ML18047A537

Forwards Updated Rept Re SEP Topic III-1, Classification of Structures,Components & Sys (Seismic & Quality), Originally Submitted 820812.Submittal Includes Pressurizer Fracture Toughness Data Inadvertently Omitted from 820812 Submittal

ML18047A537
Person / Time
Site:	Palisades
Issue date:	08/19/1982
From:	Vincent R CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.)
To:	Crutchfield D Office of Nuclear Reactor Regulation
References
TASK-03-01, TASK-3-1, TASK-RR NUDOCS 8208250113
Download: ML18047A537 (54)

Text

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consumers Power company General Offices: 1945 West Parnell Road, Jackson, Ml 49201 * (517) 788-0550

, August 19, 1982 Dennis M Crutchfield, Chief Operating Reactor Branch No 5 Nuclear Reactor Regulation US Nuclear Regulatory Commission Washington, DC 20555 DOCKET 50-255 - LICENSE DPR '

• PALISADES PLANT - SEP TOPIC III-1, CLASSIFICATION OF STRUCTURES, COMPONENTS AND SYSTEMS (SEISMIC AND QUALITY)

The intent of this letter is to furnish all the information coil)Illitted to in Consumers Power Company March 31, 1982 submittal ("Palisades Plant SEP Expected Schedule for Completion of Proposed Action Items") regarding SEP Topic III-1.

Consumers Power Company August 12, 1982 letter, which addresses the five items of concern (Fracture Toughness, Radiograph Require-ments, Valves, Pumps and Storage Tanks, and Storage Tanks) inadvertently omitted one page from the enclosure. It was discovered that the page on Evaluation 1, "Pressurizer", of Appendix I, "Fracture Toughness", was missing from our August 12, 1982 letter.

The page which contains the fracture toughness evaluation of the pressurizer as well as the rest of the report sent to the NRC staff are being submitted as enclosures to this correspondence for the purpose of completeness and continuity.

Consumers Power Company appreciates the understanding of the staff and we apologize for any inconveniences that this error might have caused.

Staff Licensing Engineer CC Administrator, Region III, USNRC NRC Resident Inspector - Palisades ATTACHMENT 8208250113 820819 PDR ADOCK 05000255 P

PDR

2

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• PALISADES SEP TOPIC III-1, *QUALITY. GROUP CLASSIFICATION OF COMPONENTS AND SYSTEMS

• August ll, 1982

3 INTRODUCTION SEP Topic III-1, Quality Group Classification of Components and Systems, was developed to ensure systems and components in the Palisades Nuclear Plant were designed, fabricated, installed and tested to quality standards that reflect the importance of their safety functions.

To assess this, the NRC contracted the Franklin Research Center to prepare a report (Reference 1) which addresses safety margins of systems and components in light of the changes that have taken place in the design and licensing criteria.

Upon NRC review of Reference 1, several items were noted which could not be dispositioned due to a lack of information.

These items were then submitted (Reference 2) to Consumers Power for disposition.

This report contains those dispositions.

In some cases, information was not available to disposition each item per the NRC guidelines.

However, in each of these cases an evaluation was completed concluding that the item did not pose a significant hazard to plant safety.

Therefore this SEP Topic is con-sidered adequately addressed and complete.

The disposition and evaluations are contained in each of the following appendices.

Appendices correspond to the six (6) items of concern listed in Reference 2, page 3 and 4.

REFERENCES Appendix I - Fracture Toughness II Full Radiography Requirements III - Valves IV - Pumps V - Tanks VI - Unidentified Codes 1 - Technical Evaluation Report; Quality Group Classifications of Systems and Components for Consumers Power Company Palisades Plant dated December 15, 1981 by Frankling Research Center.

2 - Letter from DMCrutchfield, NRC, to Mr DPHoffman, CPCo, dated December 28, 1981.

FRACTURE TOUGHNESS APPENDIX I CONSUMERS POWER COMPANY PALISADES PLANT SEP III-1, QUALITY GROUP CLASSIFICATIONS OF COMPONENTS AND SYSTEMS

APPENDIX I SYSTEMATIC EVALUATION PROGRAM SAFETY TOPIC III-1 QUALITY GROUP CLASSIFICATIONS OF COMPONENTS AND SYSTEMS ITEM Fracture Toughness Requirements CONCERN Current code requires that the fracture toughness of certain Class 1, 2 and 3 components be evaluated to ensure adequate margin between the lowest service temperature and the nil ductility transition temperature.

For 52 of the 77 components reviewed by t~e Franklin Institute there was insufficient informa-tion to determine if fracture toughness was an issue.

RESPONSE

Table A2-2 of the Franklin Report was reviewed to determine the 52 items of concern.

This list is included in Table I-1.

Design and construction information was gathered on the 52 items and compared to the established criteria exempting components from fracture toughness re-quirements.

These criteria, detailed in Section 4.1.1 of Appendix A of the Franklin Report are listed below:

Class 1

-Materials whose nominal thickness is 5/8 in. or less

-Bolts 1 in. or less

-Pipes, fittings, pumps and valves with nominal pipe size six (6) in. or less

-Austenitic stainless steels

-Non-ferrous materials

-Drop weight tests are not required for martensitic high alloy chromium (series 4xx) and precipitation hardened steels Class 2

-Exemptions *1isted for Class 1 components

-Materials whose lowest service temperature exceeds 150F are exempt from impact testing

-Commonly used plate, forging, and casting materials listed in Table A4-2 of Reference 1 when used in components whose lowest service temperature (LST) exceeds the tabulated nil ductility transition temperature (TNDT) by at least the thickness-dependent value A, determined from Figure A4~l of Reference 1.

Class 3

-Exemption listed for Class 1 components

-Materials listed in Table 4-3 in the thickness shown when the LST for the component is at or above the tabulated temperature.

-Materials for components for which the LST exceeds 100 F are exempt from impact testing.

Table I-1 summarizes the results of the above comparison.

As can be seen, many items were exempted, because of materials (23 items). co~ponevt thickness (15 items), component diameter (2 items) or other reasons (3 items).

This left 9 items remaining to be dispositioned.

1) Pressurizer

2)

Piping RCS Hot and Cold Legs

3)

Safety Injection Tanks

4)

Component Cooling Water Pillnps

5)

Service Water Pumps

6)

Main Steam Piping (counted as two items)

7)

Atmospheric Pump Valves

8)

Feedwater Piping Evaluations were completed on these items as noted in Table I-1.

These evaluations are included in this appendix.

Based on the results of the research and evaluations completed, Consumers Power Company considers the item of fracture toughness requirements adequately disposi-tioned.

2

ITEM DESCRIPTION REACTOR COOLANT SYSTEM

1) Pressurizer

2) Piping RCS hot and cold leg VALVES

3) Pressurizer safety valves

4) Power operated relief

5) Block valves

6) Other valves within quality group 'A' portion of RCPB

7) Other valves within quality group 'B' portions of RCPB

• l) Exempt due to material

2) Exempt due to thickness

3) Exempt due to diameter

4) Exempt due to other reaso s EXEMPTION*

1 2

3 x

x x

x x

TABLE I-1 FRACTURE TOUGHNESS DATA 4

COMMENTS/DISPOSITION Fracture toughness of the materi-al is acceptable per evaluation

.. (

f 't Page 1 o REFERENCES Evaluation !(attached)

X Fracture toughness of the materi-Page 35 of Appendix A of Reference 1 al is acceptable per evaluation ASTM A-376 Type 316 ASTM A-376 Type 316 Class 1, Stainless Steel Type J\\3)1 Grade CF8M Class 1~ Stainless Steel A376

'l',ype 316 Class 1, Stainless Gteel A376 Type 316 Purchase Specification Ml-LB Purcha.se Specification Ml-LB Wa1wort.h BU.1 of Mat.Prial M21~1-42-1 Purchase Specification M241-BC Bechtel Pip1ng Specs-Class CC P&ID's M-201, 202, 203 & 2oh Valve Data Base Bechtel Piping Specs-Class CC P&ID's M-201, 202, 203 & 204 Valve Data Base -

• ITEM DESCRIPI'ION SAFETY INJECTION SYSTEM

8) Safety injection tanks

9) Interconnecting piping and valves required to perform safety injection function

10) Interconnecting piping and valves required to perform recirculation function

11) High pressure safety injec-tion pumps CONTAINMENT SPRAY SYSTEM

12) Iodine removal hydrazine

13) Tank; iodine removal NaOH makeup tank T-102, T-103

14) Interconnecting p1prne and valves required to perform test function EXEMPTION TABLE I-1

• FRACTURE TOUGHNESS DATA COMMENTS/DISPOSITION

• 1-------------1 1

x x

x x

2 x

x 3

4 Fracture toughness of this materi-al is considered acceptable per evaluation A376, Type 316 (CC)

A403, F 316 (CC)

A358, Type 304 ( GC)

A376, Type 301~ (DC)

J\\358, Type 304 J\\403, Type WP304 Stainless steel ASTM 351, Mod CF8 Nominal walls of.375" and.406 11 is less than 5/8" Stainless steel Type 3011 Page 2 o.

REFERENCES Evaluation 2 (attached)

Class CC, GC, DC Piping Bechtel Pipe Spec M-260 P&ID's M-201, 203, & 2ob Valve Dat.a Base Class HC Piping Bechtel Pipe Spec M-260 Valve Data Base P&ID M-20li Pump Material J.i st FSAR p 6-27c Radiography Report from Buffalo Tank M-382, sh 23-1 F'SllR pp 6-?l and 6-2?

ITEM DESCRIPTION EXEMPTION 1

2 3

CHEMICAL AND VOLUME CONTROL 15 ).- Letdown orifices x

16) -Excess letd0wn heat

17) Exchanger-tube and shell side

18) Interconnecting piping and x

valves required to perform

L~tdown*; *charging,. and supply *of safety injection and refueling water tanks function

19) Concentrated boric acid x

tanks

20) Boric acid filter x

21) ConcentratP.d boric acid x

transfer pumps

22) Interconnecting piping and x

valves required for boric acid storage and supply function TABLE I-1 FRACTURE TOUGHNESS DATA COMMENTS/DISPOSITION 11 SA 2t10, Type 304 x

Does not exist x

A376, or ASTM 312 Type 304 Seamless Type 304 and 316 stainless st Pel J\\312 and 376 'I'ype 304 st:linless steel Page 3 o.

REFERENCES Atlas Drawing Dl737 N/A Class HC & EC P&ID M-202 Bechtel Pipe Specs M-260 Purchase.Spec Ml-H Cuna Dwg 51042 Class HC P&ID M-202 Ree ht.el Pj pe Spec M-260

ITEM DESCRIPTION

23) Interconnecting piping and valves required to perform residual heat removal function COMPONENT COOLING WATER SYSTEM.

24) Component cooling water pwnps

25) Heat exchanger tube.side

26) Surge tank T-3 Interconnecting piping (9-22) and valves required to service quality groups B & C system components

29) Interconnecting piping and valves from boric acid batching tank to boric.acid supply

30) Interconnecting piping and valves required to perform demineralizer function 1

x x

x EXEMPTION 2

x x

x x 3

TABLE I-1 FRACTURE TOUGHNESS DATA 4

COMMENTS/DISPOSITION A312 and A376 Type 3oh stainless steel Considered acceptable per evaluation Head thiGkness is 7/16" Wall thickness of l/h" Maximum wall thickness of.375 for pipe diameters 6" A312 and A376 Type 304 stainless steel A312 and A376 Type 301~

stainless steel Page 4 o REFERENCES Class HC P&ID M-202 Bechtel Pipe Spec M-260 Evaluation 3 (attached)

Industrial Process Engineers Dwg 59 35-M-lhl-2 Purchase Spec M-38; 950x23 P&ID M-202 Bechtel.Pipe Spec M-260 Class HC P&IDs M~202 &*M-210 Bechtel Pipe Specs M-260 Class HC P&TD's M-202 & M-210 Recht.el Pipe Spec M-260

ITEM DESCRIPI'ION EXEMPTION 1

2 3

31) Auxiliary Pressurizer x

spray piping and valves I:

32) Shutdown cooling/low pressur'~ x safety injection pumps

33) Shutdown cooling heat x

exchanger shell side SERVICE WATER SYSTEM

34) Service water pumps

35) Interconnecting piping and x

valves required to service quality Group C system components MAIN STEAM SYSTEM 36 & 37)

Interconnecting piping and valves comprising main steam lines extending from the secondary side of the steam generators up to and*

including the outermost containment isolation valve in each main steam line and connected piping up to and TABLE I-1 FRACTURE TOUGHNESS DATA COMMENTS/DISPOSITION 4

ASTM A376, Type 316 eamless all piping 6" diameter ASTM 351 stainless steel, Mod CF8 Nominal wall is 1/2" Considered acceptable per evaluation Wall thickness 5/8" max wall thickness is.375" Fracture toughness of this material is cons:! dered ~ecepta.ble per evaluation Page 5 o. *,

REFERENCES Class CC P&ID M-202 Bechtel Pipe Spec M-260 FSAR p 6-27c Engineers & Fabricators, Inc Dwg CEV-15080 Evaluation 3 (attached)

Bechtel Pipe Spec M-260 Class HB, KB, JB P&ID M-208 Evaluation 4 (attached)

ITEM DESCRIPTION (Contd) including the first valve that is normally closed or capable of automatic closure during all modes of normal reactor operation

38) Atmospheric dump valves

39) Safety valves FEEDWATER SYSTEM

40) Interconnecting piping and valves comprising feedwater lines extending from the secondary side of the steam generators up to and includ-ing the outermost contain-ment isolation valve in each feedwater line and connected piping up to and including the first valve that is nor mally closed or capable of automatic closure during all modes of normal reactor operation

/

EXEMPTION 1

2 3

x TABLE I-1 FRACTURE TOUGHNESS DATA COMMENTS/DISPOSITION 4

Fracture toughness of this materi-al is conside1,ed adequate per evaluation.

Type 316 stainless steel Fracture toughness of this material is considered adequate

\\

I T

I REFERENCES Evaluation 5 (attached)

Dresser Dwg D44952 Evaluation 4

Page 7 o TABLE I-1 FRACTURE TOUGHNESS DATA ITEM DESCRIPTION EXEMPTION COMMENTS/DISPOSITION REFERENCES 1

2 3

4 AUXILIARY FEEDWATER SYSTEM bl) Pumps - motor driven x

Component diameter is 6" or less P&ID M-205

'1

42) Pumps - turbine driven x

I I

43)

Wall thickness of 3/16" C-18-950xl3 sh 41 I

Condensate storage tank x

Purchase Spec I

44) Interconnecting piping and x

Maximum pipe nominal wall of P&ID M-220 valves required to supply

. 375" Bechtel Pipe Spec M-260 auxiliary feedwater from Class.HB, HC

'1 condensate storage tank to steam generators

45) Interconnecting piping and x

Maximum pipe nominal wa.11 of Pipe Class GB valves required to supply

.500 11 P&ID M-205 steam from main steam Bechtel Pipe Spec M-260 system to turbine driven pumps AUXILIARY FEEDWATER

46) Backup supply from fire x

Maximum pipe nominal wal], of Class KB, KC protection system

. 375 11 P&ID M-213 Bechtel Pipe Spec M-260 CONTAINMENT HYDROGEN CONTROL SYSTEM

i. 7) Hydrogen recombiner unit x

0Uf'twork e]iminn.tPfl c'lllP to Wall Pur('hm;1e 8pPP M-296 including ductwork and thickness,all mnterinl lt(l t.0 60 other components required to gaup;t;> nheet metal perform a safety function

ITEM DESCRIPTION EXEMPT.ION 1

2 3

CONTAINMENT PURGE SYSTEM

48) Piping and valves CONTAINMENT COOLING SYSTEM

49) Containment fan coolers x

(fans &: cooling coils)

50) System Ductwork and dampers x

CONTAINMENT ISOLATION SYSTEM

51) Interconnecting piping and x

valves of the reactor cool-ant pressure boundary that penetrate the containment up to and including the outer-most containment isolation

52) Interconnecting piping x

valves of quality Groups B, C, or D system that pene-trate the containment from the first isolation valve inside containment up to and including the outermost containment isolation valve TABLE I-1 FRACTURE TOUGHNESS DATA COMMENTS/DISPOSITION 4

x System has been removed from service Component thickness less than 5/8 11 Component thickness less than 5/8" A376, Type 316 stainless steel A376 and A358, Types 316 and 304 stainless* steel r

i r

Page fl o REFERENCES P&ID's M-217 & M-218 Purchase Specs M-55 & M-59 FSAR p 6-22 Purchase Specs M-55 & M-59 FSAR p 6-22 Class CC P&ID M-203 Class CC, GC Becht.el Pipe Spec M-260 P&ID M-203

EVALUATION 1 PRESSURIZER Tables A4-2 through A4-6 and Figure A4-l of Reference 1 will be used to eval-uate the resistance to brittle fracture of the pressurizer.

The method follows the example calculation for the primary pipe presented in Reference 1.

The Lowest Service Temperature (LST) is 130F.

From Table A4-3 of Appendix A of Reference 1, TNDT= lOF for SA-533 Grade B Class 1.

The permissible LST is

~NDT +A where-A is the required temperature margin over TNDT as determined

r-:tom Figure A4-l of Appendix A of Reference 1.

For material 5 15/32" thick, A = 60F then:

LST -

TNDT )A 130F -

lOF = 120F) 60F So that this material, if it were a Class 2 or 3 component would be exempt from impact testing.

The fact that the pressurizer is Class 1 would not'exempt it from impact testing based on present code requirements.

However, the fact that the LST exceeds the TND by more than 150% of A allows us to conclude that the pressurizer material used in the construction of the Palisades Plant is adequate, provided that exposure to radiation does not induce an increase of the TNDT sufficient to require the fracture mechanics _approach.

In this re-gard, note that paragraph NB-2332(b) indicates that if the LST exceeds the nil ductility transition temperature (TNDT) by lOOF, then the fracture mech-anics approach is not required.

In this case:

LST -

TNDT = 130F - lOF ")lOOF So that the material of the Palisades pressurizer is considered adequate.

EVALUATION 2 SAFETY INJECTION TANKS The actual nil ductility transition tempera~ure (TNDT) data is not available for the Palisades safety injection tanks. Accordingly, an evaluation was made of the fracture toughness as follows:

1)

The material of the tank is 15/16 in. thick A-515 Grade 70. TNDT data for steel of this type show the TNDT is probably in the tange of 80-90F.

2)

The average hoop stress in the tank is at the operating pressure of 200 psi.

one half of the yield stress of 38,000 for brittle fracture is very low.

approximately 12,800 psi This stress is less than psi and thus the potential

3)

The steady-state operating temperature of the safety injection tanks is equal to the temperature in the dome of the containment building.

This temperature is typically above 115F which is25-35F above the expected TNDT of the safety injection tank material.

This margin of 25-30F is consistent with the required margin of 30F specified in Figure A4-l of Reference 1.

Accordingly, the fracture toughness of the Palisades safety injection tanks is considered adequate.

Reference MFR Calculations, "Safety Evaluation of Palisades Safety Injection Tank,"

dated August 9, 1982.

I

EVALUATION 3 COMPONENT COOLING WATER PUMPS (3)

SERVICE WATER PUMPS (3)

Materials used in construction of these pumps are as follows:

Components Cooling Water Pumps - Case Service Water Pumps

- Bowl Discharge Head Discharge Colunm Carbon Steel Cast Iron Carbon Steel Carbon Steel Documentation could not be found identifying specific types of the above materials.

Design and estimated Lowest Service Temperatures (LST) are as follows:

Design LST CCWS Pumps SW Pumps 140F 300F*

• Based on piping design temperatures 90F 32F Without the material specifications and thicknesses of the pump casings, an evaluation following the guidelines of Section 4.1 of the Franklin Report cannot be conducted.

These pumps were also included in the evaluation of Appendix IV of this report.

Although a fracture toughness evaluation could not be completed on these pumps, Consumers Power is not aware *Of any information which indicates*that fracture toughness is a concern for pump pressure boundary parts.

The design margins of safety as described in the FSAR relevant to operation of these systems of this report are as follows:

CCWS PUMPS Any one of three pumps is capable of supplying component cooling requirements during normal plant operation.

During shutdown, one pump can furnish at least 50% of the maximum shutdown cooling water requirements.

For post-DBA operation, one pump can furnish at least 50% of the required capability for cooling the containment spray and safety injection recirulcation water.

For the DBA condi-tion, the containment sprays are backed up by an independent redundant cooling system, (the containment air coolers) which do not rquire component cooling water

• 2 SW PUMPS Each of the three service water pumps is capable of supply 50% service water during normal, shutdown and post-DBA conditions.

EVALUATION 4 FEEDWATER SYSTEM MAINSTEAM SYSTEM These piping systems were fabricated per the following:

All feedwater piping and main steam piping 24" or less in diameter Main steam piping 26" or greater in diameter Al06 Grade B Al55-KC70 Class 2

Normal service temperature for the Feedwater and Main Steam System is 435F and 514F respectively.

Lowest Service temperature for both of these systems is above 350F.

Except during startup when the Feedwater System temperature can be as low as 70F.

Since this time is short and relatively infrequent this case is not considered in this evaluation.

The maximum material thickness is 1.250".

From.Figure A4-1 of Reference 1, A = 30F for piping less than or equal to this thickness.

The T DT of the above material is not readily available_.

However, using the

• form~as given in Section 4.1 of the Franklin Report, the TNDT would have to be greater than 320F before impact testing would be requirea:

LST -

TNDT = 30F 350F -

TNDT = 30F ; TNDT = 320F As TND 's in the magnitude of 320F or greater are highly impropably, Consumers Power.Company concludes that the Feedwater and Main Steam Piping material used in the construction of the Palisades Plant is adequate.

EVALUATION 5 ATMOSPHERE DUMP VALVES (4)

Body material for these valves is chrome-moly (WC-6) Alloy Steel.

The valves

• are Class 2 and have normal service temperature of 532F and an estimated lowest service temperature of at least 350F.

Therefore according to the fracture toughness exemption criteria for Class 2 components given in Section 4.1 of the Franklin Report this material is exempt from impact testing.

Also, if the LST exceeds the reference nil ductility transition temperature (RTNDT) by lOOF then fracture mechanics is not required.

In this case, the LST is 350F 20:

LST -

TNDT = lOOF or 350F -

TNDT = lOOF indicates that the TNDT has to be 250F or greater before fracture mechanics is required.

This magnitude of TNDT for this material is highly unlikely.

Therefore, the material of the atmospheric dump valves is considered adequate.

RADIOGRAPHY REQUIREMENTS APPENDIX II CONSUMERS POWER COivlPANY PALISADES PLANT SEP III-1, QUALITY GROUP CLASSIFICATIONS OF COivlPONENTS AND SYSTEMS

APPENDIX II SYSTEMATIC EVALUATION PROGRAM SAFETY TOPIC III-1 QUALITY GROUP CLASSIFICATIONS OF COMPONENTS AND SYSTEMS ITEM

/

Radiography requirements of:

CONCERN Class 1 and 2 Piping Pressure Vessels

1.

Full Radiography Requirments - The licensee should provide the following:

A.

Category C joints in current Class 2 or 3 vessels built to Class C requirements do not satisfy current radiography requirements.

For the following pressure vessels information is necessary regarding the radiographic requirements imposed on the Category C welds:

(1) regenerative heat exchangers, (2) letdown heat exchangers, (3) purification filter, (4) volume control tank, (5) excess letdown heat exchanger, (6) shutdown cooling heat exchanger, (7) boric acid filter, (8) purification deminerali-zer, (9) deborating demineralizer and(lO) CCWS heat exchanger.

B.

The_ present code requires full radiography for Class 1 and 2 welded joints for piping, valves, and pumps, where as it was not required in past codes.

However, Provisions 2 and 3 of Code Case N-7 required full radiography.

Confirmation that Code Case N-7 was applied to all Class 1 and 2 piping would resolve this concern.

RESPONSE

Vessels As this concern pertained to Category C welds in current Class 1 and 2 vessles, a review vas initiated to determine the classification of the ten (10) identified pressure vessels.

These classifications are determined by the Palisades Plant Technical Staff, based on Reg Guide l.?.h. The results of the review are noted in Table II-1 and eliminated several of the identified vessels (note, one item - the excess letdown heat exchanger - does not exist at Palisades).

1

Consumers Power Company initiated research of the available documentation for construction radiography requirements for the ten identified vessels.

The re-sults of this review are also presented on Table II-1.

As can be seen, docu-mentation of construction radiography requirements was found for all classed vessels with the exception of the shutdown cooling heat exchanger.

Furthermore, a review was made of the Palisades Inservice Inspection 40-Year Master Plan for current inspection requirements on these vessels.

These re-quirements are listed in Table II-2 and are completed once every ten (10) years.

Note the shutdown cooling heat exchanger is adequately covered by the Inservice Inspection Program.

Several inspections of regenerative heat exchanger welds are also required by the Palisades Technical Specifications, Section 4.4, as listed below:

Weld

1.

Primary Side Shell to Tube Sheet Welds

2.

Primary Head Examination Volumetric Volumetric Frequency 100% over a maximum five (5) year interval 100% over a maximum five (5) year interval Based on the above information and Tables II-1 and II-2 the radiography require-ments of the identified ten (10) vessels are considered adequate.

2

TABLE II-1 DOCUMENTATION OF VESSEL CLASSIFICATION AND CONSTRUCTION RADIOGRAPHY VESSEL CLASS

1.

Regen Heat Exchanger 1 & 2

2.

Letdown-Heat Exchanger 3

3.

Purification Filter N

4.

Volume Control Tank N

5.

Excess Letdown Heat Exchanger NA

6.

Shutdown Cooling Heat Exchanger 2 & 3

7.

Boric Acid Filter 2

8.

Purification Demineralizer N

9.

Deborating.Demineralizer N

10.

CCWS Heat Exchanger 3

N - Not classed NA - Does not exist at Palisades 1 - Requirements noted on Bechtel drawings CONSTRUCTION RADIO~RAPHY Radiography: 100% in accordance with Section III, Class Al Radiographs performed on shell seams A.& Band channel weld seams C, D

& E 100% radiography of head and shell No inspection record found Does not exist at Palisades Specific requirements not listed but states that vendor and their customer will review radiographs 100% radiography of head and shell All category A & B joints to be radio-graphed - All catego:ry C & D joints to be penetrant tested 1 Both the shell and tube side -

100%

radiographed DOCUMENT Bechtel Drawing

1. Ml-H-F Sheet 354-3 Bechtel Spec 5935-M-l-H (Sub F)

Bechtel Inspection Reports 4' 5 & 6 Bechtel Spec 5935-M-l-H (Sub D)

Bechtel Inspection Reports 1, 2 & 3 N/A Specification 70P-017 Purchase Spec Bechtel Spec 5935-M~l-H (Sub D)

Bechtel Inspection Reports 1, 2 & 3 No documentation Bechtel Drawing

1. Ml-H-E Sheet 2-1 Bechtel Spec 5935-M-14-AC Bechtel Inspection Reports 5 & 6

TABLE II-2 INSERVICE INSPECTION REQUIREMENTS (ASME SECTION XI)*

VESSEL CLASS

• 1.

Regen Heat Exchanger 1 & 2

2.

Letdown Heat Exchanger 3

6*.

Shutdown Cooling Heat Exchanger 2 & 3 (Note:

The volumetric examina-tions listed are scheduled to be performed during the 1983 refueling outage)

7.

Boric Acid Filter

10.

CCWS Heat Exchanger 2

3 INSPECTIONS Class 1:

5 volumetric examinations 2 - circumferential welds 2 - nozzle to shell welds 1 - nozzle inner radius VT-2 examination1 Class 2:

Exempt per IWC-1220(c)

Code 77S78 (size"' 4")

VT 2.

t*

1 exarnina ion 1

3 VT 2 t*

1 C ass exarnina ion Class 2:

4 volumetric examinations Class 3:

2 - circumferential welds 2 - nozzle to shell welds VT-2 VT-2 exarnination1 t". 1 examJ_na. ion Exempt per IWC-1220(c)

Code 77S78 (size~ 4")

VT-2 VT-2 exarnination1 t"

1 exrunina ion

• These inspection requirements were based on the Palisades 40-Year ISI Master Plan, Rev 0, which is based on the 1977 Edition Summer 1978 Addenda of ASME Section XI.

1vT-2 is a hydrostatic test

Piping A review of the Bechtel Piping Specifications M-249 and M-260 was conducted to determine the a.mount of preservice radiography performed on Class 1 and 2 piping systems.

The results of this review are listed in Table.II-3.

It has been determined that Code Case N-7 was implemented for Class 1 and 2 Austentic Stainless Steel Piping with the following notes taken from M-249:

Note 1:

Where size or configuration of weld does not permit effective radiography, liquid penetrant or magnetic particle inspection is required..... Note "B" on sheet 3.

Note 2:

Class CC Systems (Primary Coolant System) -

from primary loop out through second valve - dye check 100% of all welds.

Note 3:

Class CC Systems - beyond second valve -

dye check at least 10% of all welds in each system.

4*.*

Note All other systems requiring both 100% radiography and Code Case N-7

- dye check at least 10% of all welds in each system Table II-3 provides documentation of the construction.radiography required on the Class 1 and 2 piping systems at Palisades.

The information in this table was taken from the Bechtel Piping Specification M-249 (Drawings 5935-M-249, sheets 1-5).

Additionally the inspection program implemented at Palisades was reviewed.

This program meets the requirements set forth in Section XI of the ASME Code.

Table II-4 summarizes the results of this review.

The table is set up to show the number of volumetric and surface examinations scheduled to be performed over a 40-year period.

Palisades is presently at the end of the first 10 year interval of the 40-year master plan.

By the end of 1983, approximately 25% of planned inspections will be complete.

Based on the results of the research conducted and documented in Tables II-3 and II-4, the item of radiography requirements for Class 1 and 2 piping is considered adequately dispositioned.

• In addition to Code Case N-7 3

TABLE II-3 SYSTEM CLASS 1 SYSTEM Primary Coolant System CLASS 2 SYSTEM Feedwater Feedwater Recirc to Main Condenser High Pressure Safety Injection to Primary Loop Safety Injection Recirc to SIRW Tank Feedwater to Steam Generator Feedwater to Steam Generator Downstream of FW Regulator Low Pressure Safety Injection Pump Discharge High Pressure Safety Injection Pump Suction Shutdown Heat Exchanger Discharge Safety Injection Recirc to SIRW Tank Engineering Safeguards Pump Suction Boric Acid Pump Suction Boric Acid Pump Discharge Containment Sump Drain Volume Control Charging Pumps SIRW Tank to Charging Pump SIRW Tank Miscellaneous Piping Containment Purge

• Notes 2, 3 and 4 apply RADIOGRAPHY 100%

100%

100%

100%

100%

100%

100%

100%

100%

100%

100%

100%

10%

100%

100%

100%

100%

100%

100%

CODE CASE N-7 Yes No No Yes Yes No No Yes Yes Yes Yes Yes No*

No Ye.s Yes No No No

Notes:

TABLE II-4 INSERVICE INSPECTION PROGF~..M CLASS 1 COMPONENTS TOTAL SYSTEM WELDS VOLUMETRIC SURFACE Reactor 272*

39 28 Pressurizer 36 36 0

Steam Generator A 24

• 24 0

Steam Generator B 24 24 0

Regen Heat Exchanger 7

7 0

PCS 392 274 111 ESS 225 124 93 eve 192 1

190

• 185 inaccessible CRDM welds CLASS 2 COMPONENTS Steam Generator 'A' 12 9

0 Steam Generator 'B' 12 9

0 Shutdown Cooling Heat Exchanger 'A' 4

4 0

Shutdown Cooling Heat Exchanger 'B' 4

4 0

MSS 164 24 24 Feedwater 87 36 8

ESS 1021 29 182 Radwaste 6

1 0

Spent Fuel Pool 66 0

0 Service Water 5

0 3

Vent and Air System 28 0

10 Component*

11 0

0 1

Welds that require both volumetric and surface examination have been counted only once under the volumetric category.

2 These numbers represent close approximations.

3 Total welds = total welds in the system.

4 Volumetric = exams performed using PT.

5 Surface = exams performed using PT.

6 Several welds in each system have been excluded or exempted from inspection due to inaccessibility, size, multiple loops, etc.

VALVES APPENDIX III CONS'LWERS POWER COMPANY PALISADES PLANT SEP III-1, QUALITY GROUP CLASSIFICATIONS OF COMPONENTS AND SYSTEMS

APPENDIX III SYSTEMATIC EVALUATION PROGRAM SAFETY TOPIC III-1 QUALITY GROUP CLASSIFICATIONS OF COMPONENTS AND SYSTEMS ITEM Valves CONCERN Provide, on a sample basis for Class 1, 2 and 3 valves, information regarding the design of the valve in order to evaluate if they meet current body shape and pressure-temperature rating requirements.

RESPONSE

Of the 8599 valves in the plant, 275 (53 Class 1, 184 Class 2, 36 Class 3, 2 Un-classed) are listed in Procedure No. EM-09-02, "Inservi*ce Testing of Plant Val;es,"

of the Plant Engineering Manual.

These valves were selcted in accordance with NRC letter dated January 13, 1978 and follow-on discussion with the NRC.

This list includes:

1)

Those valves required to function to safely shut down the plant in the event of an accident.

2)

Those valves required to function to mitigate the conse-quences of an accident.

3)

Those valves required to function to prevent the uninten-tional release of radioactive fluids or gases to the out-side environment.

4)

Those affording a safety-related overpressure protection function.

5)

Those for which the nature of their service or their location dictates that administrative controls be exer-cised to ensure the valves are not inadvertently left out of their safety positions during plant operation.

All remaining valves are considered installed for operating convenience or main-tenance, and are therefore not included in the Inservice Inspection (ISI) program.

Consumers Poyer Company intends to performs the following evaluation on a sample basis as requested by the NRC:

Class 1 Valves -

Compare actual body shape with body shape rules of Section NB-3544, ASME Code Section III Division 1, 1977 through 1978 Summe~ Addenda.

If the' shapes are not significantly different, they are con-sidered adequate.

1

Class 2 and 3 Valves - Identify pressure-temperature rating requirements of Class 2 and 3 valves and compare them to the pressure-temperature ratings of ANSI Bl6.34-1977, "Steel Valves".

To develop the sample for evaluation, the valves were grouped according to valve type, class (either l or 2/3), and manufacturer (see Table III-l). Data sheets and drawings of the valves were obtained and reviewed with the following results:

Class 1 Valves - There is insufficient information to perform the body shape evaluation for Class 1 valves.

Nevertheless Consumers Power Company considers that the Class 1 valves should be adequate for the following reasons:

1) The plant has been in service since 1972 and in this 10-year period, corrective actions have been taken to resolve valve problems which have occurred.

2) The valves are included in the ISI program which requires periodic operability test-ing and examination of the pressure bound-ary integrity.

Class 2 and 3 Valves - The results of the evaluation of these valves are summarized in Table III-2.

There is sufficient information to evalute the pressure-temp-erature rating£ of 21 of the 24 groups representing 168 of the 220 total Class 2/3 valves.

Of the 168 valves, 2 do not meet the current pressure-temperature requirements.

These are CV-1910 and CV-1911, the reactor system sampling line containment isolation valves.

These are 1/2 inch 1500# valves made of 316 S.S.

The system design pressure is 2485 psi.

Based on the current pressure-temperature rating, the design pressure of the valve is 2220 psi.

Although this valve design pressure is less than the system design pressure by about 10%, the valve design pressure is siig tly less than the normal operating pressure of 2250 psi.

The valves are considered adequate because they are very small and because the current pressure-temperature rating is greater than the normal operating pressure.

1 2

3 Masoneilan Dre:iser Target Rock Industrial Corporation Class.2/3 Class 1 Class 1 CV-0155 PRV-1042B PRV-1067 CV-2009 PRV-1043B PRV-1068 CV-0522A PRV-1069 CV-0522B PRV-1070 CV-1002 PRV-1071 CV-1007 PRV-1072 CV-1001 CV-1004 CV-1064 CV-1065 CV-1037 CV-1036 CV-1038 CV-1044 CV-1045 CV-1101 CV-1102 CV-1103*

CV-1104 CV-1211 CV-1503 CV-1501 CV-1502 CV-0939 CV-1358 CV-3069

• VnlvP ~r.]P.ctea for ev;1J11ntion 4

BlRck,Sivalls and Bryson Class 2/3 CV-2130 CV-2136 CV-2155 CV-3006 CV-0736A CV-073711 CV-0825 CV-0878 CV-0913*

CV-0950 5

Velan Valve Class l M0-3rJ07 M0-3068 M0-3008 M0-3009 M0-3066 M0-3010 M0-3011.

M0-3064 M0-3012 M0-3013 M0-30111 M0-3062

.I-1 Vl\\LVE C:ROUPTNC:::J (Globe) 6 7

Vclan l!:.rnunel Valve Dahl Class 2 CJm;s

? i(,*rcvc CV-30112 3227ES CV-30h6 3217ES CV-301'7 Mo-1o*r;o*

CV-30311 8

llnmmPl Dnhl Cl mm 2 CV- ~n;->5 CV-20133 CV-3001*

CV-3002 9

10 11 12 Wnl.wort.h Nu pro Cons. Safety lllloy StePl Co.

V11lve lli v.

Products Class 2 Class 2 Cl A.SS 1 Class 2 CV-3036*

CV-1910*

RV-lOhO CV-3071*

CV-1911 RV-1041 RV-1039

13 Velan Valve Class 1 M0-3015 M0-3016

• Vrtlv" :;p]ectP.F'P 0120Sfo'P 311J<:m:J 3l'l'H::J 319m:0 M0-301'1 M0-3045 M0-30li9 M0-30)2 (Gate)

J7 lR WnJworth 1\\1 loy Gtr'Pl Co.

l'rorl11r.ts Class 2/3 Clnsn 2 CV-3059 CV-3057 CV-3030*

CV-3031*

CV-3027 CV-3212 CV-3056 CV-3223 CV-3037 cv-:::22!1 317RES CV-3213 31721\\!J CV-3070 CV-3018 lOlSW CV-0521 19 20

/\\n**ltor I\\ 11 in Vnlvr>

ChnlmPrs Clnsn 2 Clans 3 01J8GF'P*

CV-OR73*

0117GF'P

21 22 23 Alloyco Inc. Alloyco Inc.

Chapman Valve & Mfr;.

Class 1 Class 2 Class 2 3101ES V0155B 2171CVC 3102ES 2138CVC 2141cvc 3ll6ES 2139CVC 3181ES 3ll7ES 3226ES 3166ES 3131ES 3216ES 3183ES*

3132ES 3186ES 3168ES 3146ES 3177ES 3147ES 3171ES 3201ES 3192ES 3208ES 3220ES 3230ES 3-N238-M2R*

3-N238-M2R

• Vn.J V<' ::;<'lected for ev<i.luat.ion

-1 VAINE GROUPINGS (Check) 2161CVC*

25 Velrm VA.lve Cl ass 1 3104ES 3119ES 313liES 3lli9ES 3250ES 32'.)lES 3252ES 3253ES

?6 Westinp,-

hous" Class 1 3103ES 3118ES 3131ES 31l18ES 27 28 Walworth At woo cl Co.

& Morrill Class 2 Clas fl 2 32liOF.S*

CV-0501*

3239ES CV-0510

• V:ilvf' r.f'lPctcrl for ev:i.lu:1tion V/\\LVF. GROUPINGS (No7.zle l

?9 Croshy Valve and Gar;e RV-0701*

t.hrOUf;h RV-0721i

VALVE GROUPINGfl (Butterfly) 30 31 32

n Bettis Fisher Pr11tt All is Corporation Controls 11Pnry Ch al mt? rs Class 3 Class 2/3 Class 2/3 Class 2/3 CV-0867*

CV-0884 MO-Pl CV-0910 CV-0885 M0-1'2 CV-0911 CV-1803 MO-P3 CV-091iO CV-1805 OJ03CC CV-09JiJ~

CV-1806 0101~cc CV-011?3 cv-rno*r 0102CC CV-0826 CV-11108 CV-0861i CV-1813 CV-08i11 CV-1814 CV-Oll?li CV-O'.)lili/\\*

CV-08117 CV-0997B CV-0937 CV-0938 CV-0945 CV-0946 CV-1359*

• Valve selected for evaluation

• Val vr> r:el ccted for evnl1mtion TA VAINE GROUPINGS (Angle)

Masoneilan Class 2 CV-0767*

CV-0768 CV-0770 CV-0771 CV-0738 CV-0739

I-1 VflLVE GROUPINGS The va.lVPfl below werp unable to he groupf"d due to insufficient infonnntion MV-0916 OlOlCC 0914cc 0131SWS 013?.SWS 3236ES 0137SWS 0138f1WS 60hVfl

. 603VA 601VA 605VA L-6VA RUD-0162 1-223 1 1/2-??.3 4-257 2-263-hOl 2-2f'13-hOO 1 1/2-N276Y CA-122 141VAS Jh2VAS 31fl7ES 3353ES 335?ES 0775F'W 077l1r*'W l1-N:"'M:1 11n 11-N;'*>l.1:'11}\\

O*)JnCC

TABLE III-2 Results of Pressure-Temperature Rating Evaluation of Class 2/3 Valves Category(l)ASTM Material Material Max.Temp.

Max.Pressure Rating Allowable Specification Group No F

psig(2)

Pressure psig(3) 1 A-351CF-8M 2.2 283 55 150#

219 4

A-215-WCB 1.1 140 140 150#

275 6

A-182-F316 2.2 150 2735 1500#

3347 8

A-351-CF-8M 2.2 350 500 300#

537 9

A-351-CF-8M 2.2 350 2405(4) 1500#

2682 10 Type 316 2.2 650 2485 1500#

2220 Stn. St.

12 A-351-CF-8M 2.2 350 500 300#

537 14 A-182-F316 2.2 250 150 150#

227 15 A-351-CF-8M 2.2 350 500 300#

537 17 A-351-CF-8 2.1 300 60 150#

205 18 A-351-CF-8 2.1 300 60 150#

205 19 A-351-CF-8 2.1 300 125 150#

205 A-216-WCB 1.1 120 110 150#

280 18-85 Insufficient data 23 A-351-CF-8M 2.2 350 450 300#

537 24 A-351-CF-8M 2.2 Insufficient data 27 A-351-CF-8 2.1 300 16 150#

205 28 A-216-WCB 1.1 514 1100 600#

1185 29 A-216-WCB 1.1 550 985 1500#

2865 30 A-216-WCB 1.1 283 55 150#

235 31 A-515-70 1.1 140 150(4) 150#

275 32 Insufficient data 33 A-216-WCB 1.1 75 110 150#

285 34 A-217-65 1.13 550 1000 600#

1270 Notes

. (1) Only categories from Tab.le III-l for Class 2/3 valves are included in the evaluation.

(2) Maximum design pressure obtained from valve data sheets.

( 3) Curre~t allowable pressure rating based on ANSI Bl6.34-1977.

(4) Maximum design pressure obtained from piping specification rather than from valve data sheets.

PUMPS APPENDIX IV CONSUMERS POWER COMPANY PALISADES PLANT SEP III-1, QUALITY GROUP CLASSIFICATIONS OF COMPONENTS AND SYSTEMS

APPENDIX IV SYSTEMATIC EVALUATION PROGRAM SAFETY TOPIC III-1 QUALITY GROUP CLASSIFICATIONS OF COMPONENTS AND SYSTEMS ITEM Pumps CONCERN Eight (8) of the twelve (12) pumps reviewed were designed to standards other than ASME B&PV Code Sections III or VIII, 1965.

These codes were not available and the compariso~s could not be made.

Provide the codes or requirements to which the 8 pumps were designed.

RESPONSE

Through the Systematic Evaluation Program (Topic III-1), the question of what design codes were used in the design of 8 of 12 pumps reviewed arose.

This question is addressed in Table IV-1.

As can be seen from this table, 3 of these pumps were designed to ASME Boiler & Pressure Vessel Code, Sections III and/or VIII, while a fourth is in fact not a pump.

Therefore, these 4 items give no cause for concern.

The codes to which the remaining 4 pumps were designed to are also supplied in Table IV-1.

These pumps are included in our Inservice Inspection Program and have been in service since 1972.

The ty:pes of tests run on these pumps are listed in Table IV-1.

These tests are performed monthly when the plant is in operation.

Table IV-2 supplies the design temperature, design pressure, and material used for each pump.

The information available to Consumers Power Company is insufficient to perform analyses in accordance with ASME Section III.

However, due to the fact that these pumps are tested regularly per the ISI Pillnp and Valve Program and the fact that they have been inservice since 1972, Consumers Power Company feels that the safe operation of the Palisades Nuclear Plant related to these 4 pumps is ensured.

1

-~-------

PUMP Containment Spray Shutdown Cooling/Low Pressure Safety Injection Concentrated H3 Bo3 Transfer Component Cooling Water Service Water SWS Strainers AFWS-Turbine Driven AFWS-Motor Driven CODES.

SHI, ASA B31. 1 ASA Bl6.5 ASME VIII, ASA Bl6.5 SHI, ASA Bl6.5 SHI, ASA, ASTM SHI, ASA, ASTM ASME B&PV Code, Sections III &

VIII ASME B&PV Code TABLE IV-1 PUMP DESIGN CODES DATE 6/21/67 1965, 1961 5/15/69 12/27/68 8/25/67 9/18/69 MATERIAL 316 SS Stainless Steel Case-Carbon Steel Bowl-Cast Iron Discharge Hea.d-Carbon Steel Discharge Column-Carbon Steel COMMENT Information from Bechtel Spec M-8; FSAR Vol 2 No further evaluation required Information from Combustion Engineering Spec M-lHC; Palisades ISI Plan Vol 2 Information from Bechtel Spec M-34; FSAR Vol 2 Information from Bechtel Spec M-11; FSAR Vol 2 Not a pump - no further evaluation necessary.

Information from Bingham Pump Design Cale., no need for further evaluation Sarne pump as preceeding except for driver, no need for further evaluation

TABLE IV-2 PUMP INSERVICE TESTING PROGRAM

• Test Differential Bearing Visible Pump.

Procedure Vibration

• Pressure Temp Flow Oil Level Service Water M0-16 x

x Component Cooling H20 M0-18 x

x x

x Containment Spray M0-19 x

x x

x Concentrated H3Bo3 M0-21 x

x x

x From Palisades Technical Specifications, Surveillance Program Monthly Section

TABLE IV-3 DESIGN TEMPERATURE AND PRESSURE AND MATERIAL OF PUMPS DESIGN PUMP PRESSURE Containment 500 psig a Spray (discharge)

Concentrated 150 psig c H3Bo3 Component Cooling 125 psig a Water Service Water 125 psig a aPiping Vessel Specifications

.FSAR Vol 2, p. 6-20.

cFSAR Vol 2, p. 9-73

~SAR Vol 2, p. 9-74 eFSAR Vol 2, p. 9-20 f

9-6 FSAR Vol 2, p.

DESIGN TEMP 300 Fa 250 Fe 140 Fa 32-75 Fa MATERIAL 316 ssb stainless steeld case-carbon steele

• r bowl-cast iron discharge head-carbon steel discharge column-carbon steel

TANKS APPENDIX V CONSUMERS POWER COMPANY PALISADES PLANT SEP III-1, QUALITY GROUP CLASSIFICATIONS OF COMPONENTS AND SYSTEMS

APPENDIX V SYSTEMATIC EVALUATION PROGRAM SAFETY TOPIC III-1 QUALITY GROUP CLASSIFICATIONS OF COMPONENTS AND_ SYSTEMS ITEM Storage Tanks CONCERN This Appendix is to present the results of an evaluation of the Palisades atmos-pheric and low pressure (0-15 psig) storage tanks in accordance with the require-ments presented in Reference 2.

Specifically, the NRC requested the following:

RESPONSE

a)

Confirm that the atmospheric storage tanks meet current compressive stress requirements

• b)

Confirm that the 0-15 psig storage tanks meet current tensile allowables for biaxial stress field conditions.

c)

Six of the nine tanks were designed to standards other than ASME B&PV Code Sections III or VIII.

These codes are not available and the comparisons could not be made.

Provide the codes or requirements to which the six tanks were designed.

The nine storage tanks to be evaluated are identified in the Franklin Technical Evaluation Report C-5257-428.

The six tanks which, according to Reference 2 were designed for codes other than the ASME Code are:

Refueling Water Storage Tank (SIRW)

Hydrogen Recombiner Iodine Removal Hydrazine Tank

. Iodine Removal NaOH Makeup Tank Boric Acid Blender Condensate Storage Tank The three tanks which, according to Reference 2, were designed to an ASME Code are:

Safety Injection Tanks Concentrated Boric Acid Tanks Components Cooling Water Surge Tank

The evaluation of these storage tanks was performed in two phases as follows:

Phase 1 consisted of a review of the design information available at Consumers Power Company to determine whether sufficient infor-mation was available to resolve the NRC concerns.

Phase 2 consisted of additional analyses and evaluations for those items for which the existing information was not sufficient to resolve the NRC concerns.

As shown in Tables V-1 and V-2, the NRC concerns could be resolved for seven of the nine storage tanks based on the information available at Consumers Power Company.

Specifically, Two of the items are not storage tanks.

Four of the items are pressure vessels with a design pressure greater than 15 psig and are not atmospheric or low pressure (0-15 psig) storage tanks.

One item is a small diameter indoor atmospheric tank designed to ASME Code Section III, Class C requirements.

The compres-sive stresses in the tank are negligible.

The refueling water storage tank and the condensate storage tank were identified as requiring further evaluation in Phase 2.

a)

Refueling Water Storage Tank (Class 2)

The refueling water storage tank is called the Safety Injection and Refueling Water (SIRW) Tank at Palisades.

The tank is lo-cated outdoors. It was evaluated in accordance with ASME Code Section III, NC-3100 for Class 2 vessels.

In addition, com-pressive stresses were evaluated in accordance with NC-3852.6(b).

The results of the calculations are summarized in Table V-3.

They are as follows:

(1)

The tank was designed to A5A B96.l (1967).

(2)

The material is 5454 aluminum.

This is an acceptable material for ASA B96.l and for ASME Code Section III, Class 3.

It is not an acceptable material for ASME Code Section III, Class 2.

This difference is not consid-ered significant because aluminum is a suit-able material for an outdoor storage tank for borated water.

(3)

The wall thickness of the lower shell is 0.406 inches.

This is nearly 20% greater than the wall thickness (0.333 inches) required by ASA B96.1 but approximately 2

/l l0% less than the wall thickness (0.450 inches) required by ASME Code Section III, Class 3.

Class 3 requirements were used for comparison because 5454 aluminum is acceptable for this class and because spot radiography is permitted.

A joint efficiency of 0.85 is used when spot radiography, rather than full radiography, is specified.

Note that for Class 2, which assumes a joint efficiency of 1.0, the required wall thickness (0.382 inches) is less than the tank wall thickness.

Accordingly, the wall thickness is considered satisfactory because it is conser-vatively sized based on the original code re-quirements and because the wall thickness is only 10% less than required by the ASME Code.

(4) The tank was spot radiographed.

As noted above, this is permitted for Class 3 tanks but not for Class 2 tanks.

This level of nondestructive exam-ination is considered satisfactory because the tank has oeprated satisfactorialy for more than ten years and because the tank is included in the Palisades inservice inspection (ISI) program which requires periodic visual inspection of the tank.

b)

Condensate Storage Tank (Class 3)

As shown in Table V-3, the calculations* for the condensate storage tank show it meets current requirements.

• MPR Calculations, "Stress Analysis - Palisades Condensate Storage Tank,"

dated August 9, 1982 3

TANKS RF.PORTED BY NRC AS BEING ATMOSPHERIC OR LOW PRF.Sm.'RF. ( 0-15 PSIG)

AND AS HAVING BEEN DEi.Ir.NED TO CODES OTHF!l THAN ASMF.(l)

TANK

1.

Refueling Water Storage Tank (called Safety Injection and Refueling Water (SIRW) Tank at Palisades)

2.

Hydrogen Recombiner

3.

Iodine Removal Hydrazine Tank

4.

Iodine Removal NaOH Makeup Tank

5.

Boric Acid Blender

6.

Condensate Storage Tank NRC QUALITY CLA:::SH'TCA'J'ION 2

2 3

3 3

3 NOTES: (1) Enclosure 1 to NRC lettPr to CPCo (Dnvirl I' lloffmnn) <lat;ecl Decemher 211, 1981. (Refr>rrmce ;:>)

DEGTGN CODE Bechtel Gpec C-18 Bechtel Spec M-296 Bechtel Spec M-382 Bechtel Spec M-382 CE Spec M-11!

Bechtel Spec M-)2 Bechtel Spec C-Hl

(/\\PI 650)

(2)

(3)

Tank rlesir~n pri?nsure in 16 psie per R<>chtel Spec M.'.. lfl?. Tnnk is also exempterl because rleni l',n presr:ure eXCPPrb J ') P".i r;.

This mieht be a 1*efercnce to the boric ncid hntr!1i.nr; t.nnk.

If so this i:1 a r:mnl.l t.nnk, opf'n to the atmor:pt11"?rr~ and located indoorr.. 'l'hercfore thin tank cloer: not n"rr:I 0v:1.l 1rn-tion either.

COMMENTS Atmospheric tank -

Sr*opinr; analysis formed in accorclnnce with ASME III (1977 and 19'rll Summer Addendum), Class 2.

Is a cabinet not a tank; should be delPterl.

Bechtel specifica-tion ri?quired design to he in accordance with AGME III (2 )

( 1965) Class C.

• Bechtel specifica-tion required deidr;n to he in accordance with Ai.ME III (2 )

(J.9G5) Class C.

Ts n pipe tee not a t:i.nk; r~uld he deleter:!. 3 Atmospheric tnnk -

Scopjn~ analyGin performe<l in ac-cordance with /\\GME lif (1977 nnd 1~7R S11mmr>r /\\r.ldendllm),

Cl:i::c; 3.

EVAWATION Tank does not meet all require-ments of current cocle but is con-s ir!Pred satisfac-tory -

See Table 5-3.

None required.

None required.

None required.

None required.

Tank desip,n meets c11rrf>nt re-

<JUi remcnts -

See '!'able 5-3.

TANK

1.

Safety Injection Tanks

2.

Concentrated Boric Acid Tanks

3.

Component Cooling Water Surge Tank TA TANKS REPORTED BY NRC AS BEING ATMOSPHERIC OR LOW PRESSURE (0-1'.i rsrr,)

AND AS HAVING BEEN DESIGNED TO ASME CODEG(l)

NRC QUALITY CLASGIFICATION 2

2 3

nmnr.N CODE

/\\f~Ml*~ TT l

( J<JG5 )

Class C ASME III ( 1965)

Class C ASMF. III ( 1965)

Class C COMMENTS Is a pressure vessel (dcsir:n pressure =

250 p,,;i) not n.low pressure tank; should be dcJPted.

Tr; a small dirunetf'r (13 ft.) indoor atmos pheric tank.

Ts a pressure vessel

( rles i p,n pressure =

2'.J psi) not a ]ow presc.ure tank; should br rlrleted.

Notes:

(1) Enclosure 1 to NRC ktter to CPCo (David !' Hoffm:m) rlntcd Dec<>.mber 28, 1981. (R<>f0r"""" 3l.~

EVALUATION None required.

Compressive stresses should be nep,l i r,i ble -

no further analy-sis required.

None required.

Safety Injection and Refueling Water (SIRW)

Storage Tank (T-58)

Condensate Storage Tank (T-2) 1'11 EVALUATION OF SAFETY INJECTION AND RF.FllELING WATER (SIRW) /\\ND CONDENSJ\\'l'F. S'l'ORl\\GE TANKS ATTRIBUTE Design Code Material Wall thickness (lower shell)

Compressive Stress (upper shell)

Non-Destructive Examination Design Code Material Wall thickness (Lower Shell)

Compressive Stres::; (Upper

~hell)

Non-Di:>structive Examination AS-RUHT ASA R96.1(1967) 545!1 Aluminum o.406 in.

ll9 psi Spot radiop,raphy API 650 ASTM A-36 (Carbon Steel) 3/16" (0.188 in.)

Not determjned f)pot rn.rJ i or:r:i phy ORIGLNl\\L REqUIREMP;NTS

/\\Gii W16.1 ( J.')67) 0.333 in.

Not determined Spot radiop,rnphy

/\\PI 650 llSTM A-36 0.106 in.

Not rlet.ermined CURRRNT DEGfGN RF.QlJT!U:l-lfo:NTS llGME III Class 2 Aluminum is not a Code Mn.terial o.450 in. (l) 588 pni allowable Full radiop,raphy l\\SME II T Class e Equivalent to Corle Mnterinl SA-36 0.1119 in. ' 2 )

Not determined f.po t. rnrl i or:rn.ph,v MF.E1'S CURRENT RF.QlT JH l':MENTS?

N/11 No No Yes No N/A Yes Yes EV/\\LUl\\TION Tank is considered satisfactory because:

a.

Aluminum is suitable for outdoor storaee tank con-taining borated water.

b.

Wall thickness is con-servatively sized based on original code requirements and is only 10% less than required by ASME code.

c.

Tank is included in Pnlisades !SI prop,ram which requires periodic visual inspection.

Tank is satisfactory - meets current requirements.

NOTF.S: (J) Wall thickncsr. calr.uln.t.i.on bn::;cr! on /\\f,MP. lTJ, Cln.r:s 1 r0q11i rcmPnt.s wU.h n.,Joint efriC'i<'ney of o.nr,. Cnlr11l,.t.rd wnll t.hir.kner.s requi.rccJ per

/\\~'.Ml*: fJT CJa:;r.? i:; 0.)1'.? in. Rcqu.i.rf'd t.hirknc:;:; is.lr:::: h"ra11:;r-f11JI rnrl.i.or:raphy ir. "lr:~:imir'<l.

( '* \\

'111. ~

1

", 1 * * '

I 1

I I

~

I

UNIDENTIFIED CODES APPENDIX VI CONSUMERS POWER COMPANY PALISADES PLANT SEP III-1, QUALITY GROUP CLASSIFICATIONS OF COMPONENTS AND SYSTEMS

./'.

• )

APPENDIX VI SYSTEMATIC EVALUATION PROGRAM SAFETY TOPIC III-1 QUALITY GROUP CLASSIFICATIONS OF COMPONENTS AND SYSTEMS ITEM Unidentified Codes for Certain Components CONCERN Six (6) components lacked information on the design codes as identified in Table 4.2 of the Franklin Report.

These components are as follows:

1) Reactor Coolant System Block Valves

2)

Containment Spray Nozzles

3)

Shutdown Cooling/Low Pressure Safety Injection Pumps

4)

Excess Letdown Heat Exchanger

5)

Deborating Demineralizer

6) Purification Demineralizer

RESPONSE

Table 4. 2 of the Franklin Report lists design codes for Class l, 2 and 3 components.

A review of the above components classification according to the Palisades Q.-list was completed.

The results noted that:

a)

Excess Letdown Heat Exchanger does not exist at Palisades b)

The Deborating Demineralizer and the Purification Deminer-alizer are not classed therefore are eliminated from this item.

For the remaining items a document search was conducted to identify the design codes with the following res.ults:

a)

The RCS Block Valves were bought with Purchase Order 5935-M-241-BC, Section 2.0 of this order states:

All valves shall conform to the applicable standards of ASA Code for Pressure Piping B 31.1 and ASA Code for Steel Pipe Flanges and Fianged Fittings B 16.5.

Valves in Nuclear Service shall meet the requirements of Nuclear Code Case N-2 and N-10, except for Paragraph 8 of N-10.

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n JI b)

An extensive records search was conducted for the design code(s) used for the containment spray nozzles.

This search included:

i Purchase Specifications 5935 G-1 ii Drawing Files iii Correspondence Files (M-134) iv FSAR v Drawing 5935-M-134-AC-2-1 vi Drawing 5935-M-134-AC-1-1 No design codes were identified for the spray nozzles.

The piping was designed to B31.1.

Due to the function, operational experience and testing of these nozzles, this item is not considered a safety hazard and no further evaluations or research is required.

c) The Franklin Report has separate listings for the shutdown cooling/low :pressure safety injection pump and the low pressure safety injection pumps.

The Franklin Report states that the Palisades low pressure safety injection pumps meet current requirements, but no further information was avail-able on the other pump.

The reason for this is that Palisades does not have a separate shutdown cooling pump.

An extensive records search was conducted for design code(s) for the shutdown cooling/low pressure safety in-jection pumps.

This review included:

i Combustion Engineering Spec 70P-Ol4 ii Drawing Files Ml-G-B iii Correspondence Files (Ml-G-B, M-1) iv Pump Data Base v

FSAR vi Bechtel Spec Ml-G-B vii Combustion Engin~ering Correspondence Files Althqugh the design criteria of these pumps were never found to be specifically addressed, ASME Section VIII was referenced in the Purchase Specification Ml-GB.

Therefore, Consumers Power Company suspects that Section VIII of the ASME Code was used as a basis for design of these pumps.

This supports the Franklin Report's conclusions on the acceptability of these pumps.

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