and 2.

i yr Interval power unit commercial Hatch 2 RPV welds scheduled l operation for final 40 month period of l

l 1st interval will be' scheduled for 1st 40 month period of 2nd j interval.

! (RQ No.8.1.3) 10 CFR 50.59 allows Records of all changes

' Granted Reporting Re- changes to facility will be maintained. provided any quirements and procedures Changes affecting ASME additional of Procedural without NRC approval Section XI will be exams required j Changes Affect- provided that there incorporated in the ISI which result i

ting ISI Pro- are no unreviewed program plan whenever from changes in grams safety issues. The it is updated. or equipment i

facility ISI program / are performed plan should be revised prior to the

to include changes. end of the ten year

) interval.

Notes:

1. Relief is granted provided that the licensee examines, to the extent possible, additional RPV welds, such that the length of total welds examined will equal the length of the individual welds requiring examination.

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