ML17194B282

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Forwards Revised Safety Evaluation of SEP Topic III-1, Quality Group Classification of Components & Sys. All Open Items Resolved,Except for Fracture Toughness Requirement & Radiography,Which Will Be Resolved in Integrated Assessment
ML17194B282
Person / Time
Site: Dresden Constellation icon.png
Issue date: 09/02/1982
From: Oconnor P
Office of Nuclear Reactor Regulation
To: Delgeorge L
COMMONWEALTH EDISON CO.
References
TASK-03-01, TASK-3-1, TASK-RR LSO5-82-09-019, LSO5-82-9-19, NUDOCS 8209080368
Download: ML17194B282 (12)
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Docket No. 50-237 LSOS-82-09-019 Mr. L. DelGeorge Director *of Nuclear Licensing Conunonwealth Edison Company Post Office Box 767 Chicago, Illinois 60690

Dear Mr. DelGeorge:

September 2, 1982 SUBJECT.:

SEP TOPIC 111-1, QUALITY GROUP CLASSIFICATION OF COMPONENTS AND SYSTEMS - DRESDEN NUCLEAR POWER STATION UNIT 2

References:

(1) Letter, P. O'Connor to L. DelGeorge, "SEP Topic III-1, Quality Group Classification of Components and Systems (Dresden Unit 2)*,

11 dated March 9, 1982.

(2) Letter, T. Rausch to P. O'Connor, "Dresden 2, SEP Topic: Ill-1, Quality Group Classification of*

Components and Systems," dateiJ July 16, 1982.

Enclosed is the staffis revised safety evaluation of SEP Topic III-1 for the Dresden Unit 2 plant. Our evaluation is based upon the original as-sessment in Reference 1 and incorporates the additional information provided in Reference ~. The...staff has concluded that, based upon a sampling review of thei~nftiro!nation in Reference 2, all of the open items addressed 1n Reference--1',' except for fracture_ toughness requirements and radiography, have been resolved. The remaining open items will be resolved in the Integrated Assessment of Dresden Unit 2.

Sincerely,

. Original slgne'd oy::

Paul W. O'Connor, Project Manager Operating Reactors Branch No. 5 Division of Licensing s-~4-f A.tJ:~~

Enclosonte:

As stated cc w/enclosure:

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SEPB NRC FORM 318 (10-80) NRCM 0240

  • OFFICIAL RECORD COPY USGPO: 1981-335-960
  • Mr. L. De 1 George cc Robert G. Fitzgibbons Jr.

Isham, Lincoln & Beale Counselors at Law Three First National Plaza Suite 5200 Chicago,~111inois 60602 Mr *. B. B. Stephenson Plant Superintendent Dresden Nuclear Power Station Rural Route #1 Morri~. Illinois 60450

  • The.Honorable Tom Corcoran.

United States House of Representatives Washington, D. C.

20515

  • u *. S. Nuclear Regulatory Commission Resident Inspectors Office Dresden Station RR 11 Morris, Illinois 60450 Mary Jo Murray Assistant Attorney General Environmental Control Division 188 w.*Randolph Stree~

Suite 2315

.. Chicago, Illinois 60601

  • . Chainnan Board of Supervisors of cGrundy County Gruney *tounty Courthouse
  • Morris, Illinois 60450 John F. Wolf, Esquire 3409 Shepherd Street Chevy c*hase, Maryland 20015 Dr. Linda w. Little 500 Hennitage Drive Raleigh, North Carolina 27612.

Judge Forrest J. Remick

.The Carriage House - Apartment 205 2201 L Street, N. W.

Washington, D. c. 20037 Dresden 2 Docket No. 50-237 Revtsed 5/19/82 Illinois* Department of Nuclear Safety 1035 Outer Park Drive, 5th Floo~

Springfield, Illinois 62704 U. S. Environmental Protection Agency Federal Activities Branch.

Region V Office ATTN:

Regional Radiation Representative 230 South Dearborn Street Chicago, Illinois 60604 James G. Keppler, Regional Administrator Nuclear Regulatory Commission, Region Ill 799 Roosevelt Street Glen Ellyn, Illinois 60137

SYSTEMATIC EVALUATION PROGRAM TOPIC UI-1 DRESDEN NUCLEAR POWER STATION UNIT 2 Topic:. Ill-1, Classification of Structures, Com onents*and S stems

l.

Seismic and Qualit I'NTRODUCTlON I

SEP plants were gener~lly designed and constructed during the time sp~n from the late l950's to late 1960'*s. They were designed ~c;cording to codes and criteria tn effect at that time; however, since then, ttie codes and criteria have been revised to incorporate the results' of additional research. Thus, earlier plants may have been des1"gned accordi'ng to criteria and codes no longer accepted by the NRC.

The purpose of Topic lII-1 is the review of the classif.icatton of structures, systems and components of as-built plants as compared to.

current appropriat~ classifications, codes and standards for seismic and quality groups.

The review of seismic classification is being addressed in the seismic. topics.. Accordingly, this topic was. limited to an evaluation of the ~uality group classification of systems and components.

II.

REVIEW CRITERIA The review crit~ria are presented in the Appendtx.of franklin Techni~al Evaluation Report - C527-430, "Quality Group Classtfication of Components and Systems - Dresden 2 Plant.

11 (Tliiis TER i's Enclosure 2 of a March 9, 1982 letter from P. O!Connor to L. DelGeorge, "SEP Topic lll-1, Quality*

Grou.p Classification of Components and Systems (Dresden Unit 2) 11,)

III.

RELATED SAFETY TOPICS AND INTERFACES The scope of review for this topic was limited to avoid duplication of effort since some aspects of the review were performed under related topics.

The related topics and the subject matter are identified below.

III-6 Seismic Design Considerations III-7.B Design Codes, Design Criteria, Load Combinations and Reactor Cavity Design Criteria V-6 Reactor Vessel Integrity V-8 Steam Generator Integrity IV.

. REVIEW GUlDELI'NES The review guidelines are presented in Section 3 of Franklin Report -

C-5257-430, "Quality Group Classtfi'cation of Components and Systems -

Dresden. 2 Plant.

11 Quality Assurance was not reviewed si'nce it is addressed in Topic XVII, Operational Quality Assurance (QA) Program" and because QA during design and construction is outside of the scope of SEP.

V.

EVALUATION The basic input for this report is Table 4.1 in Section 4 of the Frankl in Report.

Table 4. l is a compilation of all systems and components whi'ch are required to be classified by Regulatory Guide l. 25 and tl'ie.

original codes and standards used i'n the plant design. After compari'ng the original codes with those currently used for licensing new facilities, the fol lowing areas were identified where the requirements have changed:

l) Fracture Toughness

2)

Quality Group Classification

3)

Code Stress Limits

4)

Radiography Requirements

5)

Fatigue Analysis of Piping Systems An evaluation of each of these areas is presented in Section 5 of the Franklin Report, with a detailed discussion included in the Appendix of that report.

We have determined that changes in the following areas have not significantly affected the safety of the systems arid components reviewed in this report:

1) Quality Group Classification
2)

Code Stress Limits

3)

Fatigue Analysis of Piping Systems As noted earlier, we have decided that the area of qua l Hy ass*urance.need not be reviewed for this report.

In the remaining two areas we have concluded the following:

l) Fracture Toughness - The ASME Boiler and Pressure Vessel *code, Section Ill, requires fracture toughness testing of pressure retaining material and material welded thereto. Attached to this evaluation is an updated

!Table 5.1 of tlie FrankHn Report.

The fracture _toughness requiTements for the Reactor Water Cleanup System, the Reactor Shutdown Cooli'ng System and the Reactor Buildi'ng Closed Cooling Water System have not been provided for our review.

For those components identified tn the revised Table 5.1 as requiring fracture toughness testing, the actual requirements imposed on those components and the test results have not**

been provided.

This i'nformation is necessary to complete our evaluation, because of the radical change in fracture toughnes~ test requirements that occurred in 1972.

The remaining components and systems.identified in Table 5. l meet current fracture toughness requirements.

2)

Radiography - The ASME Boiler and Pressure Vessel Cod~ requires that radiographic inspections of certain component parts and jotnts be performed.

We have revi"'ewed, on a sample basis, the fabricatfon and construction inspectton program implemented at Dresden Untt 2.

We fi'nd that the program is generally in agreement with current require-ments except that the following items have not been addressed:

a) Class 2 vessels bui"lt to Class C requirements and containi~ng Category C jotnts, along with the examination technique employed, should be identtfted.

b)

The actual examinati'on given to the reci'rculatton system pump casing (this i's a Class 1 component built to Class C requtrements).

Any other di'screpanci'es that exist between the actual i-nspectton pro-cedures used and those currently required duri'ng fabrication and ~on struct~on are few and their safety significance is small beca~se Dresden Unit 2 has implemented an i*nservice inspecti'on program that meets the current requfrements of 10. CFR Part 50, Sectton 50.55a(g}.

VI.

  • CONCLUSION We have evaluated the quality group classification of the components and systems in Dresden Unit 2 and, wi'th the exception of tne two open i'tems discussed above, we conclude that Dresden Unit 2 meets current requirements.

The open items will be resolved i'n the Integrated Assessment.

t 1

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~tructuree, Systems, and Cbmponents RECIRCULATION SYSTEM Recirculation System Piping Recirculation System

.Valves Recirculation System Pumps EMERGENCY SYSTEMS Isolation Condenser

  • Shell Side Tube Side.

All Stainless Steel Piping, Valvea, Fittings All Carbon Steel Piping, Valves, Fittings Quality Group Claeeification Class A Claes A Clase A Clase C

  • Clase B
  • Claes B Clase B Material Stainless Steel Type 304 Stainless Steel A351, Gr. CF8M Stainless Steel Type 304,_ 316 Carbon Steel S.A. 106 Stainless Steel Type 304; 316
  • Type 304.

Al06, Gr. B Impact Teet Required?

No No No

-No-No No No Reason for

  • Exemption(l)

Remarks Be Be Be ea Be 8e ea

1. Refer to Tables A4-4 through Alt-6 of Appendix A in Franklin* Research Center report on Quality group classification of components and ~ysteme for explanation of exemptions.

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Structures, Systems, and Components Standby Liquid Control System Pump Casing Tank Piping and Casing Core Spray System Pump Casing All Carbon Steel Piping, Fittings, Valves All Stainless Steel Piping, Fittings, Valves Quali\\:y Group Classification Clase B Clase B Clase B Claes B Claes B Clase B Table S-1 (Cont.)

Material

.Carbon Steel Stainless Steel Type 304 Stainless Steel Type 304 Carbon Steel A216, Gr. WCB Al06, Gr. B Type 304 2

Impact Test Required?

No No No Yee No No

. Reason for

  • Exemption(!)

8d Be 8d, e ea 8a,e Remarks Thickness up to 13/16 in.

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Table 5-1 (Cont.)

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Structures, Systems Quality Group Impact Teat

  • Reason for and Com~onents.

Clasaif ication Material Reguired7 Exem~tion( 1}

Remarks Spray Spargera and Clase B Stainless Steel No Be Spray Nozzles Type 304 Low Pressure Coolant lnjection7Containment e

I Coolant Subsystem I i Pump Casing Class B Carbon Steel Yea Thickness up

  • I A216, Gr. WCB to 13/16 m I

I I All Stainless Steel Class B Type 304 No Se Piping, Fittings, Valves l

All Carbon Steel Piping Class B

  • Al06, Gr. B No Sa I

Fittings, Valves l

Heat Exchangers -

Class B 70/30 CuNi No Sf l

Tube Side J

Shell Side

  • Class.C Carbon Steel Yea Portions Have I

S.A. 212 - B l" thicknes-I l

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Structures, Syatema, and Components High Pressure Coolant Injection Pump Casing Quality* Group Classification Claaa B Piping, Fittings, and Class S Valves Spargera.(Feedwater Class B Spargera Used)

Standby Coolant Supply System (Condenser*Hotwell to Service Water Line)

Pipings, Fittings, and

.~.

Safety Valves Relief Valves I

Not Safety-Related Claaa B Class A Claaa* A Table 5-1 (Cont.)

Material.

ASTM A 217, Gr. B Carbon Steel Al06, Gr.B Stainless Steel Type.304 Impact Teat

    • Required?

Yee Yea No Carbon Steel No A211, Al06, Gr~ B

  • carbon Steel No Carbon Steel No 4

Reason for

~xemption(l)

Be Sa 8d 8d Remarks Thickness up to l 1/2" Impact Test o~

all Piping wit1'1" Nominal Pipe

  • Diameter Greater Than 6" Deleted

, I Table 5-1 (Cont.)

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St_ructuree-, Systems, Quality.Group Impact Test Reason for I -l and Components Claes if ication Material Required?

Exemption(l)

Remarks CONTAINMENT PENETRATIONS r

Hydraulic Lines to the Class B Stainless Steel No 8d Control Rod Drives I

Valves Claes B No 8d e

-1 CONTAINMENT ISOLATION VALVES Clase A No 8d I

NOT LISTED WITH MAJOR SYSTEM J

CONTROL ROD DRIVE Claes A No 8d I

HOUSING l

CONTROL ROD DRIVE I

.SYSTEM Velocity Limiter Clase B Stainless Steel No 8d Casting Guide Tubes Claes B Stainless Steel No 8e

  • Type 304 I

I SPENT FUEL STORAGE e

I FACILITIES i

Spent Fuel Pool Claes c Stainless Steel No Ba I

. Lining-3/16 inch thick I I I

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  • l I t I I 1

Structures, Systems, and"Components REACTOR VESSEL HEAD

~OOLING SYSTEM Piping, Fittings, and Valves CONDENSATE/FEEDWATER.

SYSTEM Piping from Reactor Vessel to Outermost Containment Isolation Valve

(

Quality Group ClassifiC1ltion Class C Class A Table 5-1 (Cont.)

Material Stainless Steel Carbon Steel Al06, Gr. B Impact Test Required?

No Yes

,.Reason for Exemption(l) 8d,e Remarks

Table 5-1 (Cont.)

Structures. Systems.

Quality Group Impact Teet

  • Reason for and Coml!onents Classification Material Reguired?

Exem(!tion(l~

Remarks I

l.

MAIN STEAM SYSTEM p1-1rtn*g*;- Valve&-.- Fittings Clase A Carbon Steel Yes A155 CONDENSATE STORAGE TANK Class c Aluminum No 8f COMPRESSED AIR SYSTEM Piping, Fittings, and Clase D No -

8d Valves STANDBY DIESEL GENERATOR SYSTEM I*

Service Water Piping, Class C Carbon Steel No ea

'Fittings, *and Valves Al06, Gr. B l

I Fuel oil Piping, Fittings Class C Carbon Steel No 8a I -

_and Valves ASJ, Gr. B e

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