Text

Summary of 840126 Meeting W/Util,Westec,Bechtel,Sargent & Lundy & Inel in Bethesda,Md Re Equipment Environ Qualification Review.Agenda & List of Specific Equipment Qualification Deficiencies Encl
	ML17195A103
Person / Time
Site:	Dresden, Quad Cities, 05000000
Issue date:	01/30/1984
From:	Gilbert R; Office of Nuclear Reactor Regulation
To:	; Office of Nuclear Reactor Regulation
References
	LSO5-84-01-047, LSO5-84-1-47, NUDOCS 8402010061
	Download: ML17195A103 (36)
	v • d • e

Docket Nos. 50-237/249/254/265 LS05-84-0l -047-January 30, 198.4,

LICENSEE:

COMMONWEALTH EDISON COMPANY (CECO)

FACILITIES:

Dresden Nuclear Power Station, Unit Nos. 2 and 3 Quad Cities Station, Unit Nos. 1 and 2

SUBJECT:

SUMMARY

OF MEETING HELD ON JANUARY 26, 1984 The NRC staff held a meeting in Bethesda, Maryland with representatives of CECo, Westec, Bechtel and Sargent and Lundy to disucss issues relating to the Equipment "Environmental Qualification Review for Dresden Units 2 and 3 and Quad Cities Units 1 and 2.

A list of attendees is provided in and an agenda of items discussed, including a list of specific equipment environmental qualification (EQ) deficiencies in tabular form, is provided in Enclosure 2.

CECo and their contractor personnel presented information relating to the procedures to complete the EQ review and to carry out subsequent audits.

They also responded to specific EQ deficiencies called out in the Fr~nklin Research Center TER previously sent to CECo and discussed already imple-mented or to be implemented resolutions to the deficiencies. Discussions among the staff and CECo and its representatives continued until agreement on each issue was reached.

It was agreed that CECo's draft response memorializing the discussions of the meeting would be submitted by February 29, 1984.

Each station was to be treated separately.

Upon receipt of CECo's draft response, the staff will give it a one or two day review and report the results of that review to CECo quickly. After receipt of the results of the staff's review, CECo will perform its final internal corporate review and, after an approximate four week period, will transmit a response to be attached to the staff's SER closing out the issue.

Based on this schedule, closure of this issue for Dresden 2 and 3 and Quad Cities* 1 and 2 should be c?mplet~ by mid-April.

Enclosures:

1.

List of Attendees

2.

Meeting Agenda cc w/enclosures:

See next page DL:\\6~ #5 RGi l'Hert: cc I !;JIJ/84:

Original signed by'

Robe~t A. Gilbert, Project Manager Operating Reactors Branch #5 Division of Licensing

Mr. Dennis cc Isham, Lincoln & Beale Counselors at Law One First National Plaza, 42nd Floor Chicago, Illinois 60603 Mr. Doug Scott Plant Superintendent Dresden Nuclear Power Station Rural Route #1 Morris, Illinois 60450 U. S. Nuclear Regulatory Commission Resident Inspectors Office Dresden Station Rural Route #1 Morris, Illinois 60450 Chairman Board of Supervisors of Grundy County Grundy County Courthouse Morris, Illinois 60450 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 III 799 Roosevelt Street Glen Ellyn, Illinois 60137 Mr. Gary N. Hri9ht, Manager Nuclear Facility Safety Illinois Department of Nuclear Safety 1035 Outer Park Drive, 5th Floor Sprin9field, Illinois 62704 Mr. D. R. Stichnoth, President Iowa-Illinois Gas and Electric Company 206 East Second Avenue Dav~nport, Iowa 52801 January 30, 1984 Robert G. Fitzgibbons Jr.

Isham, Lincoln & Beale Three First National Plaza Suite 5200 Chicago, Illinois 60602 Mr. Nick Kalivianakas Plant Superintendnet Quad Cities Nuclear Power Station 22712 - 206th Avenue N-0rth Cordova, Illinois 61242 Resident Inspector U.S. Nuclear Regulatory Commission 22712 - 206th Avenue North Cordova, Illinois 61242 Mr. Marcel DeJaegher, Chairman Rock Island County Board of Supervisors Rock Island County Court House Rock Island, Illi~ois 61201

LIST OF ATTENDEES Dresden Units 2 and 3, Quad Cities Units l and 2 Meeting of January 26, 1984 NAME A.FFILIATION

c. Crane HP.stec M. Neuhauser Bechtel J. Wahl Bechtel M. Rauckhorst Sargent & Lundy B. Rybak CE Co - Licensing B. Viehl CECo - Engineering D. Lamken CE Co Engineering N. Smith CECo - Engineering G. Frankovich CE Co Dresden J. Almer CECo - Dresden P. Shemanski NRC R. Ka rs ch NRC T. Le NRC R. Bevan NRC R. Gilbert NRC N. Chrissotimos NRC - Region I II T. CappucCi NRC - ACRS '

M. Yost INEL (NRC Consultant)

ENCLOSURE 1

ENCLOSURE 2 AGENDA FOR COMMONWEALTH EDISON MEETING WITH NRC STAFF TO RESOLVE ENVIRONMENTAL QUALIFICATION SER DEFICIENCIES FOR DRESDEN 2 AND 3 AND QUAD CITIES 1 AND 2

I.

GENERIC ISSUES A.

10 CFR 50.49 B.

Short Term Operation C.

Containment Transient Margins D.

Aging & Qualified Life E.

Maintenance and Surveillance II.

EQUIPMENT QUALIFICATION DOCUMENTATION A.

Submitted to NRC B.

Received from NRC III.

GENERIC EQ DEFICIENCIES NOTED IN SER/TER A.

Definitive Schedule for Corrective Actions

B.

Aging and Qualified Life C.

Safety-Related Display Instrumentation D.

Equipment Deleted from Scope E.

Temperature Switches and Solenoid Valves

F.

Containment Transient Margins IV.

RESOLVED POSITIONS CONSIDERED CLOSED A.

Equipment in NRC Category Illa B.

Equipment in NRC Category IIIb C,

Summary of Qualification Methods of Mild/Harsh Parameters V.

SPECIFIC EQ DEFICIENCIES NOTED INTER/SER A.

Cable B.

Differential Pressure Indicating Switch C.

Differential Pressure Transmitter D.

Distribution Panel, 125 V de E.

Electric Air Heater F.

Electrical Penetrations G.

Flow Switches H.

Flow Transmitters I.

Hydrogen Sensors J *. Level Indicating Transmitter Switches K.

Level Switches

Presented.as* common to Zion, Dresden*, and Quad Cities on January 25, 1984.

v.

SPECIFIC EQ DEF.ENCIES NOTED IN SER/TER (CONT' L.

Level Transmitters M.

Local Control Panels N.

Local Panels

o.

Monitors Acoustic P.

Motor Cont~ol Centers, 480 v Q.

Motor Driven Pumps R.

Motor Exhaust Fans

s.

Motor Operators T.

Position Switches

u.

Pressure Switches

v.

Pressure Transmitters

w.

Radiation Detectors

x.

Room Coolers (Fan Motors)

Y.

Solenoid Valves

z.

Switchgear, 4.16 kV AA. Temperature Elements BB. Temperature Switches cc. Terminal Blocks DD. Oils and Greases VI.

POTENTIAL PROBLEM AREAS A.

Cable - Pending Test Completion 2/84 B.

MSIV Solenoid Manifolds - Testing Completion Date (8/84) After Startup C.

RWCU Temperature Detectors (RTDs) - Potential Outage Constraints D.

Acoustic Monitors - Potential Outage Constraints

lIA. Correspondence to NRC 0

0 0

o 0

0 0

D. Peoples to J. Keppler - D3, QC1, QCz Master Lists F. Janacek to J. Keppler - QC1, QCz initial response IE Bulletin 79-0lB Response Dz, D3, QC1, QCz Revised IE Bulletin 79-0lB response Dz J. Abel to J. Keppler - D3, QC1, QCz revised response (11/1/80)

J. Abel to D. Eisenhut - Dz revised response (11/1/80)

T. Rausch to H. Denton TER Response Dz, D3, QC1, QCz TER Response Supplement QC1, QCz TER Response Supplement D3 TER Response Supplement Dz, D3, QC1, QCz - TMI Equipment E. Schwartz to D. Eisenhut - TMI Action Plan Equipment Qualification T. Rausch to H. Denton -

GE Drywell Analysis T. Rausch to H. Denton - Reaffirmance of JCOs B. Ryback to H. Denton - Proprietary Material B. Ryback to H. Denton TER Response Dz, D3, QC1, QCz B. Ryback to H. Denton - 10CFRS0.49 Response Dz, D3, QC1, Qz C. Reed to H. Denton - R.G. 1.97 and G.L. 82-33 Commitments IIB. Correspondence from NRC 0

0 0

0 IE Bulletin 79-01 IE Bulletin 79-0lA J. Keppler to C. Reed IE Bulletin 79-0lB NRC Request to Dz IE Bulletin 79-0lB Supplement D. Ziemann to D. Peoples - Schedule and Clarific~tions CLI 80-Zl Staff Orders Dz, D3, QC1, QCz IE Bulletin 79-0lB Supplement No. Z IE Bulletin 79-0lB Supplement No. 3 Staff Order G. Lainas to J. Abel ~ Partial NRC Review Dresden Z T. Novak to J. Abel - Partial NRC Review Dresden 3 T. Ippolito to J. Abel -

NRC SER-QC1, QCz T. Ippolito to J. Abel -

NRC SER - D3 D. Crutchfield to J. Abel -

NRC SER-Dz GL-8Z-09 Memorandum to D. Eisenhut from P. O'Connor - JCO Evaluation D. Crutchfield to L. DelGeorge NRC SER-Dz, D3 D. Vassallo to L. DelGeorge - NRC SER-QC1, QC2 03/04/80 04/ZZ/80 06/10/80 08/ZZ/80 10/Z9/80 10/30/80 09/04/81 OZ/03/8Z OZ/Z3/8Z 04/Z9/8Z 08/0Z/8Z Ol/Z5/83 OZ/01/83 OZ/14/83 04/04/83 05/19/83 11/15/83 OZ/08/79 06/06/79 01/16/80 OZ/15/80 OZ/Z9/80 03/Z8/80 05/Z3/80 08/Z9/80 09/Z9/80 10/Z4/80 10/Z4/80 OZ/13/81 04/01/81 06/03/81 06/03/81 06/10/81 04/Z0/8Z 10/19/8Z 12/29/8Z 01/18/83

.. ~~;,.,

COMMONWEALTH EDISON MEETING WITH NRC STAFF TO RESOLVE lNVIRONMENTAL QUALIFICATION SER DEFICIENCIES DRESDEN AND QUAD CITIES Ill.

GENERIC EQ DEFICIENCIES A.

Deficiency In many instances, the licensee has conmltted to replace equipment during a refueling outage following receipt of the qualified components ons I +e.

It is cone I uded that the 11 censee has not provided a definitive schedule for the completion of corrective actions In compliance with NRC SER requirements.

B; The licensee has not resolved the NRC concern regarding aging and qualified life <Dresden 2 only):.

C.

The licensee has not resolved the NRC concern regarding Identification of safety-related display instrumentation.

The licensee wll I provide component evaluation sunmary sheets for display instruments that provide Infor-mation only to the operators by June 1982.

Justification for exclusion of safety-related instruments from this list should contain a description of the ability to meet the requirements of Regulatory Gulde 1.97, Revision 2 (Dresden 2 only).

D.

The licensee has deleted various Items from the list of equipment Items to be qualified.

FRC does not agree with the licensee in this regard (Dresden 2 only).

049k Reference TER, Section Page 5-1 DETAILED AGENDA Proposed Resolution 5 A definitive schedule for the completion of corrective actions in compliance with NRC SER requirements has been established. The schedule for completion of corrective action was reflected In Section 1.3 of the Individual *component summary sheets In Attachment I to the Dresden and Quad Cities TER responses for components In NRC Categories l.B, II.A, and 11.B.

The schedule was also reflected In the May 19, 1983, transmittal from B. Rybak to H. Denton as required by 10 CFR 50.49.

TER, Section 5 Presented as generic Issue conmon to Zion, Dresden, and Quad Cities on January 25, 1984.

Page 5-1 TER, Section 5 Equipment quallflcatlon summary sheets were provided In the Dresden 2 TER response Page 5-1 April 4, 1983, for the Instruments Identified by the FRC Item numbers shown below.

Instrument Identification LT-2-1641-1 LT-2-1626 PT-2-1625 LT-2-646-A/B LT-2-263-61 PT-2-647-A/B PT-2-662 FRC Item Number 70 72 75 73 73 76 76 FCR Item 69 referred to DPT-2-1602-12.

This transmitter ls not Installed In the plant and has, therefore, been deleted from the scope of the environmental quallflcatlon program.

Additional and revised system component evaluation worksheets (SCEWs) were provided In the revised IE Bulletin 79-018 response submitted May 19, i983.

CECo's position regarding Regulatory Gulde 1.97~ Revision 2, compliance schedule was provided In a letter from C. Reed to H. Denton, dated November 15, 1983.

Equipment qualification was stated In Attachment I to the Dresden 2 TER response~

the Instruments Identified by FRC Item number shown below.

TER, Section 5 a.

Page 5-1 Instrument ldenflcatlon LT-2-1641-1 LT-2-1626 PT-2-1625 LT-2-646-A/B LT-2-263-61 PT-2-647-A/B PT-2-662 FRC Item Number 70 72 75 73 73 76 76

Oeta i I ed Agenda (continued)

Def iclency Reference Proposed Resolution D. (continued)

FCR Item 69 referred to DPT-2-1602-12.

This transmitter Is not lnstal led In "'the plant and has, therefore, been deleted from the scope of the environmental quallficatlon program.

E.

Appendix D of the TER discussed concerns which require resolution with regard to temperature switches and solenoid valves.

F. *It appears that the licensee has not resolved the NRC concern regarding margins applied to the ln:...containment temperature profile (Dresden.2 on I y) 049k

b.

CECo's response to Regulatory Gulde 1.97, Revision 2, Is provided In the lett'er from C. Reed to H. Denton, dated November 15, 198}.

TER, Section Page 5-2 5 Appendix D concerns were addressed In the 30-day response letter, Mr. T. Rausch to TER, SEctlon 5 Page 5-2, Dresden 2&3 Page 5-1 Quad Cities I & 2 Mr. H.R. Denton, dated February I, 1983.

In addition, the temperature switch component sunmary sheets were Included In Attachment I to the Dresden and Quad Cities TER responses.

No deficiencies related to solenoid valves were Identified In Appendix D to the Dresden TER; therefore, no action by CECo Is required for this Item.

Presented as generic Issue conmon to Zion, Dresden, and Quad Cities on January 25, 1984.

2

IV.

RESOLVED POSITIONS CONSIDERED CLOSED A.

EQUIPMENT IN NRC CATEGORY IIIA (equipment exempt from qualification)

Dresden 2:

FRC Item 42 - A0-2-220-51, 52 FRC Item 69 - DPT-2-1602-12

FRC Item 70 - LT-2-1641-1

FRC Item 72 - LT-2-1626

FRC Item 73 - LT-2-646A, B*, LT-2-263-61

FRC Item 76 - PT-2-647A, B* ' PT-2-662

These items were reinstated in the program per Dresden 2 TER Appendix C B.

EQUIPMENT IN NRC CATEGORY IIIB (equipment not in the scope of the review)

Dresden 2:

FRC Item 20 - M0-2-3702 FRC Item 21 - M0-2-3703 FRC Item 27 - M0-2-1501-20A, B* ' M0-2-1001-5A, B FRC Item 28 - M0-2-1501-38A, B FRC Item 29 - M0-2-1501-22A, B FRC Item 30 - M0-2-1402-3A, B; M0-2-1402-4A, B FRC Item 31 - M0-2-1501-18A, B FRC Item 32 - M0-2-1501-13A, B; M0-2-1501-19A, B FRC Item 33 - M0-2-7503 FRC Item 34 - M0-2-1001-2A, B, c FRC Item 35 - S0-2-1601-51A, B* ' 65; 68 FRC Item 36 - S0-2-1601-52A, B FRC Item 37 - S0-2-1601-71 FRC Item 38 - S0-2.;..1601-66; 67; 69; 70 FRC Item 39 - S0-2-8501-2A, B FRC Item 40 - A0-2-2001-5; 6

FRC Item 43 - A0-2-220-45 FRC Item 61 - DPIS-2-261-35A through 35H FRC Item 67 - FT-2/3-7541-40A, B FRC Item 106 - Time Delay Relay FRC Item 107 - Time Delay Relay

This item has subsequently been determined to be in a harsh environment, thus requiring qualification Dresden 3:

FRC Item FRC Item FRC Item FRC Item FRC Item FRC Item 14 - M0-2/3-7503 21 - M0-3-1501-38A, B 23 - M0-3-1501-20A, B; M0-3-1001-5A, B; M0-3-3702 39 - DPIS-3-261-35A through H 54 -

FT-2/3-7541~40A, B 59 - LIS-3-263-58A, B 1

IV.

RESOLVED POSITIONS CONSIDERED CLOSED (Continued)

Quad Cities 1:

FRC Item 12 - PS-l-1462A, B. C, D FRC Item 62 - FT-l/2-7541-6A, B Quad Cities 2:

FRC Item 12 -

PS-2-1462A~ B, C, D C.

SUMMARY

OF QUALIFICATION METHODS The qualification methods discussed in Paragraphs 4.3.5 and 4.3.6 of the Franklin Research Center's technical evaluation report for Dresden Units 2 and 3 respectively are revised as follows.

A number of components were included in the original IE Bulletin 79-0lB response which could be subjected to maximum temperatures between 104 and 120F for reasons other than direct exposure to a loss-of-coolant accident (LOCA) or high-energy line break (HELB) environment.

It was initially thought that this environment should be classified as more severe than nonharsh (benign) conditions and an additional category called a mild environment was created in the IE Bulletin 79-0lB.response for this equipment.

A subsequent examination of plant operating experience, vendor information, industry standards, regulatory criteria, and potential failure mechanisms for equipment in this mild category has led Commonwealth Edison Company (CECo) to the conclusion that this additional category is not required.

The justification for this revision is presented below.

CECo's position with respect to areas where the temperature does not exceed 120F is that these are mild temperature areas and as such do not expose equipment to immediate, prolonged, or significant high-stress conditions.

The maximum temperature of equipment represents no significant change from the normal temperature for equipment located in these areas.

For all equipment located in these areas, the mild temperature environment is the result of normal plant operation, the loss of the heating, ventilating, and air conditioning (HVAC) system, or operation of equipment required for post-accident plant recovery.

It is not the result of direct exposure to a LOCA or HELB environment.

In all cases the increase in temperature from the normal temperature to the maximum of 120F will be gradual.

The resulting applied stresses on the equipment are relatively low and well within the maximum stress level capability of the equipment which is conservatively designed, fabricated, and installed as supported by equipment* design specifications and manufacturers' data.

Operability of similar equipment in such mild temperature environments has been demonstrated by many years of experience in th~ utility industry.

In addition, operating experience (e.g.,

Licensee Event Reports) does not indicate that a common-mode failure of safety-related equipment resulting from mild temperature environments is a problem.

Therefore, no additional evaluations or documentation are necessary to ensure that this equipment will perform its safety function.

2

'This 'justification was found satisfactory by Franklin in the January 1983 TER for Quad Cities Units 1 and 2, Section 4.3.3.2.

A further discussion concerning the qualification of safety-related electrical equipment located in a mild environment which CECo also endorses can be found in Reference 1.

This equipment was reevaluated on a case-by-case basis and reassigned to either the harsh or mild (benign) category as shown in Table 1.

As a further clarification, the terms "nonharsh" and "mild" are now used synonymously in the report reflecting the current usage of these terms in the nuclear industry.

In support of this position, we note that the latest revision of 10 CFR 50.49 excludes equipment in a mild environment from the present equipment qualification effort.

The licensee's position on the above qualification methodology is summarized below as reflected in the individual equipment status summary sheets.

1.

A harsh environment is defined as any one or a combination of any number of the following conditions.

a.

Temperature above 120F

b.

Total radiation exposure above 5 x 104 rads

c.

Pressure transient resulting from a LOCA or HELB inside the drywell, the pressure suppression pool, and the main steam tunnel.

2.

Qualification of humidity will be required only when the humidity is in conjunction with harsh temperatures.

3.

A mild (nonharsh) environment must meet all of the following criteria.

a.

Temperature equal to or lower than 120F

b.

Total radiation below 5 x 104 rads

c.

Pressure no higher than that of all plant locations other than the drywell, the pressure suppression pool, and the main steam tunnel, i.e., less than or equal to atmospheric pressure.

4.

CECo's approach to achieve environmental qualification of safety-related electrical equipment is summarized below in Table 1 and the notes which follow.

TABLE 1

SUMMARY

OF QUALIFICATION METHODS Temperature Radiation Mild Harsh Mild Note a Note b Harsh Note c Note d 3

Notei:

a.

Equipment located in a mild environment is not included within the scope of the NRC SER in accordance with 10 CFR 50.49.

No action by the licensee is required.

b.

Material evaluation or qualification testing or a combination of both will be performed to ensure that equipment in this category is fully qualified for the harsh temperature environment.

If the component or part of the component is found not to be qualified, its replacement will be complete by the end of the second refueling outage after March 31, 1982 or by March 31, 1985, whichever is earlier.

c.

The component will be qualified for the harsh radiation environment only by either a combination of analysis and testing, qualification testing, *or by replacement with a fully qualified component.

The replacement schedule will be as stated in Note b above.

d.

The component will be qualified by testing or replaced with a qualified component.

The replacement schedule will be as stated in Note b above.

5.

Equipment qualification for submergence and/or containment spray, if required, will be handled by analysis or testing as appropriate.

REFERENCES

1.

A Nuclear Industry Position Regarding Environmental Qualification of Safety-Related Electrical Equipment Subjected Only to Mild Environments, Submitted to H. R. Denton of the NRC by s. H. Howell of the AIF in a Letter dated July 2, 1980.

4

COMMO~E~LTH EDISON MEETING WITH NRC STAFF TO RESOLVE ENVIRONMENTAL QUALIFICATION SER DEFICIENCIES DRESDEN AND Q0AD CITIES ID GEND:

I

= Quad Cities Unit I 2 = Quad Cities Unit 2

= Dresden Unit 2

= Dresden Unit }

one = No deficiencies noted SPECIFIC EQUIPMENT EQ DEFICIENCIES Description (Manufacturer, tRC I tern Number __

Mo_d_e_l~

1 _E_t_c_) __

t\\.

E.LECTRICAL CABLE fi l:

2:.

49

None 92 65 tic I :. 51, 5}, 55, 56

~2:

J494c None 88,94,95, 96,97 63,67,68, 72, 77 General Electric cable Model Sl-57275; Vulkene Insulated switchboard wire General Electrlc and Simplex cable; butyl rubber-Insulated with PVC jacket; power and control functions NRC Category l.B l.B DETAILED AGENDA Deficiencies Documented evidence of quallflcatlon Inadequate Documented evidence of qualification Inadequate Proposed Resolution Testing and analysis had not been performed on this cable at.. flA time of the TER/SER review; therefore, quallflcatlon document~llll' tlon was noted as being Inadequate by FRC.

Quallflcatlon deflcl-

encles for qualification time, material aging, humidity, temperature, pressure and radiation were orlglnally to be resolved by type testf ng.

However, prior to testing, EDS Nuclear evaluated Wyle Test Report 44114-2 and concluded that the quallflcatlon deficiencies for pressure, radiation, and relative humidity could be resolved by that test report, and the remaining deficiencies could be resolved by an analysis utilizing Arrhenius methodology to extrapolate the test results. All deficient parameters were satisfactorily qualified by Wyle Test Report 44114-2 and EDS Analysis, Environmental Qualification of General Electric Sl-57275 Electrical Cable Report 04-0590-69, Rev I, October 7, 198}.

Testing and analysis had not been performed on this cable at the time of the TER/SER review; therefore, qualification documenta-tion was noted as being Inadequate by FRC.

Quallflcatlon defici-encies for qualification time, material aging, humidity, tempera-ture, pressure, and radiation are being resolved by type testing.

Prior to testing, It was determined that the term "Anhydrex XX"*

(identified as the Insulation material In QCI Item 56, D2 Items 95 and 96, and DJ Items 68 and 72) was the Simplex name fo their butyl rubber insulation.

Because SCEWs existed for Sil!l>lex

butyl rubber-Insulated cable, al I references to cables with Anhydrex XX Insulation have been deleted from the quallflcatlon program to eliminate unnecessary dupllcation. All deficient parameters will be qualified by Wyle Test Plan 45916-0J, Final Qualification Plan for Various Power Control and Instrumentation Cables.

This document ls to be completed In February 1984.

I/.

Specific Equipment EQ Deficiencies (continued)

Description (Manufacturer,

)=Re Item Number _ _...;.M..;..;o'""'d"""e-'-1-'-,-=-Et.;...c:;;:) __

~* Electrical Cable (continued)

~I: 54

~

iG2: None 2:

89 3:

71

~

I:

2:

J :

,n:

50 None 98,99 69,70 None None 87 78 OCI

None

~2: None 1)2:

93

,n:

66

>494.c General Electric cable; cross-linked poly'-

ethylene CVulkene)-

insulated with PVC jacket; control functions Simplex cable; poly-nylon-Insulated single/

multlpalr Instrumen-tation cable Simplex cable; threo-conductor twisted with overall shield~ Instru-mentation wire General Electric cable; multipair thermocouple extension cable with overal I shield NRC Category --------=D~e~f~lc.=...;...le~n~c~i~e~s-----~

l.B Documented evidence of qualification Inadequate l.B l.B l.B Documented evidence of qualification Inadequate Documented evidence of qualification*

Inadequate Documented evidence of qualification Inadequate 2

Proposed Resolution Testing and analysis had not been performed on this cable at the time of the TER/SER review; therefore, quallflcatlon documentation was noted as being Inadequate by*FRC.

Qualification deficiencies for qualification time, material aging, humidity, temperature, pressure, and radiation were originally to be resolved by type testing, engineering analysis, or replacement.

Conmonwealth Edison has reviewed a comparison analysis conducted by EDS, Environmental Qualification of General Electric Sl-58743 and Sl-58281 Electrical Cables, Report 04-0590-50, Rev O, November 18, 1982.

Although the analysis states that the cables are qualified, Conmonwealth edlson has determined that a more detailed analysis to establish similarity to previously tested General Electric specimens will be conducted to fully document qualification.

If this analysis cannot demonstrate quallflcat~

In CECo's judgment, the cables will be type tested or replacedJlllllll' Testing and analysis had not been performed on this cable at the time of the TER/SER review; therefore, qualification documentation was noted as being Inadequate by FRC.

Qualification deficiencies for qualification time, material aging, humidity, temperature, pressure, and radiation are to be resolved by type testing.

Prior to testing, It was determined that the polynylon-lnsulated cable and the slngle/multlpalr Instrumentation cable are the same.

Therefore, all references to the polynylon-lnsulated cable have been deleted from the qualification program to eliminate unnecessary duplication.

All deficient parameters are being qualified by Wyle Test Plan 45916-03, Final Qualification Plan for Various Power, Control, and Instrumentation Cables.

This document Is to be completed In February 1984.

Testing and analysis had not been performed on this cable at the time of the TER/SER review; therefore, qualification documentation was noted as being Inadequate by FRC.

Qualification deficiencies for qualification time, material aging! humidity, temperature, pressure, and radiation are to be reso ved by type testing.

Al I deficient parameters are being qualified by Wyle Test Plan

~

45916-03, Final Qualification Plan for Various Power, Control,...,,

and Instrumentation Cables.

This document Is to be completed In February 1984.

Testing and analysis had not been performed on this cable at the time of the TER/SER review; therefore, qualification documentation was noted as being inadequate by FRC.

Qualification deficiencies for qualification time, material aging, humidity, temperature, pressure, and radiation were Identified. A review of the applications for this cable Indicated Its only use was with originally Installed thermocouples.

There are no safety-related applications for the thermocouples In the plant; therefore, the cable does not require qualification. All references to this cable have been deleted from the qualification program.

New environmentally qualified thermocouples and thermocouple extension cables have been Installed as part of the modifications for a qualified suppression pool temperature monitoring system.

V.

Sff~if/ic EtfuipmCnt EQ Deficiencies (continued)

FRC ltcm~Number Description (Manufacturer, Model, Etc)

A.

Electrical Cable (continued)

QCI:

QC2:

D2:

D3:

QCI:

QC2:

D2:

D3:

None None 90 64 None None.

91 76 General Electrlc cable; cross-linked poly-ethylene Insulation with neoprene Jacket General Electric cable; rubber-insulated with a hypalon Jacket NRC Category ~~~~~~--"De'-"--'-f~l~c~le~n~c~l~e~s~~~~~~

l.B l.B DoCumented evidence of qualification Inadequate Documented evidence of qualification Inadequate B.

DIFFERENTIAL PRESSURE AND 'INDICATING SWITCHES

.QCI: 32 QC2: 32 D2:

62 D3:

50

'90494c Barton 289 Statlc-0-Rlng 12R2-KK815-V l.B Documented evidence of quallflcatlon Inadequate l.B Documented evidence of qualification Inadequate Proposed Resolution Testing and analysis had not been performed on this cable ~t the time of the TER/SER review; therefore, qualification documentation was noted as being Inadequate by FRC.

Qualification deficiencies for quallflcatlon time, material aging, humidity, temperature, pressure, and radiation were Identified.

Review of the applications of this cable Indicated Its only use was In the radiation monitoring system, which ls not a safety-related system.

Therefore, air references to this cable were deleted from the quallflcatlon program after It was determined the cable Is not used In safety-related appllcatlons.

Testing and.analysts had not been performed on this cable at the time of the TER/SER review; therefore, qualification documentation was noted as being Inadequate by FRC.

Quallflcatlon deflclen~

for qual lflcatlon time, material aging, humidity, temperature,.

pressure, and radiation were Identified.

Review of the appllcatlons of this cable Indicated Its only use was In the radiation monitoring system, which Is not a safety-related system.

Therefore, all references to this cable were deleted from the qualification program after It was determined the cable Is not used In safety-related applications.

These components were scheduled for replacement; however no qualified replacement was Identified at the time of the fER!SER review.

Therefore, documented evidence of quallflcatlon was Indicated as Inadequate. They will be replaced by qualified Rosemount Model 1153, Serles B transmitters. Qualification Is required for temperature, pressure, humidity, and radiation during post-accident conditions.

Rosemount has tested Its Model 1153, Serles B transmitters and provided the quallflcatlon documentation In Test Report 108025, Rev B, dated February 1983.

The report has been reviewed and evaluated and found to qualify the transmitters for the required conditions. The qualified I~

of the Model 1153, Serles B transmitters has been determined b~

Rosemount to be 20 years; therefore, these components will require replacement after this period.

These components were scheduled for replacement; however, no qualified replacement was Identified at the time of the TER/SER review.

Therefore, documented evidence of qualification was Indicated as Inadequate.

They will be replaced by qualified Rosemount Model 1153, Serles B transmitters. Qualification Is required for temperature, pressure, humidity, and radiation during post-accident conditions.

Rosemount has tested Its Model 1153, Serles B transmitters and provided the qualification documentation In Test Report 108025, Rev B, dated February 1983.

The report has been reviewed and evaluated and found to qualify the transmitters for the required conditions. The qualified life of the Model 1153, Serles B transmitters has been determined by Rosemount to be 20 years; therefore, these components wit I require replacement after this period.

Speci fie Eguipment EQ Deficiencies* (continued)

Description CManu facturer, JC I tern Number __

Mo-'-"d""'e-'-1.._,...:E:..;t-=c_,,_) __

NRC Category _______

Oe_f_lc_ie_n_c_i_e_s _____ ~

Differential Pressure and Indicating Switches (continued) t:

~*

61 39

~I: 35

~2: 35 Barton 288

Barton DIFFERENTIAL PRESSURE TRANSMITTERS I:

~I:

,.2:

68 47 None None Barton 386 l.B Documented evidence of qualification Inadequate l.B Documented evidence of qualification Inadequate II.A Documented evidence of qualification inadequate 4

Proposed Resolution These components were scheduled for replacement; however, no qualified replacement was identified at the time of the TER/SER review.

Therefore, documented evidence of qualiflcatlon was Indicated as Inadequate.

They will be replaced by qualified Rosemount Model 1153, Serles B transmitters. Qualification ls required for temperature, pressure, humidity, and radiation during post-accident conditions. Rosemount has tested Its Model 1153, Serles B transmitters and provided the qualification documentation In Test Report 108025, Rev B, dated February 1983.

The report has been reviewed and evaluated and found to qualify the transmitters for the required conditions.

The qualified life of the Model 1153, Series B transmitters has been determined by Rosemount to be 20 years; therefore, these components will require replacement after this period.

These components were scheduled for replacement; however, no qualified replacement was Identified at the time of the TER/SER review.

Therefore, documented evidence of quallflcatlon was Indicated as Inadequate. They will be replaced by qualified Rosemount Model 1153, Serles B transmitters. Qualification Is required for temperature, pressure, humidity, and radiation during post-accident conditions. Rosemount has tested Its Model 1153, Serles B transmitters and provided the quallflcatlon documentation In Test Report 108025, Rev B, dated February 1983.

The report has been reviewed and evaluated and found to qualify the transmitters for the required conditions.

The qualified life of the Model 1153, Serles B transmitters has been determined by Rosemount to be 20 years; therefore, these components will require replacement after this period.

Analysis of this component had not been performed at the time of the TER/SER review; therefore, documented evidence of qualifi-cation was Indicated as Inadequate. These components are locate~

In an area of the plant where the normal environment Is

~

considered mild.

However, the radiation level In this area Is considered harsh during post-accident conditions, and qualification Is required for radiation only.

Subsequent to the response submittal, a test report was located. Test Report WCAP 7410-L, Section 4, qualifies these components for higher radiation dose than required.

A concern was presented that because a load resistor and power supply for these components were located outside the test enclosure, they could not be qualified. The resistor was Installed to extend the life of a transistor at high temperatures (300F).

The accident conditions will not cause temperatures higher than 114F; therefore, the resistor ls considered expendable.

The power supply has been located In a mild environment area of the plant.

It is not subjected to any harsh conditions. Therefore, these Barton 386 transmitters are considered qualified for the required environmental conditions at the Dresden/Quad Cities units.

,¥._.

Spcci fie Equipment [Q Deficiencies (continued)

Description (Manufacturer,

'RC item Number __

M_o_d_e-'l.....

1-=Et""-c"') __

~.

DISTRIBUTION PANELS

~I: 44

,>CZ: 44 Cutler.,.Hanmer i.,

ELECTRIC AIR HEATERS i)C-1 : 59

~2:

~3:

84 51 Chroma lox 1-113462/2-113462 1° ELECTRICAL PENETRATIONS

~GI: 52 11<'2* None

~2: 55

~3: 73 1!1494c General Electric GE-NEBS NRC Category --------=De;.:;...;.f~lc.=..le~n~c~l~e~s-----~

l.B Documented evidence of qualification Inadequate l.B Documented evidence of qualification Inadequate I I.A Documented evidence of qualification Inadequate NA None II.A Documented evidence of qualification Inadequate; adequate similarity not established. Aging evaluated Inade-quately. Quallfled llfe not established.

No program to Identify aging degradation.

II.A Documented evidence of qualification Inadequate 5

Proposed Resolution Quallflcatlon deficiency was Identified as the radiation pacameter and was originally to be resolved by analysis and/or testing.

This deficiency was applicable because these panels had not been qualified to a harsh radiation environment.

Subsequently, the approach adopted for qualification was a combination of analysis and testing. Bechtel performed an engineering analysis (Chron 7332) for nonmetallic components except those associated with the circuit breaker.

This analysis Indicated that all these nonmetallic components had radiation damage thresholds In excess of the required radiation environment. A radiation test was conducted by Wyle for the breakers, and Wyle Test Report 45917-3 was evaluated. The deficiency ls resolved by this analysis and the test report. This Item Is fully qualified to all environmental parameters.

This equipment was originally scheduled for replacement with a quail fled heater because the quallflcatlon was not established at the time of TER/SER review.

Radiation was the only harsh environ-ment requiring qualification; therefore, all the materials were reevaluated.to determine whether qualification could be established by analysis. Subsequently, the unit was qualified by Engineering Analysis for Nonmetallic Components, Bechtel Power Corporation, July 8, 1983.

The original documentation submitted during the TER/SER review was Incomplete because of the ongoing data search for these penetra-tions. Qualification was required for all the accident and normal environment parameters Inside the drywall.

Subsequent to the sub-mittal of the TER response, environmental Information study, Report EWA-EAF98-94, was received from General Electric CGE)

.ill along with another report dated May 30, 1972, for the electrlca111111' penetration assemblies sunmary data. These reports, as well as GE Report F-01 CAprll 30, 1971), GE Report 994-75-011 (April 29, 1975), and a special report for an Incident at Dresden Unit 2 In June 1970, have been reviewed and found to adequately qualify these penetrations for the normal and accident environment.

These electrical penetration assemblies contain metal I le as wel I as nonmetal I le mater la ls.

Deterioration due to thermal aging Is Insignificant for nonorganlc and metallic materials under the specified environmental conditions.

Therefore, component aging Is based on organic materials.

GE Report 994-75-011 demonstrates a cycling and aging test to simulate a nuclear power station startup and shutdown cycle.

V.

Specific Egu i pmont EQ Def I c I enc I ~"s (cont I nued)

Description (Manufacturer, FRC Item Number _ __;.Mo....;;...:d-'e-'-1-L,_E=-t'-'c""') __

F.

Electrical Penetrations (continued)

,G.

FLOW SWITCHES

.QCI: 11 QC2: 11 D3:

49 DZ:

63 D3:

55 b494c Barton, 289 McDonnel AF-2 NRC Category --------=De-'-"f~lc"'-'-'le~n-'c~l~e~s-----~

l.B Documented evidence of qualification inadequate l.B Documented evidence of qualification inadequate 6

Proposed Resolution This IOOF temperature change and 120 cycle test ls consistent with the requirement of IEEE Standard 317-1976 even though this standard was not In effect at the time of the qualification test. Because the penetration assemblies successfully wltKstood the cycling and aging test, which represents significant thermal stressing, the aging qualification Is considered supportable by this test.

In addition, the penetration *assemblies can be considered to have a remaining qualified life of 30 years. This conclusion Is based on the material analysis of the age-sensitive materials used In the FOi canister design electric penetrations CGE Report EWA-EAF98-94), their location within the assembly (which ls not subject to extreme temperature and radiation

degradation), and the fact that these assemblies continued to function during and subsequent to the June 5, 1970, depressurlzatlon Incident.

This 30-year qualified life requires that periodic maintenance and surveillance procedures be

.-~

established and Implemented.

Surveillance procedures are bel developed to detect conmon-mode failure mechanisms.

If unidentified aging or degradation mechanisms become apparent, upgraded replacement or maintenance programs will be developed to address these concerns.

Based on the above reports and the followup meetings with GE and the fact that they did perform satisfactorily during the June 5, 1970, Incident, It Is concluded that these penetrations are quallfled.

These components were scheduled for replacement; however, no qualified replacement was Identified at the time of the TER/SER review.

Therefore, documented evidence of qualification was Indicated as Inadequate.

They will be replaced by qualified Rosemount Model 1153, Serles B transmitters. Quallflcatlon Is required for post-accident radiation only. Rosemount Test Report 108025, Rev B, dated February 1983, has been evaluated and found to qualify the Rosemount Model 1153, Serles B transmitters for the normal service conditions and the postulated post-accident radiation at the Dresden and Quad Cities units. '1111111111' The Installed operational life of the Model 1153, Serles B has been determined by Rosemount to be 20 years; therefore, these components will require replacement at the end of this period.

These components were scheduled for replacement; however, no qualified replacement was Identified at the time of the TER/SER review.

Therefore, documented evidence of qualification was Indicated as Inadequate.

They will be replaced by qualified Rosemount Model 1153, Serles B transmitters. Quallflcatlon Is required for post-accident radiation only. Rosemount Test Report 108025, Rev B, dated February 1983, has been evaluated and found to qualify the Rosemount Model 1153, Serles B transmitters for the normal service conditions and the postulated post-accident radiation at the Dresden and Quad Cities units.

The Installed operational life of the Model 1153, Serles B has been determined by Rosemount to be 20 years; therefore, these components will require. replacement at the end of this period.

Spe'ci'f i c Equipment EQ Def i c I enc I es** (cont I nued)

Description (Manufacturer, iRC Item Number __

Mo_d_e_i~,_Et_c~> __

Flow Switches (continued) l:I: 63 ii:

66

,3:

56 3:

38

~: 64

,2:

65 Hercoid, DA5333 Hercoid, PPQW Mercoid, PPQW Barton, 288 Barton, 288

_Barton, 289 FLOW TRAN$MITTERS "194c 10,31 10,31 77, 78 41 46 General Electric GE/MAC 553 NRC Category _______

De_f_lc_le_n_c_l_e_s _____ ~

Proposed Resolution l.B Documented evidence of qualification Inadequate These components were scheduled for shielding or replacement~ and quallflcatlon was not available at the time of the TER/SER review.

Therefore, the documented evidence of qualification was considered Inadequate by FRC.

Quallflcatlon was required for post-accident radiation only.

The shielding design for these components has been completed, and the radiation environment Is now mlld. Therefore, these components are deleted from the.

quallflcatlon program.

Documented evidence of quallflcatlon Inadequate These components were scheduled for replacement; however no qualified replacement was Identified at the tjme of the fER/SER review.

Therefore, documented evidence of qualification was Indicated as Inadequate. They will be replaced by qualified Rosemount Model 1153, Serles B transmitters.

Qual lflcatlon ls**A required for post-accident radiation only.

Rosemount Test

-~*

Report 108025, Rev B, dated February 1983, has been evaluated and found to qualify the Rosemount Model 1153, Serles B transmitters*

for the normal service conditions and the postulated post-accident radiation at the Dresden and Quad Cities units.

The Installed operational life of the Model 1153, Serles B has been determined by Rosemount to be 20 years; therefore, these components will require replacement at the end of this period.

l.B I. Documented evidence of quallflcatlon These components were scheduled for replacement; however, no l.B l.B I.B II.A I.B Inadequate qualified replacement was Identified at the time of the TER/SER

2. Aging degradation evaluation Inadequate review.

Therefore, documented evidence of quallflcatlon was lndl-

3. Qualified life or replacement schedule cated as Inadequate.

They will be replaced by qualified not established Rosemount Model 1153, Serles B transmitters. Qual lflcatlon ls

4. Program not established to Identify required for post-accident radiation only.

Rosemount Test aging degradation Report 108025, Rev B, dated February 1983, has been evaluated and

5. Criteria regarding radiation not found to qualify the Rosemount Model 1153, Serles B transmitters satisfied for the normal service conditions and the postulated Documented evidence of qualification Inadequate 7

post-accident radiation at the Dresden and Quad Cities units.

The Installed operational life of the Model 1153, Serles B has been determined by Rosemount to be 20 years; therefore, these A components will require replacement at the end of this period.~

At the time of TER/SER review, these components were scheduled for either testing or analysis. The decision was made to test the component for radiation because radiation caused by a design basis accident Is the only harsh environment to which these components are ever subjected. Subsequently, the GE/MAC 553 transmitters were tested by Wyle Laboratories. Qualification was provided In Wyle Test Report 45917-1, July 30, 1982.

Review and evaluation of the test report revealed that these components are acceptably qualified for the required conditions.

'f!'.*

Specific Equipment EQ Deficiencies (continued)

Description (Manufacturer, f RC I tern Number __

Mo_d_e_I,.__E_t_c"'"") __

~*

Flow Transmitters (continued) bel: 61 Leeds And Northrup 000-0300-0300 I.

HYDROGEN SENSORS l.;>C I : None ru 2: None None None General Electric NRC Category _______

Oe_f_lc_le_n_c_l_e~s-----~

l.B Documented evidence of quallflcatlon Inadequate NA None

~. LEVEL-INDICATING TRANSMITTER SWITCHES 1k,)C I : None ru 2: None 71 60 f;

I:

2:

~494c 42 42 None 59 Yarway 4418CE Yarway 4418C NA None NA None l.B Documented evidence of qualification Inadequate l.B NA 111.B Documented evidence of Inadequate None None quallflcatlon 8

Proposed Resolution This component was originally scheduled for replacement; however, no qualified replacement was Identified at the time of TER/SER review.

Therefore, documented evidence of qualification was Indicated as Inadequate.

Subsequently, It was determined that this component would perform no safety-related function.

It provides only flow Indication for the SGTS and does not provide any control function.

The required control function for the system ls provided by FSL 1/2-7541-BA,B and -33A,B.

Therefore, this component ls deleted from the program.

These sensors were not part of the original IE Bulletin 79-0IB~

submittal and were added to the program after the SER/TER revllllllJ Quallflcatlon deficiencies were observed for operating time, tem-perature, pressure, relative humidity, and radiation.

CECo decided to replace this General Electric system, Including the sensors, with a qualified gas analyzer system Instead of qualifying by other means.

CECo has procured these gas analyzers and Is In the process of Installing these new systems.

These gas analyzers are manufactured by Comslp, Delphi System Division (Hodel K-IV).

EA&T Test Report 1035-1 for Comslp Is being evaluated to establish the qualification of these components; These components *were scheduled for replacement; however, no qualified replacement was Identified at the time of the TER/SER review.

Therefore, documented evidence of quallflcatlon was Indi-cated as Inadequate.

They wl II be replaced by qualified Rosemount Model 1153, Serles B transmitters. Qualification ls required for post-accident radiation only. Rosemount Test Report 108025, Rev B, dated February 1983, has been evaluated and fou'liiii.i.

to qualify the Rosemount Hodel 1153, Serles B transmitters for~

the normal service conditions and the postulated post-accident radiation at Dresden and Quad Cities units. The qualified life of the Hodel 1153, Serles B has been determined by Rosemount to be 20 years; therefore, these components will require replacement at the end of this period.

These components were scheduled for replacement; however, no qualified replacement was Identified at the time of the TER/SER review.

Therefore, documented evidence of quallflcatlon was Indi-cated as Inadequate.

They will be replaced by qualified Rosemount Hodel 1153, Serles B transmitters. Quallflcatlon Is required for posfi..-accldent radiation only.

Rosemount Test Report 108025, Rev B, dated February 1983, has been evaluated and found to qualify the Rosemount Hodel 1153, Serles B transmitters for the normal service conditions and the postulated post-accident radiation at Dresden and Quad Cities units. The qualified life of the Model 1153, Serles B has been determined by Rosemount to be 20 years; therefore, these components will require replacement at the end of this period.

~ Sp;gc i*.f i c Eqitt i pme~t-<"t\\J' O:~"tr{i*enc i ~~~;~ (cont I nued)

Description

(~anufacturer, 1,rn~ ~~~~(11- ~.~.u~?.e r ---'M__,o;_.;:d;...;;e...:.l.L, _E=-t'-'c=-=)--

~-

LEVE~ SW~TCHES

~I:

~2:

l>2:

~3:

None None None None Magnetrol 291 lL l>2:

'!03:

LEVEL TRANSMITTERS t.;lC I:

~2:

l>2:

~3:

12;73 None None None None None General Electric GE/MAC 553 ITT-Barton, 764 "1.

LOCAL CONTROL PANELS 1~1: 65 Harlo, DRAW-D/297 11lJ494c NRC Category _______

De_f_lc_le_n_c_l_e~s-----~

NA 111.A NA NA None None NA l.B Documented evidence of qualification inadequate.

9 Proposed Resolution These components were originally considered to be In a mild area; therefore, they were deleted from the qualification program.

Later, It was found that these components would be subjected to a harsh temperature environment for a short period of time during a LOCA.

These components were previously tested, and the test results are provided In Wyle Test Report 43235-1, May 2, 1977.

This report has been reviewed and evaluated and found to adequately encompass the required time and temperature environment for Dresden/Quad Cities units. Therefore, these.*

components are considered to be qualified.*

At the time of TER/SER review, these components.were scheduled**

either testing or analysis. The decision was made to test the component for radiation because radiation caused by a design basis accident ls the only harsh environment to which these components are ever subjected.* Subsequently, the GE/MAC Hodel 551 and 55} transmitters were tested by Wyle Laboratories.

Qualification was provided In Wyle Test Report 45917-1, July 30, 1982.

Review and evaluation of the test report revealed that these components are acceptably qualified for the required conditions.

These components were not Included In the November I, 1980, sub-mittal. They have been reevaluated as a result of THI modifica-tions and Included In the qualification program since that sub-mittal. These components have been tested for various environmental parameters, Including temperature and radiation, which are the only harsh environmental parameters under which these units will be required to operate. Documentation of quallflcatlon for these components Is provided In ITT-Barton Test Report RE-704-9.

This report has been reviewed and evaluated and found to adequately encompass both normal operating and accld~.iliiii.

environments.

Therefore, these components are considered to b'lllll' qualified.

These components were scheduled for replacement; however, no qualified replacement was Identified at the time of the TER/SER review.

Therefore, documented evidence of quallflcatlon was Indicated as Inadequate.

These panels are required to be qualified for radiation only.

A review of possible replacement panels on the market revealed that none were quail fled to meet the required radiation dose.

Therefore, the panels will be physically shielded to reduce their radiation dose to that of a ml Id environment.

The panel shielding wl 11 be completed by March 1985.

V.

Specific Equipment EQ Deficiencies (continued)

Description (Manufacturer, FRC I tern Number _ __;.Mo..:.=d:..::ec..:.l.._,-=-Et..:...c=.:)'"--

N.

LOCAL PANELS 02:

81 03:

57 Boss enclosure

0.

MONITORS, ACOUSTIC

.QCI:

QC2:

02:

03:

QCI:

QC2:

03:

02:

None None 103 None None 104 None 105 NOT Instruments Model 7810 sensors NOT Instruments Model IOOA preamp I I f I ers NOT Instruments Model 1040 flow detector P.

MOTOR CONTROL CENTERS QCI: 43 QC2: 43 02:

83 03:

62 0494c General Electric 1700 Serles NRC Category -~~~~~~De~f_i_c_le_n_c_l_e_s~~~~~~

l.B Documented evidence of qualification inadequate l.B None, pending modification l.B None, pending modifications I.B None l.B Documented evidence of qualification inadequate 10 Proposed Resolution These components were scheduled for replacement; however, no qualified replacement was Identified at the time of the TE~SER review.

Therefore, documented evidence of qualification was Indicated as Inadequate.

These panels are required to be qualified for radiation only.

A review of possible replacement panels on the market revealed that none were qualified to meet the required radiation dose.

Therefore, the panels will be physically shielded to reduce their radiation dose to that of a mild environment.

The panel shielding will be completed by_ March 1985.

These sensors are being replaced.

Replacements requlre*quall~

cation for temperature, pressure, humidity, spray, and radiation.

Replacement sensors are qualified to preliminary Wyle Test Report 45638-1, dated May 24, 1983.

The final test report Is expected to be Issued In February 1984.

Acoustic monitor testing was completed on April 13, 1983.

The preampllflers require qualification for radiation only and are qualified according to preliminary Wyle Test Report 45638-1, dated May 24, 1983.

The final test report Is expected to be Issued In February 1984.

Not applicable because these components are not subjected to harsh environmental conditions.

Qualification deficiency was Identified as the radiation para-meter and was originally to be resolved by analysis and/or testing. This deficiency was applicable because these MCCs h~

not been qualified to a harsh radiation environment.

Later, -Jiil' qualification was selected to be by the method of testing.

A

. detailed walkdown of the MCCs was completed to Identify the specific components of each MCC.

An Investigative study was undertaken to properly select the components to be Included In the test program.

These components, which were obtained from the stations with consideration for the vintage, were assembled Into a test model designed to be representative of all MCCs.

A radiation test was conducted for this model.

Wyle Test Report 45917-30 was evaluated.

The deficiency Is resolved by this test report, and this Item Is fully qualified to all environmental parameters.

~

V.

Specific Eguipment EQ Deficiencies (continued)

FRC Item Number Description (Manufacturer, Model, Etc)

Q.

MOTOR-DRIVEN PUMPS QCI: 2 QC2: 2 02: 79 QCI: 3 QC2: 3

'02: 80 03: 45 General Electric 5K6338XC23A General Electric 5K6336XCl93 General Electric 5K6637XC71A General Electric 5K6338XC23A 5K6637XC71A R.

MOTOR EXHAUST FANS QCI:

60 02:

85 03:

52 0494c General Electric 5K256BK2038 General Electric 5K256AK2037 NRC l.B Documented evidence of qualification inadequate l.B Documented evidence of qualification Inadequate 1.8 Documented evidence of qualification Inadequate II.A Documented evidence of quallflcatlon inadequate l.B Documented evidence of qualification Is inadequate 1.8 II Proposed Resolution The qualification of these components was not established at the time of TER/SER review, and the components were slated to be qualified for radiation during a post-OBA operation only.

General Electric has provided qualification documentation In Its Reports NEDC-30066 and 83NED024 (February 1983) for the pump motors at Dresden and In NEDC-30067 and 83NED025 (February 1983) for those at Quad Cities. Based on the evaluation of the data In these reports, these motors are adequately qualified for the*

normal and the postulated post-OBA environmental conditions *.

The qualification of these components was not established at the time of TER/SER review, and the components were slated to be quail fled for radiation during a post-OBA operation only....

General Electric has provided qua I lflcatlon documentation *in *A Reports NEDC-30066 and 83NED024 (February 1983) for the PlnlJ>....,-

motors at Dresden and In NEDC-30067 and 83NED025 (February 1983) for those at Quad Cities. Based on the evaluation of the data In these reports, these motors are adequately qualified for the

normal and the postulated post-OBA environmental conditions.

The qualification of these components was not established at the time of TER/SER review, and the components were slated to be qualified for radiation during a post-OBA operation only.

General Electric has provided qualification documentation In Its Reports NEDC-30066 and 83NED024 (February 1983) for the pump motors at Dresden and In NEDC-30067 and 83NED025 (February 1983) for those at Quad Cities. Based on the evaluation of the data In these reports, these motors are adequately qualified for the normal and the postulated post-OBA environmental conditions.

The qualification of these components was not established at the time of TER/SER review, and the components were slated to be qualified for radiation during a post-OBA operation only.

General Electric has provided quallflcatlon documentation In Its Reports NEDC-30066 and 83NED024 (February 1983) for the pump ~

motors at Dresden and In NEDC-30067 and 83NED025 (February 19~

for those at Quad Cities. Based on the evaluation of the data 1n these reports, these motors are adequately qualified for the normal and the postulated post-OBA environmental conditions.

The quallflcatlon of these components was determined to be Inade-quate at the time of the TER/SER review because qualified replacements were not Identified. Therefore, they will be replaced by qualified Westinghouse motors. Qualification Is required for radiation only.

Radiation qualification is documented In Westinghouse Test Report MM9112, dated January 1982.

Review of the test report revealed that these fan motors are qualified for the required radiation dose rate.

V.

Specific Equipment EQ Deficiencies (continued)

Description (Manufacturer, rRC I tern Number --=-Mo=d.::..e.:....I ----=E:..:.t-=c.:...> __

S.

MOTOR OPERATORS 02:

1-19,22-26 Limltorque Type SMB 03:

1-13,15-ac motors: Peerless, 20,22,24-30 Reliance, Llmltorque, QCI: 4-8, 13,14, Electric Apparatus 19,22-29,34, de motor: Peerless,

. 39,40,41,45, Rellanc~

46,68 QC2: 4-8. 22-:-29.

34, 39,40,41, 45,46.

0494c

NRC Category ~--------"De-'-f_l~c_le_n_c_l_e_s _____ ~

l.B, I I.A, 11.C Documented evidence of quallflcatlon Inadequate Demonstrate adequate slmllarlty between the equipment and the test specimen Evaluate age-related degradation for

. these operators Quallfled llfe or replacement schedule not established Establish a program to Identify aging degradation for these operators 12 Proposed Resolution I. Similar deficiencies were highlighted at both the Ores~en and Quad Cities stations.

The deficient environmental parameters were temperature, pres-sure, radiation, and operating time.

A discussion of each TER/SER deficiency follows.

o Previous79-018 submlttals did not reference the evidence of quallflcatlon that had already been provided by Llmltorque for existing equipment.

The SCEW sheets are being revised to Include this material.

Previous 79-0IB submlttals did not discuss the quallflcatlon of replacement equipment.

The selection of replacement operators and motors ls now complete, and the applicable Llmltorque test reports have been evaluated and found acceptable for quallflcatlon.

These test reports and letters fran Llmltorque stating....

appllcablllty of the reports to specific replacement equipment wlll be referenced on the revised SCEW sheets.

As replacement operators are Installed, all replacements wlll be qualified to Test Report 600461 or 600376 depending on their service condition.

o Previous 79-0IB submlttals did not reference existing

letters fran Llmltorque, which define the appl lcabl I lty of test reports to given equipment based on their similarity to the test samples.

The SCEW sheets are being revised to Include this material.

o Previous79-018 submlttals did not list any equipment sus-ceptible to age-related degradation on the SCEW sheets.

o Mobile 28 grease has been Installed on the torque and llmlt switches of all operators In the drywall and the steam tunnel to replace Beacon 325 grease, which hardened.

o Llmltorque has stated that Class 8 motors were aged to a 40-year qualified llfe prior to accident testing In Test Reports 80058, 80003, and WCAP-7410-L.

No other canponents are susceptible to age-related degradation according to Llmltorque Report 80058.

o Replacement motors and operators are qualified for the~

40-year llfe by Llmltorque Test Report 600376 and 60046.,.,,

as well as 80058.

o Aging In a mlld temperature environment Is not required In accordance with the 79-0IB response, Section 4.3.4, because any stresses due to aging are very small and well within the design of the equipment.

o Replacement schedules had not been provided In early 79-0IB responses but were provided In the May 1983 revision.

o Except for the replacement of Beacon 325 grease with more suitable, qualified grease, Llmltorque has Identified no other age-sensitive materials.

o The previous79-018 responses had addressed the maintenance/

surveillance programs generically rather than as specifically related to Llmltorques.

The existing maintenance and surveillance programs will be used to specifically address the maintenance and surveillance requirements of equipment qualification such as any required maintenance resulting fran use of canponents and parts with limited qualified life.

V.

Specific Eguipffient EQ Deficiencies (continued)

Description (Manufacturer, FRC I tcm Number __

Mo_d_e_l~1 _Et_c~> __

S.

Motor Operators (continued) 0494c NRC Category _______

Oe_f_lc_le_n_c_l_e_s _____ ~

Equipment peak temperature exceeds qualification temperature Spray criteria not satisfied Radiation qualification not satisfactory

. 13 Proposed Resolution o Th Is comnent Is on I y app 11 cab I e to FRC I tern 13 at Dresden Unit 2 CM0-2-2301-4).

The operator has already been replaced with a new SMB operator. Llmltorque Test R,port 600376 for the new operator has been evaluated and the operator Is qualified for the drywall environment.

o This comnent Is also applicable only to FRC Item IJ at Dresden Unit 2.

The replacement operator Is quail fled.as discussed In the preceding paragraph. All operators In the.

drywall that have operating times greater than 2 minutes will be replaced with those qualified to a spray environ-ment according to Llmltorque Test Report 600376.

o This comnent applies to FRC Items 2 and 13 for Dresden Un It 2.

FRC I tern 13 Is be Ing rep I aced with a qua I If led operator as discussed In Item I above.

FRC Item I is now

considered qualified based on Llmltorque Report 80003 an*

new radiation calculation CNUC-25), which showed the do to be below the B0003 tested dose.

II. Resolution for Llmltorques Inside the Drywell A. The SER/TER agreed with CECo's plan to replace al I Llmltorques Inside the drywall.

B. All SMB~ size operators and all operators with operating*

times greater than 2 minutes are being replaced with those qualified to Llmltorque Test Report 600376.

This report has been evaluated and has been found applicable to qualify these new operators to Dresden and Quad Cities environmental service conditions.

C. Operators with Type B motor Insulation and operating times less than 2 minutes are being qualified utilizing Test Report WCAP-7410-L, supplemented with a Bechtel thermal analysis CNUC-31), which demonstrates that the operators complete their function prior to exceeding the WCAP-7410-L test temperature.

D. Operators (described In Item C above) with motor brakes will have qualified replacement motors that do not require brakes.

Test Report 600376 has been evaluated and has been found applicable to qualify these new motors to the service

.4llllll conditions.

9 E. The one operator with an Electric Apparatus motor ls being quallf.led utilizing the WCAP-7410-L test report supplemented by a statement from Llmltorque that, for purposes of environmental qualification, the Electric Apparatus motor Is equivalent to a Rel lance motor as used In the WCAP test.

Ill. Resolution for Llmltorques Outside the Drywall A. Although previous SER/TER responses Indicated a total replacement of Llmltorque operators with de motors In the torus and steam tunnel, Llmltorque has stated by letter that, for the purposes of equipment quallflcatlon, the Class 8 Insulation system of Dresden and Quad Cities motors Is similar to the ac motors qualified In Test Report 80003.

Test Report 600461-80003 has been evaluated and found applicable to qualify these operators to their environmental service conditions as supplemented by the Llmltorque letter

V.

Specific Equipment EQ Deficiencies (continued) rRC Item Number Description (Manufacturer, Model, Etc)

S.

Motor Operators (continued)

T.

POSITION SWITCHES

'QCI: 58

-QC2: None 02:

57 03:

None 0119/lc NAMCo, EAOBO I I I 00 NAHCo, SA5A NRC Category ~~~~~~~De~f_l_c_le_n_c_l_e_s~~~~~~

1.8 Documented evidence of quallflcatlon Inadequate II.A 14 Proposed Resolution

8. Operators In the steam tunnel and torus with short operating times are qualified by Test Report 80003, supplemented by a Bechtel thermal analysis (NUC-29).

The analysis shows t-hat the thermally sensitive materials will not exceed the qualification test temperature In Report 80003.

C. Operators with unqualified motors wlll have replacement motors qualified to the service conditions and Llmltorque Test Report 600461-80003.

D. The motors In operators with motor brakes wlll be replaced with motors qualified to Report B0003, which do not require brakes, or the operators wlll be completely replaced with new operators qualified to either Test Report 600376 or Report

.80003 depending upon the service conditions.

At the time of TER/SER review, adequate evidence of quallflcatlon was not established for these position switches because qualified replacement switches were.not Identified. Qualification ls required for all the accident environmental parameters, and aging Is required because these components are subjected to harsh levels of radiation and temperature during normal operation.

At Quad Cities Unit I, the original switch has already been replaced with a NAMCo snap-lock Model EA180-11302 during November and December of 1982.

At Quad Cities Unit 2, the existing switch wlll be replaced with the above NAMCo model during the next station outage. Qualification data for these NAMCo replacement switches Is provided In NAMCo Test Report QTR 105, Rev 3, August 20, 1981.

This report has been reviewed and found to adequately qualify these new switches for the required accident environment.

To establish a designated llfe, an analysis Is being performed based on the data provided In the NAHCo test report.

At the time of TER/SER review, adequate evidence of quallflcat.n was not provided for these position switches (which Included POS-2-220-44, -45, -51, and -52 at Dresden Unit 2) because qualified replacement switches were not Identified.

In the TER response, It was Indicated that only POS-2-220-44 was required to be qualified; the others were Identified as exempt from quallflcatlon because they were located In mlld environments or not required to function as Class IE components, as In the case of POS-2-220-51 and -52.

Subsequently, It has been determined that POS-2-220-44 and -45 at Dresden Unit 2 and POS-3-220-44 at Dresden Unit 3 are required to be qualified because they are located In harsh environments.

The original switches will be replaced with qualified NAMCo Model EA180-11302.

These replacing switches are qua~lfled the same way as those in FRC. Item QCl:58.

. i

~.*.

Specif i0r£qu'i pinent i::Q Def ic lericl:es (cont I nued) rRC Item Number Description (Manufacturer,

Mode I, Etc)'

NRC Category ~~~~~~--'De....;_f_lc~le~n~c~l~e~s~~~~~~

T.

Position Switches (continued) 02:

58

.cD2:

54 D2:

56 D2:

102 0494c NAMCo, SA5A II.A Documented evidence of qualification inadequate NAMCo, 01200G (Mark II)

II.A Documented evidence of quallflcatlon Inadequate NAMCo, 01200G (Mark II)

II.A Documented evidence of qualification Inadequate Manufacturer unknown IV Documentation not made available 15 Proposed Resolution During the TER/SER review, FRC disagreed with the CECo position that these components could be deleted from the program because these are used for position Indication only, and failure of the switches will not affect the associated control circuits.

Therefore, these components were Identified as requiring quallflcatlon at the time of TER/SER review.

A subsequent TER response stated that these position switches should be exempted from qua 11 f I cat I on because a I ternat Ive s 1 gna Is for the Ind lcat I on of the correspond Ing va Ive pos It Ions are prov I ded by f I ow transmitters FT-2-645A, B, C, and D, which are localed In a mild environment on Instrument rack 2202-10 In the southwest corner room.

Therefore, these position switches should be exempted JJ...om quallflcatlon.

'According to the TER/SER evaluations, FRC did not concur with CECo In Its assertion that position Indication for containment I so I at I on va Ives Is not requ I red.

FRC cone I uded that posit Ion Indicators should not be deleted from the environmental qua 11 f I cation 11 st.

It was subsequently I dent If led in the TER

response that qualified differential pressure Indicating switches DPIS-2-1622A,B (refer to FRC Item 62 response) will provide Indication of the valve position by measuring differential pressure across the valves.

Therefore, the valve position sw I tche.s are exempt from qua 11 f I cat I on.

Testing and analysis had not been performed on these position switches at the time of the TER/SER review; therefore, quallflcatlon documentation was noted as being Inadequate by FRC.

Qualification deficiencies for operating time, material aging humidity, temperature, pressure, and radiation were ldentf fled.

A review of the switch function revealed alternative devices for Indicating the positions of their valves.

Therefore, as Indicated In the TER response, these switches should be exempted from quallflcatlon because alternative signals for~

Indication of the valve position during the post-accident pe~

are provided by flow transmitters FT-2-645A,B,C,D.and differential pressure switches OPIS-2-261-2A through -2S, located In a m I Id env I ronment.

FRC stated that the status of the equipment could not be determined from the CECo submittal; therefore, CECo should clearly establish whether the position switches require qualification or that they are not safety-related. Position switches POS-2-2301-64, POS-2-2301-65, POS-2-2301-29, and POS-2-2301-30 provide valve position Indication for valves 2-2301-64, 2-2301-65, 2-2301-29, and 2-2301-30, respectively.

These valves are steam line drain valves on the high-pressure coolant Injection CHPCI) steam line drain pots.

They provide automatic switchover from the main condenser to the suppression chamber upon an llPCI Initiation signal. The valves are designed as redundant pairs In series; therefore, the failure of one to close would not preclude the switchover. The position switches

V.

Specific Equipment EQ Deficiencies {continued)

Description

{Manufacturer, fRC Item Number ~~Mo~d~e~l~*-E~t~c~>~~

T.

Position Switches {continued)

U.

PRESSURE SWITCHES QCI: 21 QC2: 21

oc1: 33

,:QC2: 33 QCI: 36 QC2: 36 02: 59,60 03: 42,48 QCI: None QC2: None 02:

None 03:

None Statlc-0-Ring 12NN-KK215VX Statlc-0-Rlng GNL-3 Statlc-0-Rlng 12N-M5-PP Statlc-0-Rlng 5N-M3 Barksdale B2T-A12SS Barksdale B2T-12SS-GE

v.

PRESSURE TRANSMITTERS QCI: None Balley, B&W QC2: None KG556220BMIWFE 02:

None 03:

None NRC Category Deficiencies l.B Documented evidence of qualification Is Inadequate II.A Documented evidence of qual lflcatlon Is Inadequate II.A Documented evidence of qualification Is Inadequate l.B Documented evidence of qualification Is Inadequate NA None NA None 16 Proposed Resolution have no part In the control function or circuitry of the Isolation valves.

The switches only provide supplemental Indication and operator action ls not.required. Therefore; the position switches provide no safety-related function and have been deleted from the environmental qualification program.

In addition, this deletion Is further justified because both the subject solenoid valves and associated position switches are

I ocated In a ml Id env I ronment.

These components were scheduled for replacement; however, no qualified replacement was Identified at the time of the TER/SER review.

Therefore, documented evidence of qualification was....

Indicated as Inadequate.

They will be replaced by qualified~

Rosemount Hodel I 153, Serles B transmitters. The harsh environment parameters this equipment will encounter are temperature, pressure, and humidity during post-OBA operation.

Radiation Is considered mild at <1.0E04 rads.

Rosemount Test Report 108025, Rev B, dated February 1983, which provides the quallflcatlon data for these transmitters, Indicates that the*

transmitters are qualified for the required environmental conditions. The qualified life of the Hodel 1153; Serles B transmitters has been determined by Rosemount to be 20 years; therefore, these components will require replacement at the end of this period.

Not applicable because these components are not subjected to harsh environmental conditions; therefore, they are deleted from the qualification program.

Not applicable because these c0mponents are not subjected to harsh environmental conditions; therefore, they are deleted from the qualification program.

Not applicable because these components are not subjected to.

harsh environmental conditions; therefore, they are deleted fr,

the qualification program.

Wiii be replaced with Rosemount Hodel 1153; qualified by Test Report 108025, Rev B, February 1983.

At the time of the TER/SER review, no deficiency was Identified for these Balley pressure transmitters. However, these trans-mitters are required to be qualified for post-accident radiation only.

Wyle has conducted testing on these transmitters and provided qualification documentation In Test Report 45917-60, September 1983.

The report has been reviewed and evaluated, and It has been determined that these transmitters are qualified for the required accident radiation dose.

v.

FRC

v.

OCI:

QC2:

02:

03:

QCI:

OC2:

02:

03:

'02:

l.>2:

S~ecific Egui~nt E~ Deficiencies Description (Manufacturer, Item Number Model 1 Etc>

Pressure Transmitters (cont I nued)

None None None None 9,30 9,30

74.

40 75 76 Rosemount 1152GP7A22PB GE/MAC 551 GE/MAC 551 GE/MAC 551.

l494c (continued)

NRC Categor~

NA I.B II.A 111.A Deficiencies None Documented evidence of qualification Inadequate Documented evidence of qualification Inadequate Equipment exempt from qualification

. 17 Proposed Resolution At the time of TER/SER review, no deficiency was Identified for these Rosemount Model 1152 transmitters. However, these trans-mitters are required to be qualified for radiation only.

Rosemount has conducted testing on these transml"tters and provided qualification documentation In Report 117415, dated September 1975.

based on review and evaluation of this report, It has been determined that these transmitters are qualified for the normal and required accident environments.

At the time of TER/SER revlewf these components were scheduled for either testing or analysis.

he decision was made to test the component for radiation because radiation caused by a design ***S accident Is the only harsh environment to which these compone are ever subjected.

Subsequently, the GE/MAC Model 551 and 55 transmitters were tested by Wyle laboratories. Quallflcatlon was provided In Wyle Test Report 45917-1, July 30, 1982.

Review and evaluation of the test report revealed that these components are acceptably qualified for the required conditions.

At the time of TER/SER review, these components were scheduled for either testing or analysis.

The decision was made to. test the component for radiation because radiation caused by a design basis accident Is the only harsh environment to which these components are ever subjected.

Subsequently, the GE/MAC Model 551 and 553 transmitters were tested by Wyle laboratories.

Qualification was provided In Wyle Test Report 45917-1, July 30, 1982.

Review and evaluation of the test report revealed that these components are acceptably qualified for the required conditions.

At the time of TER/SER review, these components were scheduled for either testing or analysis.

The decision was made to test the component for radiation because radiation caused by a desl' basis accident Is the only harsh environment to which these components are ever subjected.

Subsequently, the GE/MAC Model 551 and 553 transmitters were tested by Wyle laboratories.

Qualification was provided In Wyle Test Report 45917~1, July 30, 1982.

Review and evaluation of the test report revealed that these components are acceptably qualified for the required conditions.

V.

Specific :[quipmc~t EQ Deficiencies (continued)

Description (Manufacturer, FRC Item Number __

Mo_d-'e_l_,_,--'-Et_c-') __

W.

RADIATION DETECTOR QCI:

QC2:

D2:

D3:

None None None None General.Atomic RD-23 NRC Category _______

De_f_lc_le~n-'c_l_e_s _____ ~

NA None X.

ELECTRIC MOTORS CROOM COOLER FAN MOTORS)

QCI: 37

.QC2: 37 QCI: 38 QC2: 38

J494c General Electric Model 5K213AK2476 General Electric Hodel 5Kl84AL2151 l.B Documented evidence of quallflcatlon Inadequate l.B Documented evidence of qualification Inadequate 18 Proposed Resolution This component was not part of the Initial response to the IE Bulletin of November 1980.

It was subsequently added as a Three Mlle Island CTMI) modification.

General Atomlc's high-range radi-ation monitor detector assembly RD-23 was tested several times under simulated loss-of-coolant accident conditions before a complete set of data could be obtained.

The cause of concern was the techn I que used to protect the HN cab I e connect I on betw_een the detector and the Rockbestos coaxial cable.

Finally, the use of a Raychem Type WCSF heat-shrink tubing to cover the entire connector proved successful. After evaluation of General Atomlc's Test Report E-254-960, dated May 1981, the entire high-range radiation monltor.(of which the RD-23 radiation ~

detector Is a part) Is qualified for use In a variety of Installations. However, for a qualified life of 40 years~ normal equipment maintenance must be performed as outlined In operations and maintenance manuals, and the aluminum electrolytic capacitors must be replaced every 10 years.

These components were scheduled for replacement; however, no qualified replacement was Identified at the time of the TER/SER review.

Therefore, documented evidence of quallflcatlon was Indicated as Inadequate.

They will be replaced by qualified Westinghouse motors.

The components are required to be qualified for post-accident radiation only. Westinghouse has provided the radiation qualified for the replacement motors In Test Report MM9112, dated January 1982.

Based on review and evaluation of this report, It has been determined that the Westinghouse motors are adequately qualified for the postulated accident radiation dose.

These components were scheduled for replacement; however, no ~

qualified replacement was Identified at the time of the TER!sflll' review.

Therefore, documented evidence of qualification was Indicated as Inadequate.

They will be replaced by qualified Westinghouse motors.

The components are required to be qualified for post-accident radiation only. Westinghouse has provided the radiation qualified for the replacement motors In Test Report MM9112, dated January 1982.

Based on review and evaluation of th Is. report, It has been de term I ned that the Westinghouse motors are adequately qualified for the postulated accident radiation dose.

V.

Specific'EguiixOOnt EQ Deficiencies (continued)

Description (Manufacturer, FRC I tern Number __

M_o_d_e_i.._,_E"""t_c-') __

NRC Category Deficiencies X.

Electric Motors (Room Cooler Fan Motors) (continued)

D2:

86 D3:

58 General Electric Model 5Kl84AL2561 Y.

SOLENOID VALVES

.:QCI:

.QC2:

D2:

D3:

16 16 44,45 31 QCI: 17 QC2: 17 D2:

47 D3:

33 bc:f

18

~2: 18

,)2:

48

n

34 t494c AVCo C5512 Gould, 320X39/320X30 AVCo/Target Rock C5450-5 Dresser 1525VX l.B Documented evidence of qualification inadequate l.B 11.C 11.C Documented evidence of qualification inadequate Aging degradation not Identified, quali-fied life and replacement schedule not es tab I I shed Aging degradation not Identified, quali-fied life and replacement schedule not establ I shed 19 Proposed Resolution These components were scheduled for replacement; however, no qualified replacement was Identified at the time of the TER/SER review.

Therefore, documented evidence of quallflcatlon was indicated as Inadequate.

They will be replaced by qualified Westinghouse motors.

The components are required to be qualified for post-accident radiation only. Westinghouse has provided the radiation qualified for the replacement motors In Test Report.

MM9112, dated January 1982.

Based on review and evaluation of*

this report, It has been determined that the Westinghouse motors are adequately qualified for the postulated accident radiation dose.

The November 1980 submittal Identified these components as requiring quallflcatlon by testing or replacement at Quad Cities and by replacement at Dresden.

No Information on replacement quallflcatlon was available at that time; therefore, FRC determined that documented evidence of quallflcatlon was inadequate.

Subsequently, CECo Joined a generic test program for these valves sponsored by TVA.

The TVA test program was Initiated at Wyle Laboratories to envelop all harsh environmental conditions at Dresden and Quad Cities. The ongoing test program has currently established a 5-year quallflcatlon for these solenoid valves.

In addition, an analysis will be performed to take credit for the tests being conducted to environmental conditions beyond those required at Dresden and Quad Cities and to establish a reasonable estimate of the qualified life and appropriate maintenance and replacement requirements.

At the time of the TER/SER review, these components were Identi-fied as Dresser Industries valve Model C5450-5.

FRC notes th~

only age degradation was not Identified. Subsequently, these'lllllllll-ponents were Identified as Automatic Valve Corporation CAVCo)

Model C5450-5 operators on Target Rock relief valves.

As a result, these operators are required to be qualified to harsh environmental conditions due to temperature, humidity, pressure, radiation, and demlnerallzed water spray.

Thermal aging Is also required to be addressed.

General Electric Plant Design Engineering Memorandum 126-62, dated January 15, 1975, establ I shes qualification for these AVCo/Target Rock solenoid valves to the Dresden and Quad Cities harsh environmental conditions.

In addition, this report has been supplemented by a Bechtel analysis performed to establish a reasonable estimate of the designated life.

During the TER/SER review, FRC Indicated that aging degradation for these Dresser solenoid valves was evaluated Inadequately and that qualified life and replacement schedule were not established.

Later, it was also determined that these components would be exposed to higher levels of radiation and temperature than the original values stated In the November 1980 report. Therefore,

V; Specific Equipmont EQ Deficiencies (continued)

Description (Manufacturer, rRC I tern Number __

M""""o'""'d'--e_l..._

1 --"'-Et'-c;:;..:) __

Y.

Solenoid Valves (continued)

QCI: 47

,QC2: 47 D2:

46 D3:

32

'QCI: 66 QCI: None QC2: 49 D2:

49 D3:

35 01\\91\\c; Versa VPS2502/VGS4522/

VGS4422 Versa VWS2302 ASCo NP-I 206380-3RVF ASCo 206380-3F NRC Category ---------"De..;;...;..f~lc;:_;_;le~n~c~l~e~s-----~

l.B Documented evidence of qualification Inadequate l.B Documented evidence of qualification Inadequate 11.C Aging degradation riot Identified, quali-fied life and replacement schedule not es tab 11 shed 20 Proposed Resolution these components are required to be qualified for temperature, radiation, and aging.

Northeast Utilities Miilstone I Project Engineering Program 42963,Section I, demonstrates partial qualification for these valves.

This report Is being supplemented by a Westec analysis to establish complete environmental qualification and proper maintenance and replacement requirements.

Westec has Identified all subcomponent materials and confirmed that a high-temperature Insulation* system was employed In these valves.

This Insulation system was also satisfactorily submergence-tested.

The analysis Is scheduled for completion In February 1984.

At the time of TER/SER review, evidence of qualification was~

adequately established for these Versa solenoids valves because qualified replacements were not Identified.

The Versa valves will be replaced by ASCo solenoid valve Models NP8344A75V and NP8344A73V at Dresden and Quad Cities, respectively.

Based on the evaluation of ASCo Test Report AQR-67368, Rev O, these ASCo valves are qualified to the required environmental conditions at Dresden and Quad Cities.

FRC Item 32 of the TER response for*

Dresden Unit 3 Indicated qualification requirements of 262F temperature and 21.0 psla pressure. However, these torus vacuum relief valves are required to operate only during a LOCA temperature of 135F and pressure of 14.7 psla; therefore, qualification Is required only for these lower values.

TER/SER review Identified that the qualification documentation was Inadequate because a qualified replacement was not Identified for this Versa solenoid valve. After reevaluating the qualification requirements, It was determined that the SGTS butterfly valve Is of the fall-open type and Is normally open during system operation.

It ls not required to change position following an accident.

Failure of this valve will not affect system safety functions; therefore, the component ls exempt from quallficat~

An aging analysis had not been performed on this component at the time of the TER/SER review; therefore, aging degradation was not Identified as a qualification parameter.

The qualified life and replacement schedule were not established. Aging and qualified life were addressed generically In Attachment 5 to the TER/SER response.

Bechtel has performed an analysts (Bechtel Calculation NUC-32, Rev O, dated July 20, 1983) to determine the qualified life of the solenoid valve subcomponents on the basis of ASCo Test Reports AQS-21678/TR, Rev A, and AQR-67368, Rev O.

Subcomponent replacement schedules have been established and are being Incorporated In the plant maintenance and survel I lance program.

The qualified life for the subcomponents Is as follows:

EPDM seals, 9 years; vlton A static seal, 37 years; and solenoid col I, 30 years.

y__. _Speci fie Equipment* EQ Deficiencies (continued)

FRC Item Number Description CManu facturer, Model, Etc)

Y.

Solenoid Valves (continued)

D2:

41 D2:

43 Z.

SWITCHGEAR D2:

82

.03:

61 QCI: NA QC2: NA (no switchgear in harsh envi-ronment)

ASCo LB831454 ASCo WPH8300B61F General Electric MC-AMH-4176-250 NRC Category ~~~~~~--=De-"--'-f~lc.::.;..;le~n~c~l~e~s~~~~~~

II.A Documented evidence of qualification Inadequate 111.B None l.B Qualification not fully established, additional testing/analysis required for radiation and aging and qualified life ll Proposed Resolution Testing and analysis had not been performed on this component at the time of the TER/SER review; therefore, qualification documentation was noted as being Inadequate by FRC.

Qualification deficiencies for operating time, material aging, humidity, temperature, pressure, and radiation are being resolved by replacement.

Bechtel performed an evaluation of the ASCo Test Report AQR-67368, Rev O, and verified that the test report will qualify these ASCo Type NP-I solenoid valves (Catalog 8314C62 for Dresden and Quad Cities). Qualified life will be supplemented by a Bechtel analysis using test data.

The qualified ASCo Type NP-I solenoid valves are being procured to replace the nonquallfled valves during the station outage scheduled to end In December~

1984.

In the TER/SER review, FRC concurred that this solenoid valve Is not In the scope of qualification review because this Is located In a mlld environment.

This Item was not, therefore, addressed In the TER response.

Subsequently, It was determined that the solenoid valve Is located In a harsh environment where quallflcatlon ls required for temperature, pressure, humidity, and radiation. This equipment will be replaced with an ASCo solenoid valve that Is qualified according to ASCo Test Report AQR67368, Rev 0.

At the time of TER/SER review, testing and analyses were not com-plete and could not fully establish the quallflcatlon of the switchgear components.

The only environmental parameter requiring quallflcatlon was radiation caused by post-accident recirculating fluids.

The qualification of the switchgear components has been fully established by the following.

1 *. Bechtel engineering analysis for all nonmetallic component~

fastened to the metal switchgear cabinet assemblies; the...,

analyses demonstrated that the post-LOCA dose was below the threshold of all of these materials.

2. The remainder of the switchgear subcomponents were qµallfled by testing actual Dresden switchgear components In a plant-specific test program.

These components passed functional tests before and after radiation exposure as stated In Wyle Test Report 45917-2, dated September 2, 1983.

V.

Specific Equipment EQ Deficiencies (continued)

FRC Item Number Description (Manufacturer, Model, Etc)

AA.

TEMPERATURE ELEMENTS QCI: I QC2: I 02:. 53 03:

36.

Minco (for Panalann)

S51-l-103 BB.

TEMPERATURE SWITCHES QCI:

QC2:

02:

03:

15 15 50,51 43,44

- QCI: 20,48 QC2: 20,48

~,Jii94c UEC Type F7, Model BBB UEC Type F7, Model 76 Fenwal Model 17002-40 NRC Category ~~~~~~-'=De""""""f~ic=-.;....;le~n~c~l~e~s~~~~~~

l.B II.A II.A Documented evidence of qualification Inadequate Documented evidence of quallficatlon Inadequate II.A Documented evidence of qualification Inadequate

.A Proposed Resolution The identified deficiency was temperature and was originally to b(

resolved by material analysis.

A literature search revealed that all teflon components of the Minco temperature element were lnade~

quate for the required environment.

Therefore, the existing resistance temperature detectors, TE-129i-60A through H, will be replaced with environmentally qualified temperature detectors manufactured by Conax Corporation. These Conax temperature detectors will provide an environmentally qualified system, which will have redundant sensing trains to detect steam leaks.

Conax Test Report IPS-875 was evaluated, and the replacement compq15ts are fully qualified for the required environment.

The TER/SER evaluations concluded that the qualification documen-tation was Inadequate for these components because CECo's periodic calibration did not provide evidence of qualification In accor-dance with the DOR guidelines.

These temperature switches are required to be qualified to harsh environmental.conditions of temperature, humidity, pressure, and radiation. Thermal and radiation aging effects must also be established.

Therefore, It was detennlned that the quallflcatlon would be established by either analysis or replacement.

Subsequently, It was decided to replace the mlcroswltch to establish material traceability and to qualify the components by analysis.

An analysis is being perfonned using MCC Powers Test Report 734-79-002, Rev I; Farr Company Test Report L-71003, Rev A; and the manufacturers' technical literature.

The TER/SER evaluation concluded that the qualification documenta-tion was Inadequate for these components because CECo's peri.

calibration did not provide evidence of qualification in accordance with the DOR guidel Ines.

These temperature swltche are required to be qualified to harsh environmental conditions of temperature, humidity, pressure, and radiation.

Thermal and radiation aging effects must also be establ I shed *. These switches have a very short operating time, and the accident radiation dose is correspondingly small.

They are very simple devices with the most sensitive material (teflon) located only on the lead wires.

Therefore, qualification ls being established by material analysis based on the manufacturer's technical literature; GE Report ND024217; GE Report OV145C3004; Wyle Report 43854-1 of TVA; and Bechtel Chron 7089, dated March II, 1983.

~*

s'j?ir~*itic EguipOlent EQ beticienci~*s (continued)

rnc I tern Number Description (Manufacturer, Model, Etc)

~* Temperature Switches (continued)

~I: 64

02:

52

'!03:

53 11QCI: "67 Chromalox blmetal thermoswitch; manufac-turer unknown Pal I Trinity micro-switch 14-T-2H

,ICC.

TERMINAL BLOCKS tQCI: 57

02:. 100 1!02:

IOI ID3:

74 1!D3:

75 Al I en-Bradley Al I en-Bradley General Electric General Electric Al I en-Bradley lJD.

OILS AND GREASES

~one Mobi I 28 NRC Category ~~~~~~--"De-'-'-f~lc~l~e~n~c~l~e~s~~~~~~

l.B Documented evidence of qualification Inadequate l.B Documented evidence of qualification Inadequate l.B Documented evidence of qualification Inadequate None None

~one Mobi I DTE medium heavy None None P494c Proposed Resolution The TER/SER stated that quallflcatlon documentation was Inadequate for the thermoswltch because quallfled replacements were nof Iden-tified.

In the TER response, It was stated that quallflcatlon was

required for harsh temperature, humidity, pressure, and radiation for the components and that qualified replacements would be Installed during or before critical outages at the stations.

Subsequently, the stations removed these switches from the circuitry because they were not required for system operation.

Therefore, the components are exempt from qualification and have been deleted from the IE Bulletin 79-0IB scope because they are no longer required to function as Class IE components.

The SER/TER stated that qua 11 f I cat I on document at I on was I nadeqle for the thermocoup I e because qua 11 f I ed rep I acements were not Identified. Qualification Is not required for these component because an environmentally qualified suppression pool temperature monitoring CSPTM) system Is Installed as a Class IE system to monitor water temperature, thereby providing the same function as the subject thermocouples.

Therefore, these thermocouples are exempted from qualification.

These components were scheduled for replacement; however, no quallfled replacement was Identified at the time of the TER/SER review.

Therefore, documented evidence of quallflcatlon was indi-cated as Inadequate.

They will be-replaced by Marathon Serles 1500 terminal blocks.

The equipment ls required to be qualified for harsh environment due to temperature, pressure, humidity, radiation, and demlnerallzed water spray during post-OBA operation.

In addition, thermal aging at 150F Is required for the remaining 30 years.

The Marathon Serles 1500 terminal blocks were tested by Wyle Laboratories and qualified by Wyle Test Report TIE-45603-1, February 18, 1982.

Based on review and

~

evaluation of this report, It has been determined that the

~

equipment has a qualified life of 40 years and ls adequately qualified for the postulated accident environment.

Quall fled by Mobil Technical Bui letln, May 1974; used in Llmitorques.

Qualified by Mobil Technical Bulletin~ May 1974; used In General Electric LPCI, core spray, RHR, and shutdown cooling pump motors.

DISTRIBUTION Docket File NRC PDR Local PDR NSIC ORB #5 Reading ORR #2 Reading DCrutchfield DVassa 11 o HSmith RGilbert RBevan OELD ELJordan JMTayl or ACRS (10)

FMiraglia GLainas NRC Participants cc list

ML17195A103

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