ML20076E179

Provides Resolution of Equipment Qualification Open Items Cited in Safety Evaluation & Franklin Research Ctr Technical Evaluation Rept.Remaining Deficiencies Will Be Resolved by 851130.Response Encl

ML20076E179
Person / Time
Site:	Prairie Island
Issue date:	08/10/1983
From:	Musolf D NORTHERN STATES POWER CO.
To:	Office of Nuclear Reactor Regulation
References
NUDOCS 8308240200
Download: ML20076E179 (173)

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Northem States Power Company 414 Niconet Mall Minneaooks Minnesota 55401 Telepnone (612) 330 5500 August 10, 1983 Director Office of Nuclear Reactor Regulation U S "uclear Regulatory Commission Washington, DC 20555 PRAIRIE ISLAND MUCLEAR GENERATING PLAMT Docket Mos. 50-282 License Nos. DPR-42 50-306 DPR-60 bafety Evaluation for Environmental Qualification of Safety-Related Electrical Eauipment; Additional Information The purpose of this report is to provide resolution of equipment qualifi-cation open items cited in the Safety Evaluation and Technical Evaluation Report on Environmental Qualification of Electrical Equipment (TER) prepared by the Franklin Research Center. This report was received on April 25, 1983, allowing insufficient time for inclusion of this informa-tion in our 'by 19, 1983 report required by 10 CFR Part 50, Section 50.49.

Resolution of the equipment qualification open items identified in the TER has been established via one or more of the following methods:

1.

Equipment modification or replacement -- In sone cases, unqualified equipment was replaced or modifications were performed to establish qualification.

Qualified equipment was used for equipment replace-ment.

2.

Additional clarification of qualification provided -- In many cases, equipment qualification open items were the result of lack of clarity in the qualification document. The open items were resolved by providing a more detailed description of the test and/or analyses on which the qualification was based.

3.

Additional equipment qualification analyses performed -- Equipment qualification open items for some equipment items required that additional analyses be performed. These analyses are documented in calculation files and are being incorporated into the Prairie Island Equipment Qualification Central File.

The specific details of resolution for each equipment item is contained in the attached TER Response.

8308240200 830810 DRADOCKOS000g

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NORTHERN CTATED POWER COMPANY Director of NRR August 10, 1983 Page 2 As of this date, all equipment items on the Prairie Island harsh environ-ment safety-related equipment masterlist are fully qualified with the exception of those items listed below:

1.

Equipment qualification open items noted in our May 19, 1983 response to 10 CFR 50.49.

2.

Limitorque Valve Controllers -- A project has been initiated to re-evaluate the environmental qualification of all safety-related Limitorque valve controllers as a result of the equipment qualification open items cited in the TER.

The project will include contacting the equipment vendor to obtain the applicable qualification documents and then evaluating the environmental qualification. All open items cited in the TER will be addressed.

This qualification evaluation is expected to be completed by January 1, 1984.

3.

Westinghouse Safety Injection and Residual Heat Removal Motors --

A project has been initiated to re-evaluate the environmental qualification of these motors as a result of the equipment qualification open items cited in the TER.

The project will include contacting the equipment vendor to obtain the applicable qualification documents and then evaluating the environmental qualification. All open items cited in the TER will be addressed.

This qualification evaluation is expected to be completed by January 1, 1984.

4.

Rosemount 1153 Series A Transmitters -- These transmitters were included in Category II.b in the TER, equipment not qualified. A technical response for this equipment item was transmitted to the NRC on May 5, 1983. By NRC letter dated June 3,1983 from R A Clark to D M Musolf (NSP) this equipment item was reclassified into Category II.C.

As a result, a project has been initiated to re-evaluate the aging qualification of Rosemount Series A transmitters.

This evaluatien is expected to be completed by January 1,1984.

As stated in our !by 19, 1983 letter all remaining deficiencies will be resolved by November 30, 1985.

Please contact us if you have any questions related to the information we have provided.

bs David Musolf Manager - Nuclear Support Se ices DT!/ dab cc: Regional Administrator-III Resident Inspector, NRC NRR Project Manager, NRC G Charnoff 1

Attachment

. e NORTHERN STATES POWER COMPANY TER Response PRAIRIE ISLAND NUCLEAR GENERATING PLANT July 29, 1983 ENCLOSURE ONE Response to Franklin Research Center Technical Evaluation Report dated March 29, 1983 -

" Review of Licensees' Resolution of Outstanding Issues From NRC Equipment Environmental Qualification Safety Evaluation Reports" Northern States Power Company Prairie Island Nuclear Generating Plant Units 1 and 2 l

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. o e e NORTHERN STATES POWER COMPANY TER Response PRAIRIE ISLAND NUCLEAR GENERATING PLANT July 29, 1983 TABLE OF CONTENTS Page

1.0 INTRODUCTION

1-1 2.0 RESOLUTION OF DEFICIENCIES IDENTIFIED IN THE TECHNICAL EVALUATION REPORT 2-1 2.1 Resolution for Unit 1 2.1-1 2.2 Resolution for Unit 2 2.2-1 3.0 GENERAL REFERENCES 3-1 l

NORTHERN STATES POWER C0@ANY TER Response PRAIRIE ISLAND NUCLEAR GENERATING PLANT July 29, 1983 Page 1-1

1.0 INTRODUCTION

This document addresses each of the environmental qualification deficien-cies identified by the Franklin Research Center (FRC) in their Technical Evaluation Report (TER) [1] for the Prairie Island Nuclear Generating Plant. The intent of this document is to finalize equipment qualification documentation for most equipment items and provide plans for the finaliza-tion of all equipment items not presently qualified.

Since documentation of the environmental qualification of safety-related electrical equipment was initiated in 1980, there have been several submittals to the Nuclear Regulatory Connission (NRC) describing the qualification status of safety-related electrical equipment at Prairie Island. The initial equipment environmental qualification submittal was made on March 13, 1980 [2), and was updated on October 31, 1980 [3], and January 22, 1981 [4]. The NRC issued a Safety Evaluation Report (SER) to Northern States Power for the equipment qualification submittals on May 12, 1981 [5]. A response to the NRC SER was submitted by NSP on August 26,1981,[6] and was updated on April 30, 1982 [7]. On May 19, 1983, a response to the Equipment Qualification Rule, 10CFR50.49, Environmental l

Qualification of Electrical Equipment Important to Safety for Nuclear Power Plants [8] was submitted to the NRC by NSP.

The resolution of deficiencies identified in the TER will be addressed on an item-by-item basis following the numbering scheme presented in the TER for each unit.

In many cases, the equipment identification numbers listed by the FRC for each unit are incorrect. These will be corrected in this document. Resolution of deficiencies is accomplished by clarifying the qualification efforts previously performed; by summarizing qualification i

efforts performed since the FRC review was initiated and, thus, not reviewed by the FRC; or by identification of qualified replacement equipment.

In cases where complete resolution of all deficiencies identified in the TER has not been accomplished as of the issuance of this document, a plan for the resolution of these items is presented.

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NORTHERN STATES POWER COMPANY TER Response PRAIRIE ISLAND NUCLEAR GENERATING PLANT July 29, 1983 Page 2-1 2.0 RESOLUTION OF DEFICIENCIES IDENTIFIED IN THE TECHNICAL EVALUATION REPORT Each of the deficiencies identified in the TER will be discussed and resolved in this section. In cases where resolution has not already taken place, a plan for resolution will be presented. This section is organized by Equipment Item number as identified in the TER, and will be differenti-ated by Prairie Island unit number.

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NORTHERN STATES POWER COMPANY TER Response PRAIRIE ISLAND NUCLEAR GENERATING PLANT July 29, 1983 Page 2.1-1 UNIT NUMBER:

1 TER EQUIPMENT ITEM NUMBER:

1 EQUIPMENT DESCRIPTION: Limitorque Motorized Valve Actuator Model SMB-00 EQUIPMENT LOCATION: Reactor Building Unit 1 TER QUALIFICATION CATEGORY:

II.A TER-IDENTIFIED PLANT ID NUMBERS:

MV-32199, MV-32210 CORRECT PLANT ID NUMBERS FOR THIS UNIT: MV-32199 Note:

Valve actuator MV-32210 is used in Unit 2 functions and is included in Equipment Item 1 for Unit 2.

ITEMIZED DEFICIENCIES AND RESPONSES:

1.

Equipment qualification not established.

A.

Adequate similarity between equipment and test specimen not established.

B.

Aging degradation not evaluated adequately.

C.

Qualified life or replacement schedule not established.

Several pages of detailed notes were provided in the TER pertaining to deficiencies in the environmental qualification of this equipment item.

RESPONSE

A project has been initiated to thoroughly evaluate and document the environ-mental qualification of Limitorque valve actuators. Each of the concerns raised in the TER will be addressed in that evaluation. We expect that the evaluation will be finalized by January 1, 1984, and that any necessary modifications or replacements will be performed prior to November 30, 1985.

1 NORTHERN STATES POWER COMPANY TER Response PRAIRIE ISLAND NUCLEAR GENERATING PLANT July 29, 1983 Page 2.1-2 UNIT NUMBER:

1 TER EQUIPMENT ITEM NUMBER:

2 EQUIPMENT DESCRIPTION:

Limitorque Motorized Valve Actuator Model SMB-1 EQUIPMENT LOCATION: Reactor Building Unit 1 TER QUALIFICATION CATEGORY:

III.A TER-IDENTIFIED PLANT ID NUMBERS:

MV-32071, MV-32072 CORRECT PLANT ID NUMBERS FOR THIS UNIT: MV-32071, MV-32072 ITEMIZED DEFICIENCIES AND RESPONSES:

These valve actuators are in a locked-open position with power removed and cannot, therefore, change position. This equipment item is exempt from quali-fication and has been removed from the safety-related equipment masterlist.

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NORTHERN STATES POWER COPPANY TER Response PRAIRIE ISLAND NUCLEAR GENERATING PLANT July 29, 1983 Page 2.1-3 UNIT NUMBER:

1 TER EQUIPMENT ITEM NUMBER:

3 EQUIPMENT DESCRIPTION:

Limitorque Motorized Valve Actuator Models SMB-00 and SMB-000 EQUIPMENT LOCATION:

Reactor Building Unit 1 TER QUALIFICATION CATEGORY:

II.A TER-IDENTIFIED PLANT ID NUMBERS:

MV-32132, MV-32135, MV-32138, MV-32141, MV-32043, MV-320*0, MV-32046, MV-32049 CORRECT PLANT.ID NUMBERS FOR THIS UNIT: MV-32132, MV-32135, MV-32138, MV-32141, MV-32043, MV-32040 Note:

Valve actuators MV-32046 and MV-32049 are used in Unit 2 functions and are included in Equipment Item 3 for Unit 2.

ITEMIZED DEFICIENCIES AND RESPONSES:

1.

Equipment qualification not established.

A.

Adequate similarity between equipment and test specimen not established.

B.

Aging degradation not evaluated adequately.

C.

Qualified life or replacement schedule not established.

I Several pages of detailed notes were provided in the TER pertaining to deficiencies in the environmental qualification of this equipment item.

RESPONSE

A project has been initiated to thoroughly evaluate and document the environ-mental qualification of Limitorque valve actuators. Each of the concerns raised in the TER will be addressed in that evaluation. We expect that the evaluation will be finalized by January 1, 1984, and that any necessary modifications or replacements will be performed prior to November 30, 1985.

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NORTHERN STATES POWER COMPANY TER Response PRAIRIE ISLAND NUCLEAR GENERATING PLANT July 29, 1983 Page 2.1-4 UNIT NUMBER:

1 TER EQUIPMENT ITEM NUMBER: 4 EQUIPMENT DESCRIPTION:

Limitorque Motorized Valve Actuator Model SMB-1 EQUIPMENT LOCATION: Reactor Building Unit 1 TER QUALIFICATION CATEGORY:

II.A TER-IDENTIFIED PLANT ID NUMBERS:

MV-32167, MV-32168, MV-32064, MV-32065 CORRECT PLANT ID NUMBERS FOR THIS UNIT:

MV-32064, MV-32065 Note:

Valve actuators MV-32167 and MV-32168 are used in Unit 2 functions and are included in Equipment Item 4 for Unit 2.

ITEMIZED DEFICIENCIES AND RESPONSES:

1.

Equipment qualification not established.

A.

Adequate similarity between equipment and test specimen not established.

B.

Aging degradation not evaluated adequately.

C.

Qualified life or replacement schedule not established.

Several pages of detailed notes were provided in the TER pertaining to deficiencies in the environmental qualification of this equipment item.

RESPONSE

A project has been initiated to thoroughly evaluate and document the environ-mental qualification of Limitorque valve actuators. Each of the concerns raised in the TER will be addressed in that evaluation. We expect that the evaluation will be finalized by January 1, 1984, and that any necessary modifications or replacements will be performed prior to November 30, 1985.

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NORTHERN STATES POWER COMPANY TER Response PRAIRIE ISLAND NUCLEAR GENERATING PLAN 1 July 29, 1983 Page 2.1-5 UNIT NUMBER:

1 TER EQUIPMENT ITEM NUMBER: 5 EQUIPMENT DESCRIPTION: Limitorque Motorized Valve Actuator Model SMB-00 EQUIPMENT LOCATION: Reactor Building Unit i TER QUALIFICATION CATEGORY:

II.A TER-IDENTIFIED PLANT ID NUMBERS:

MV-32170, MV-32067 CORRECT PLANT ID NUMBERS FOR THIS UNIT:

MV-32067 Note:

Valve actuator MV-32170 is used in Unit 2 functions and is included in Equipment Item 5 for Unit 2.

ITEMIZED DEFICIENCIES AND RESPONSES:

1.

Equipment qualificction not established.

A.

Adequate similarity between equipment and test specimen not established.

B.

Aging degradation not evaluated adequately.

C.

Qualified life or replacement schedule not established.

Several pages of detailed notes were provided in the TER pertaining to deficiencies in the environmental qualification of this equipment item.

RESPONSE

A project has been initiated to thoroughly evaluate and document the environ-mental qualification of Limitorque valve actuators. Each of the concerns raised in the TER will be addressed in that evaluation. We expect that the evaluation will be finalized by January 1,1984, and that any necessary modifications or replacements will be performed prior to November 30, 1985.

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NORTHERN STATES PCWER COMPANY TER Response PRAIRIE ISLAND NUCLEAR GENERATING PLANT July 29, 1983 Page 2.1-6 UNIT NUMBER:

1 TER EQUIPMENT ITEM NUMBER:

6 EQUIPMENT DESCRIPTION:

Limitorque Motorized Valve Actuator Models SMB-00 and SMB-000 EQUIPMENT LOCATION: Reactor Building Unit 1 TER QUALIFICATION CATEGORY:

II.A TER-IDENTIFIED PLANT ID NUMBERS:

MV-32069, MV-32271, MV-32273, MV-32290, MV-32292 CORRECT PLANT ID NUMBERS FOR THIS UNIT:

MV-32069, MV-32271, MV-32273 Note:

Valve actuators MV-32290 and MV-32292 are used in Unit 2 functions and are included in Equipment Item 6 for Unit 2.

ITEMIZED DEFICIENCIES AND RESPONSES:

1.

Equipment qualification not established.

A.

Adequate similarity between equipment and test specimen not established.

B.

Aging degradation not evaluated adequately.

C.

Qualified life or replacement schedule not established.

Several pages of detailed notes were provided in the TER pertaining to deficiencies in the environmental qualification of this equipment item.

RESPONSE

A project has been initiated to thoroughly evaluate and document the environ-mental qualification of Limitorque valve actuators. Each of the concerns raised in the TER will be addressed in that evaluation. We expect that the evaluation will be finalized by January 1, 1984, and that any necessary modifications or replacements will be performed prior to November 30, 1985.

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NORTHERN STATES POWER COMPANY.

TER Response PRAIRIE ISLAND NUCLEAR GENERATING PLANT July 29, 1983 Page 2.1-7 UNIT NUMBER:

1 TER EQUIPMENT ITEM NUMBER:

7 EQUIPMENT DESCRIPTION:

Limitorque Motorized Valve Actuator Models SMB-00 EQUIPMENT LOCATION: Reactor Building Unit 1 TER QUALIFICATION CATEGORY:

II.A TER-IDENTIFIED PLANT ID NUMBERS:

MV-32195, MV-32196, MV-32197, MV-32198 CORRECT PLANT 10 hDMBERS_FOR THIS UNIT:

MV-32195, MV-32196 Note:

Valve actuators MV-32197 and MV-32198 are used in Unit 2 functions and are included in Equipment Item 7 for Unit 2.

ITEMIZED DEFICIENCIES AND RESPONSES:

1.

Equipment qualification not established.

A.

Adequate similarity between equipment and test specimen ~not established.

B.

Aging degradation not evaluated adequately.

C.

Qualified life or replacement schedule not established.

Several pages of detailed notes were provided in the TER pertaining to deficiencies in the environmental qualification of this equipment item.

RESPONSE

A project has been initiated to thoroughly evaluate and document the environ-mental qualification of Limitorque valve actuators. Each of the concerns raised in the TER will be addressed in that evaluation. We expect that the evaluation will be finalized by January 1, 1984, and that any necessary modifications or replacements will be performed prior to November 30, 1985.

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NORTHERN STATES P0k'ER C0WANY TER Response PRAIRIE ISLAND NUCLEAR GENERATING PLANT July 29, 1983 Page 2.1-8 UNIT NUMBER:

1 TER EQUIPMENT ITEM NUMBER:

8 EQUIPMENT DESCRIPTION:

Limitorque Motorized Valve Actuator Model SMB-00 EQUIPMENT LOCATION: Reactor Building Unit 1 TER QUALIFICATION CATEGORY:

III.A TER-IDENTIFIED PLANT ID NUMBERS: MV-32171, MV-32173, MV-32070, MV-32068, MV-32172 CORRECT PLANT ID NUMBERS FOR THIS UNIT: MV-32070, MV-32068 Note:

Valve actuators MV-32171, MV-32173, and MV-32172 are used in Unit 2 functions and are included in Equipment Item 8 for Unit 2.

ITEMIZED DEFICIENCIES AND RESPONSES:

These valve actuators are in a locked-open position with power removed and cannot, therefore, change position. This equipinent item is exempt from quali-fication and has been removed from the safety-related equipment masterlist.

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NORTHERN STATES POWER COMPANY TER Response PRAIRIE ISLAND NUCLEAR GENERATING PLANT July 29, 1983 Page 2.1-9 UNIT NUMBER:

1 TER EQUIPMENT ITEM NUMBER:

9 EQUIPMENT DESCRIPTION: Limitorque Motorized Valve Actuators Model SMB-0, SM8-1 EQUIPMENT LOCATION: Reactor Building Unit 1 TER QUALIFICATION CATEGORY:

II.A TER-IDENTIFIED PLANT ID NUMBERS:

MV-32064, MV-32193, MV-32165, MV-32231, MV-32233, MV-32066, MV-32169, MV-32192, MV-32164, MV-32230, MV-32232 CORRECT PLANT ID NUMBERS FOR THIS UNIT:

MV-32064, MV-32165, MV-32231, MV-32066, MV-32164, and MV-32230, Note:

Valve actuators MV-32193, MV-32233, MV-32169, MV-32192, and MV-32232 are used in Unit 2 functions and are included in Equipment Item 9 for Unit 2.

ITEMIZED DEFICIENCIES AND RESPONSES:

1.

Equipment qualification not established.

l A.

Adequate similarity between equipment and test specimen not established.

B.

Aging degradation not evaluated adequately.

C.

Qualified life or replacement schedule not established.

Several pages of detailed notes were provided in the TER pertaining to deficiencies in the environmental qualification of this equipment item.

RESPONSE

All valve actuators in this equipment item with the exception of MV-32064 were included in the NSP cold shutdown response, Response to IE Bulletin 79-01B, Supplement 3, January 22, 1980, and have therefore been removed from the IE Bulletin 79-01B safety-related equipment masterlist.

A project has been initiated to thoroughly evaluate and document the enviren-mental qualification of Limitorque valve actuators.

Valve actuator MV-32064 will be included in this evaluation.

Each of the concerns raised in the TER will be addressed in that evaluation.

We expact that the evaluation will be finalized by January 1, 1984, and that any necessary modifications or replacements will be performed prior to November. 30, 1985.

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NORTHERN STATES POWER COMPANY TER Response PRAIRIE ISLAND NUCLEAR GENERATING PLANT July 29, 1983 Page 2.1-10 i

UNIT NUMBER:

1 TER EQUIPMENT ITEM NUMBER:

10 EQUIPMENT DESCRIPTION: Limitorque Motorized Valve Actuator'Model SMB-00 EQUIPMENT LOCATION: Auxiliary Building TER QUALIFICATION CATEGORY:

III.A TER-IDENTIFIED PLANT ID NUMBERS:

MV-32242, MV-32243, MV-32248, MV-32249 CORRECT PLANT ID NUMBERS FOR THIS UNIT: MV-32242, MV-32243 Note:

Valve actuators MV-32248 and MV-32249 are used in Unit 2 functions and are included in Equipment Item 10 for Unit 2.

ITEMIZED DEFICIENCIES AND RESPONSES:

These valve actuators are in a locked-open position with power reiaoved and cannot, therefore, change position. This equipment item is exempt from quali-fication and has been removed from the safety-related equipment masterlist.

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l NORTHERN STATES POWER COMPANY TER Response PRAIRIE ISLAND NUCLEAR GENERATING PLANT July 29, 1983 Page 2.1-11 UNIT NUMBER:

1 TER EQUIPMENT ITEM NUMBER:

11 EQUIPMENT DESCRIPTION: Limitorque Motorized Valve Actuator Model SHB-3 EQUIPMENT LOCATION: Auxiliary Building TER QUALIFICATION CATEGORY:

II.A TER-IDENTIFIED PLANT ID NUMBERS:

MV-32023, MV-32024, MV-32028, MV-32029 CORRECT PLANT ID NUMBERS FOR THIS UNIT:

MV-32023, MV-32024 Note:

Valve actuators MV-32028 and MV-32029 are used in Unit 2 functions and are included in Equipment Item 11 for Unit 2.

ITEMIZED DEFICIENCIES AND RESPONSES:

1.

Equipment qualification not established.

A.

Adequate similarity between equipment and test specimen not established.

B.

Aging degradation not evaluated adequately.

C.

Qualified life or replacement schedule not established.

Several pages of detailed notes were provided in the TER pertaining to deficiencies in the environmental qualificatica of this equipment item.

RESPONSE

A project has been initiated to thoroughly evaluate and document the environ-mental qualification of Limitorque valve actuators. Each of the concerns raised in the TER will be addressed in that evaluation.

We expect that the evaluation will be finalized by January 1,1984, and that any necessary modifications or replacements will be performed prior to November 30, 1985.

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NORTHERN STATES POWER COMPANY TER Response PRAIRIE ISLAND NUCLEAR GENERATING PLANT July 29, 1983 Page 2.1-12 UNIT NUMBER:

1 TER EQUIPMENT ITEM NUMBER:

12 EQUIPMENT DESCRIPTION:

Limitorque Motorized Valve Actuator Model SMB-00 EQUIPMENT LOCATION: Auxiliary Building TER QUALIFICATION CATEGORY:

II.A TER-IDENTIFIED PLANT ID NUMBERS:

MV-32166, MV-32194 CORRECT PLANT ID NUMBERS FOR THIS UNIT:

MV-32166 Note:

Valve actuator MV-32194 is used in Unit 2 functions and is included in Equipment Item 12 for Unit 2.

ITEMIZED DEFICIENCIES AND RESPONSES:

l.

Equipment qualification not established.

A.

Adequate similarity between equipment and test specimen not established.

B.

Aging degradation not evaluated adequately.

C.

Qualified life or replacement schedule not established.

Several pages of detailed notes were provided in the TER pertaining to deficiencies in the environmental qualification of this equipment item.

RESPONSE

A project has been initiated to thoroughly evaluate and document the environ-mental qualification of Limitorque valve actuators. Each of the concerns raised in the TER will be addressed in that evaluation. We expect that the evaluation will be finalized by January 1, 1984, and that any necessary modifications or replacements will be performed prior to November 30, 1985.

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NORTHERN STATES POWER COW ANY TER Response PRAIRIE ISLAND NUCLEAR GENERATING PLANT July 29, 1983 Page 2.1-13 UNIT NUMBER:

1 TER EQUIPMENT ITEM NUMBER:

13 EQUIPMENT DESCRIPTION:

Limitorque Motorized Valve Actuator Models SMB-0, SMB-00, SMB-1 EQUIPMENT LOCATION: Auxiliary Building TER QUALIFICATION CATEGORY:

II.A TER-IDENTIFIED PLANT ID NUMBERS:

MV-32206, MV-32207, MV-32208, MV-32209, MV-32163, MV-32162, MV-32190, MV-32191, MV-32077, MV-32078, MV-32178, MV-32179, MV-32180, MV-32181, MV-32075, MV-32076, MV-32084, MV-32085, MV-32187, MV-32188, MV-32184, MV-32185, MV-32186, MV-32081, MV-32082, MV-32083, MV-32096, MV-32097, MV-32108, MV-32109, MV-32103, MV-32105, MV-32114, >W-32116 CORRECT PLANT ID NUMBERS FOR THIS UNIT. MV-32206, MV-32207, MV-32163, MV-32162, MV-32077, MV-32078, MV-32075, MV-32076, MV-32084, MV-32085; MV-32184, MV-32185, MV-32186, MV-32096, MV-32097, MV-32103, MV-32105, NN-32114, MV-32116 Note:

Valve actuators MV-32208, MV-32209, MV-32190, MV-32191, MV-32178, MV-32179, MV-32180, MV-32181, MV-32187, MV-32188, MV-32081, MV-32082, MV-32083, MV-32108, MV-32109, MV-32114, and MV-32116 are used in Unit 2 functions and included in Equipment Item 13 for Unit 2.

ITEMIZED DEFICIENCIES AND RESPONSES:

1.

Equipment qualification not established.

A.

Adequate similarity bet. ween equipment and test specimen not established.

B.

Aging degradation not evaluated adequately.

C.. Qualified life or replacement schedule not established.

Several pages of detailed notes were provided in the TER pertaining to deficiencies in the environmental qualification of this equipment item.

~

RESPONSE

A project has been initiated to thoroughly evaluate and document the environ-mental qualification of Limitorque valve actuators. Each of the concerns raised in the TER will be addressed in that evaluation. We expect that the evaluation will be finalized by January 1,1984, and that any necessary modifications or replacements will be performed prior to November 30, 1985.

l NORTHERN STATES POWER COMPANY TER Response PRAIRIE ISLAND NUCLEAR GENERATING PLANT July 29, 1983 Page 2.1-14 UNIT NUMBER:

1 TER EQUIPMENT ITEM NUMBER:

14 EQUIPMENT DESCRIPTION:

Limitorque Motorized Valve Actuator Models SMB-000 EQUIPMENT LOCATION: Auxiliary Building TER QUALIFICATION CATEGORY:

II.A TER-IDENTIFIED PLANT ID NUMBERS:

MV-32293, MV-32295, MV-32274, MV-32276 CORRECT PLANT 10 NUMBERS FOR THIS UNIT:

MV-32274, MV-32276 Note:

Valve actu'ators MV-32293 and MV-32295 are used in Unit 2 functions and included in Equipment Item 14 for Unit 2.

I ITEMIZED DEFICIENCIES AND RESPONSES:

1.

Equipment' qualification not established.

i A.

Adequate similarity between equipment and test specimen not established.

B.

Aging degradation not evaluated adequately.

C.

Qualified life or replacement schedule not established.

Several pages of detailed notes were provided in the TER pertaining to deficiencies in the environmental qualification of this equipment item.

RESPONSE

A project has been initiated to thoroughly evaluate and document the environ-mental qualification of Limitorque valve actuators. Each of the concerns raised in the TER will be addressed in that evaluation. We expect that the evaluation will be finalized by January 1,1984, and that any necessary modifications or replacements will be performed prior to November 30, 1985.

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NORTHERN STATES POWER COMPANY TER Response PRAIRIE ISLAND NUCLEAR GENERATING PLANT July 29, 1983 Page 2.1-15 UNIT NUMBER:

1 TER EQUIPMENT ITEM NUMBER:

15 EQUIPMENT DESCRIPTION: Limitorque Motorized Valve Actuator Models SMB-00 EQUIPMENT LOCATION: Auxiliary Building TER QUALIFICATION CATEGORY:

II.A TER-IDENTIFIED PLANT ID NUMBERS: MV-32177, MV-32073, MV-32176, MV-32074 CORRECT PLANT ID NUMBERS FOR THIS UNIT: MV-32073, MV-32074 Note:

Valve actuators MV-32177 and MV-32176 are used in Unit 2 functions and included in Equipment Item 15 for Unit 2.

ITEMIZED DEFICIENCIES AND RESPONSES:

1.

Equipment qualification not established.

A.

Adequate similarity between equipment and test specimen not established.

B.

Aging degradation not evaluated adequately.

C.

Qualified life or replacement schedule not establ,ished.

Several pages of detailed notes were provided in the TER pertaining to deficiencies in the environmental qualification of this equipment item.

RESPONSE

A project has been initiated to thoroughly evaluate and document the environ-mental qualification of Limitorque valve actuators. Each of the concerns raised in the TER will be addressed in that evaluation. We expect that the evaluation will be finalized by January 1, 1984, and that any necessary modifications or replacements will be performed prior to November 30, 1985.

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NORTHERN STATES POWER CONPANY TER Response PRAIRIE ISLAND NUCLEAR GENERATING PLANT July 29, 1983 j

Page 2.1-16 i

UNIT NUMBER:

1 TER EQUIPMENT ITEM NUMBER:

16 EQUIPMENT DESCRIPTION: Target Rock Solenoid Valve Model 808-001 EQUIPMENT LOCATION: Reactor Building Unit 1 TER QUALIFICATION CATEGORY:

IV TER-IDENTIFIED PLANT ID NUMBERS:

SV-37035, SV-37037, SV-37039, SV-37036, SV-37038, SV-37040, SV-37091, SV-37093, SV-37095, SV-37092, SV-37094, SV-37096 CORRECT PLANT ID NUMBERS FOR THIS UNIT:

SV-37035, SV-37037, SV-37039, SV-37036, SV-37038, SV-37040 Note:

Solenoid Valves SV-37091, SV-37093, SV-37095, SV-37092, SV-37094, and SV-37096 are all used in Unit 2 functions and are included in Equipment Item 16 for Unit 2.

4 ITEMIZED DEFICIENCIES AND RESPONSES:

1.

Documentation.not made available to FRC for review.

RESPONSE

Documentation was r.ot provided to FRC because it was not included in the Request for Information submitted to NSP. However, this component is fully qualified for the installed environment and application at Prairie Island based on environmental qualification testing [1] and component-specific analyses [2].

This qualification data is available for inspection upon NRC request. This equipment item is therefore categorized in Category I.A and is fully qualified.

EQUIPMENT ITEM SPECIFIC RESPONSES:

1.

Target Rock Corporation Environmental Test Report #28048.

2.

EDS Report 04-0910-21, Revision 1, " Beta Radiation Evaluation of Safety-Related Electrical Equipment at Prairie Island Units 1 and 2," April 1982.

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NORTHERN STATES POWER COMPANY TER Response PRAIRIE ISLAND NUCLEAR GENERATING PLANT July 29, 1983 Page 2.1-17 UNIT NUMBER:

1 TER EQUIPMENT ITEM NUMBER:

17 EQUIPMENT DESCRIPTION: ASCO Solenoid Valve Model NP-831655E EQUIPMENT LOCATION:

Shield Building Unit 1 TER QUALIFICATION CATEGORY:

I.A TER-IDENTIFIED PLANT ID NUMBERS:

SV-33440, SV-33441 CORRECT PLANT 10 NUMBERS FOR THIS UNIT:

SV-33440, SV-33441 ITEMIZED DEFICIENCIES AND RESPONSES:

There are no deficiencies identified in the environmental qualification of this equipment item.

NORTHERN STATES POWER COMPANY TER Response PRAIRIE ISLAND NUCLEAR GENERATING PLANT July 29, 1983 Page 2.1-18 UNIT NUMBER:

1 TER EQUIPMENT ITEM NUMBER:

18 EQUIPMENT DESCRIPTION: ASCO Solenoid Valve Model NP-8320A194E EQUIPMENT LOCATION:

Shield Building Unit 1 TER QUALIFICATION CATEGORY:

1.A TER-IDENTIFIED PLANT ID NUMBERS:

SV-33990, SV-33991 CORRECT PLANT ID NUMBERS FOR THIS UNIT:

SV-33990, SV-33991 ITEMIZED DEFICIENCIES AND RESPONSES:

There are no deficiencies identified in the environmental qualification of this equipment item.

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NORTHERN STATES POWER COMPANY TER Response PRAIRIE ISLAND NUCLEAR GENERATING PLANT July 29, 1983 Page 2.1-19 1

UNIT NUMBER:

1 TER EQUIPMENT ITEM NUMBER:

19 EQUIPMENT DESCRIPTION: ASCO Solenoid Valve Model 8316C44/8211835 EQUIPMENT LOCATION: Auxiliary Building TER QUALIFICATION CATEGORY:

II.A TER-IDENTIFIED PLANT ID NUMBERS:

SV-33199, SV-33204, SV-33254 CORRECT PLANT ID NUMBERS FOR THIS UNIT:

SV-33199, SV-33200,'SV-33204, SV-33254 Note:

Four solenoid valves are used in steam generator isolation functions for Unit 1.

Solenoid valve SV-33200 was omitted from this equipment item.

ITEMIZED DEFICIENCIES AND RESPONSES:

1.

Equipment qualification not established.

A.

Documented evidence of qualification is inadequate.

RESPONSE

Failure of these solenoid valves will not adversely affect the closing of MSIVs and will not mislead the reactor operator. Solenoid valves SV-33199, SV-33200, SV-33204, and SV-33254 have therefore been removed from the safety-related equipment masterlist and environmental qualification is not required.

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NORTHERN STATES POWER COMPANY TER Response PRAIRIE ISLAND NUCLEAR GENERATING PLANT July 29, 1983 Page 2.1-20 UNIT NUMBER:

1 TER EQUIPMENT ITEM NUMBER:

20 EQUIPMENT DESCRIPTION: ASCO Solenoid Valve Model NP-8321 ale EQUIPMENT LOCATION: Auxiliary Building TER QUALIFICATION CATEGORY:

I.A TER-IDENTIFIED PLANT ID NUMBERS:

SV-33281 CORRECT PLANT ID NUMBERS FOR THIS UNIT:

SV-33281 ITEMIZED DEFICIENCIES AND RESPONSES:

There are no deficiencies identified in the environmental qualification of this equipment item.

f NORTHERN STATES POWER COMPANY TER Response PRAIRIE ISLAND NUCLEAR GENERATING PLANT July 29, 1983 Page 2.1-21 UNIT NUMBER:

1 TER EQUIPMENT ITEM NUMBER: 21 EQUIPMENT DESCRIPTION: ASCO Solenoid Valve Model NP-8316E35E EQUIPMENT LOCATION: Auxiliary Building TER QUALIFICATION CATEGORY:

1.A TER-IDENTIFIED. PLANT 10 NUMBERS: SV-33201, SV-33202, SV-33255, SV-33256 CORRECT PLANT ID NUMBERS FOR THIS UNIT: SV-33201, SV-33202, SV-33255, SV-33256 ITEMIZED DEFICIENCIES AND RESPONSES:

There are no deficiencies identified in the environmental qualification of this equipment item.

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i NORTHERN STATES POWER COMPANY TER Response PRAIRIE ISLAND NUCLEAR GENERATING PLANT July 29, 1983 Page 2.1-22 UNIT NUMBER:

1 TER EQUIPMENT ITEM NUMBER: 22 EQUIPMENT DESCRIPTION: ASCO Solenoid Valve Model NP-8321A1E EQUIPMENT LOCATION: Reactor Building Unit 1 TER QUALIFICATION CATEGORY:

I.A TER-IDENTIFIED PLANT ID NUMBERS:

SV-33371, SV-33372, SV-33373, SV-33374, SV-33375, SV-33376, SV-33377, SV-33378 CORRECT PLANT ID NUMBERS F0P. THIS UNIT:

SV-33371, SV-33372, SV-33373, SV-33374, SV-33375, SV-33376, SV-33377, SV-33378 ITEMIZED DEFICIENCIES AND RESPONSES:

There are no deficiencies identified in the environmental qualification of this equipment item.

l i

NORTHERN STATES POWER COMPANY TER Response l

PRAIRIE ISLAND NUCLEAR GENERATING PLANT July 29, 1983 Page 2.1-23 UNIT NUMBER:

1 TER EQUIPMENT ITEM NUMBER: 23 EQUIPMENT DESCRIPTION: ASCO Solenoid Valve Models NP-831654E, NP-8320A182E, and NP-8321 ale EQUIPMENT LOCATION:

Reactor Building Unit 1 TER QUALIFICATION CATEGORY:

I.A TER-IDENTIFIED PLANT ID NUMBERS:

SV-33761, SV-33762, SV-33738, SV-33739, SV-33655, SV-33282 CORRECT PLANT 10 NUMBERS FOR THIS UNIT: SV-33761, SV-33762, SV-33738, SV-33739, SV-33282 Note:

SV-33655 is a Valcor solenoid valve used in the Reactor Hot Sampling System and should not be included with this equipment item.

ITEMIZED DEFICIENCIES AND RESPONSES:

There are no deficiencies identified in the environmental qualification of '

this equipment item.

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NORTHERN STATES POWER COMPANY TER Response PRAIRIE ISLAND NUCLEAR GENERATING PLANT July 29, 1983 Page 2.1-24 UNIT NUMBER:

1 TER EQUIPMENT ITEM NUMBER:

24 EQUIPMENT DESCRIPTION: Micro Switch Limit Switch Model BZ2RW899A2 EQUIPMENT LOCATION:

Shield Building Unit 1 TER QUALIFICATION CATEGORY:

II.A TER-IDENTIFIED PLANT ID NUMBERS: CV-31625, CV-31630, CV-31631, CV-31624 CORRECT PLANT ID NUMBERS FOR THIS UNIT: CV-31624, CV-31625 Note:

Limit Switches CV-31630 and CV-31631 are used in Unit 2 functions and are included in Equipment Item 24 for Unit 2.

ITEMIZED DEFICIENCIES AND RESPONSES:

1.

Equipment qualification not established.

A.

Criteria regarding steam exposure is inadequate.

"The unit is exposed to steam as shown on the profiles provided by the licensee." The note for steam qualification on the SCEW from the August 26, 1981, NSP IEB79-01B SER submittal states, "The qualification documentation per-taining to these components is currently being. evaluated for inclusion in the bulletin."

RESPONSE

The April 30, 1982, IEB79-018 SER response updated the aforementioned statement to resolve all open items in the environmental qualification of this equipment item. An evaluation was performed to document the environmental qualification of Micro Switch limit switches for Prairie Island shield building applications

[1]. On the basis of this evaluation, it was concluded that these limit switches will not be exposed to a steam environment for the accident which requires their operation. HELBs are not postulated for the shield building, due to encapsulation of piping in piping penetrations. The limiting accident for this component (LOCA) does not yield steam conditions in the shield build-ing. Because there is no potential for steam or significant accumulation of condensate, switch degradation due to steam / relative humidity conditions will not occur. Therefore, there are no outstanding items in the environmental qualification of this equipment item and it is now classified in Category I.A.

EQUIPMENT ITEM SPECIFIC

REFERENCES:

1.

EDS Calculation File 0910-200-EQ-01, Revision 0, " Environmental Qualifica-tion of Micro Switch Limit Switches," December 1981.

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NORTHERN STATES POWER COMPANY TER Response PRAIRIE ISLAND NUCLEAR GENERATING PLANT July 29, 1983 Page 2.1-25 UNIT NUMBER:

1 TER EQUIPMENT ITEM NUMBER: 25 EQUIPMENT DESCRIPTION: NAMC0 Limit Switch Model EA-180 EQUIPMENT LOCATION: Reactor Building Unit 1 TER QUALIFICATION CATEGORY: II.A TER-IDENTIFIED PLANT ID NUMBERS: CD-34072, CD-34074, CD-34076, CD-34078, CD-34080, CD-34082, CD-34084, CD-34086 CORRECT PLANT ID NUMBERS FOR THIS UNIT: CD-34072, CD-34074, CD-34076, CD-34078 Note:

Limit Switches CD-34080, CD-34082, CD-34084, and CD-34086 are all used in Unit 2 functions and are included in Equipment Item 25 for Unit 2.

ITEMIZED DEFICIENCIES AND RESPONSES:

1.

Equipment qualification not established.

A.

Documented evidence of qualification is inadequate.

"The licensee has cited as evidence of qualifiation a test plan for the NAMC0 EA-180 and EA-740 Limit Switches. The referenced document is a test plan and not a test report. Furthermore, the SCEW does not identify the model number.

Accordingly, qualification has not been established."

RESPONSE

The limit switches included in this equipment item are identical to those included with Equipment Item 30. Equipment Item 30 was considered to be quali-fied providing a Conax Conductor Seal Assembly was installed (which has been done).

System Component Evaluation Worksheets (SCEWs) for all NAMCO limit switches have been revised to reference the NAMC0 qualification test report for EA-180 limit switches rather than the test plan.

In addition, a thermal aging evalua-tion was performed for NAMCO limit switches to determine component replacement intervals based on installed location in the plant [1].

The results of this evaluation are being incorporated into plant maintenance activities. On the basis of testing and analysis, we have concluded that this equipment item is fully qualified and is categorized in Category I.A.

EQUIPMENT ITEM SPECIFIC

REFERENCES:

1.

EDS Calculation File 0910-200-TA-01, Revision 1, "NAMC0 Limit Switch Thermal Aging Evaluation," April 1982.

NORTHERN STATES POWER COMPANY TER Response PRAIRIE ISLAND NUCLEAR GENERATING PLANT July 29, 1983 Page 2.1-26 UNIT NUMBER:

1 TER EQUIPMENT ITEM NUMBER: 26 EQUIPMENT DESCRIPTION:

NAMC0 Limit Switch Model D2400X EQUIPMENT LOCATION:

Reactor Building Unit 1 TER QUALIFICATION CATEGORY:

I.B TER-IDENTIFIED PLANT ID NUMBERS:

CV-31296, CV-31298, CV-31300, CV-31303, CV-31306, CV-31307 CORRECT PLANT ID NUMBERS FOR THIS UNIT:

SV-33651, SV-33653, SV-33655 Note:

Solenoid valves with integral indication features have been installed.

Solenoid valve ID numbers have replaced the limit switch ID numbers.

ITEMIZED DEFICIENCIES AND RESPONSES:

1.

Equipment modification required to establish qualification.

RESPONSE

NAMCO D2400X Limit Switches have been replaced with qualified Valcor Solenoid

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Valves with integral indication features.

The valves used in Unit 1 applica-l tions are identified with ID numbers SV-33651, SV-33653, and SV-33655.

Limit switch equipment ID numbers have been removed from the safety-related equipment masterlist and solenoid valve ID numbers have been added.

Because replacement I

with qualified equipment has already taken place, this equipment item is now classified in Category I.A and is fully qualified.

l

NORTHERN STATES POWER COMPANY TER Response PRAIRIE ISLAND NUCLEAR GENERATING PLANT July 29, 1983 Page 2.1-27 UNIT NUMBER:

1 TER EQUIPMENT ITEM NUMBER:

27 EQUIPMENT DESCRIPTION: NAMC0 Limit Switch Model EA-170 EQUIPMENT LOCATION: Auxiliary Building TER QUALIFICATION CATEGORY:

I.A TER-IDENTIFIED PLANT ID NUMBERS: CV-31235, CV-31236, CV-31237, CV-31238, CV-31239, CV-31240 CORRECT PLANT ID NUMBERS FOR THIS UNIT: CV-31235, CV-31236, CV-31237 Note:

Limit switches CV-31238, CV-31239, and CV-31240 are all used in Unit 2 functions and are included in Equipment Item 27 for Unit 2.

ITEMIZED DEFICIENCIES AND RESPONSES:

There are no deficiencies identified in the environmental qualification of this equipment item.

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l NORTHERN STATES POWER COMPANY TER Response PRAIRIE ISLAND NUCLEAR GENERATING PLANT July 29, 1983 Page 2.1-28a UNIT NUMBER:

1 TER EQUIPMENT ITEM NUMBER: 28 EQUIPMENT DESCRIPTION: NAMCO Limit Switch Model EA-170 EQUIPMENT LOCATION:

Shiela Building Unit 1 TER QUALIFICATION CATEGORY:

II.A TER-IDENTIFIED PLANT ID NUMBERS: CV-31310, CV-31312, CV-31569, CV-31621, CV-31622, CV-31633 CORRECT PLANT ID NUMBERS FOR THIS UNIT: CV-31621, CV-31622 Note:

Limit switches CV-31310, CV-31312, CV-31569, and CV-31633 have all been removed from the safety-related equipment masterlist because of modifi-cations to the Containment Purge System.

i ITEMIZED DEFICIENCIES AND RESPONSES:

1.

Equipment qualification not established.

A.

Aging degradation not evaluated adequately.

B.

Qualified life or replacement schedule not established. The licensee stated in the August 26, 1981, SER Response, "The qualification docu-mentation for aging pertaining to these components is currently being evaluated for inclusion in this bulletin."

C.

Peak pressure qualification inadequate.

D.

Required profile not enveloped adequately.

"The testing envelopes the Annulus temperature profile but not the pressure profile."

E.

Steam exposure qualification inadequate. "In addition, the licensee has not addressed the sealing method used to preclude entry of moisture."

RESPONSE

A thermal aging evaluation was performed for NAMC0 limit switches to determine component replacement intervals based on installed location in the plant [1].

Depending upon the material of the particular component within the limit switch, replacement is required in the range of 7 to 40 years. The results of this evaluation are being incorporated into plant maintenance activities.

Therefore, aging degradation and qualified life / replacement schedule have been adequately addressed.

The peak pressure postulated for the installed location (shield building) is 3 inches water (0.11 psi) and going to a vacuum of approximately 3-1/2 inches water (0.13 psi). The pressure will remain at this level for the duration of

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NORTHERN STATES POWER COMPANY TER Response PRAIRIE ISLAND NUCLEAR GENERATING PLANT July 29, 1983 Page 2.1-28b ITEMIZED DEFICIENCIES AND RESPONSES (Cont.):

the 2-hour operating time. Pressures of this magnitude for a 2-hour duration will not impose stresses on the limit switches in excess of those occurring during pressure variations in normal operation and will not lead to switch failure.

These limit switches will not be exposed to a steam environment for the acci-dent which requires their operation. HELBs are not postulated for the shield building due to encapsulation in piping penetrations. The limiting accident for this component (LOCA) does not yield steam conditions in the shield building.

Because there is no potential for steam or significant accumulation of conden-sate,' switch degradation due to steam / relative humidity conditions will not occur. In addition, RTV is applied to the conduit entry of all NAMC0 EA-170 limit switches to further protect against intrusion of moisture into the limit switch.

On the basis of the discussion provided above, we conclude that all deficien-cies have been resolved and this component is fully qualified. Equipment Item 28 is therefore categorized in Category I.A.

EQUIPMENT ITEM SPECIFIC

REFERENCES:

1.

EDS Calculation File 0910-200-TA-01, Revision 1, "NAMC0 Limit Switch Thermal Aging Evaluation," April 1982.

l l

NORTHERN STATES POWER C0ffANY TE.R Response PRAIRIE ISLAND NUCLEAR GENERATING PLANT July 29, 1983 Page 2.1-29 UNIT NUMBER:

1 TER EQUIPMENT ITEM NUMBER:

29 EQUIPMENT DESCRIPTION: NAMC0 Limit Switch Model EA-180 EQUIPMENT LOCATION: Reactor Building Unit 1 TER QUALIFICATION CATEGORY:

I.B TER-IDENTIFIED PLANT ID NUMBERS: CV-31231, CV-31232 CORRECT PLANT ID NUMBERS FOR THIS UNIT: CV-31231, CV-31232 ITEMIZED DEFICIENCIES AND RESPONSES:

1.

Equipment modification required to establish qualification.

RESPONSE

A Conax Electric Conductor Seal Assembly (ECSA) has been installed to hermeti-cally seal the limit switch enclosure. Categorization in Category I.A., Equip-ment Qualified, was not established because of the absence of a Conax ECSA.

Since the ECSA has been installed, this equipment item is now categorized in Category I.A and is fully qualified.

In addition, a thermal aging evaluation was performed for NAMC0 limit switches to determine component replacement intervals based on installed location in the plant [1]. The results of this evaluation are being incorporated into plant maintenance activities.

EQUIPMENT ITEM SPECIFIC

REFERENCES:

1.

EDS Calculation File 0910-200-TA-01, Revision 1, "NAMC0 Limit Switch Thermal Aging Evaluation," April 1982.

NORTHERN STATES POWER COMPANY TER Response PRAIRIE ISLAND NUCLEAR GENERATING PLANT July 29, 1983 Page 2.1-30 UNIT NUMBER:

1 TER EQUIPMENT ITEM NUMBER:

30 EQUIPMENT DESCRIPTION: NAMC0 Limit Switch Model EA-180 EQUIPMENT LOCATION:

Reactor Building Unit 1 TER QUALIFICATION CATEGORY:

I.B TER-IDENTIFIED PLANT ID NUMBERS: CD-34072, CD-34074, CD-34076, CD-34078 CORRECT PLANT ID NUMBERS FOR THIS UNIT: CD-34072, CD-34074, CD-34076, CD-34078 ITEMIZED DEFICIENCIES AND RESPONSES:

1.

Equipment modification required to establish qualification.

RESPONSE

A Conax Electric Conductor Seal Assembly (ECSA) has been installed to hermeti-cally seal the limit switch enclosure. Categorization in Category I.A, Equip-ment Qualified, was not established because of the absence of a Conax ECSA.

Since the ECSA has been installed, this equipment item is now categorized in Category I.A and is fully qualified.

In addition, a thermal aging evaluation was performed for NAMC0 limit switches to determine component replacement intervals based on installed location in the plant [1]. The results of this evaluation are being incorporated into plant maintenance activities.

EQUIPMENT ITEM SPECIFIC

REFERENCES:

1.

EDS Calculation File 0910-200-TA-01, Revision 1, "NAMC0 Limit Switch Thermal Aging Evaluation," April 1982.

l NORTHERN STATES POWER COMPANY TER Response

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PRAIRIE ISLAND NUCLEAR GENERATING PLANT July 29, 1983 Page 2.1-31 UNIT NUMBER:

1 TER EQUIPMENT ITEM NUMBER:

31 EQUIPMENT DESCRIPTION: NAMC0 Limit Switch Model EA-180 EQUIPMENT LOCATION: Auxiliary Building TER QUALIFICATION CATEGORY:

I.B TER-IDENTIFIED PLANT ID NUMBERS: CV-31098, CV-31099, CV-31116, CV-31117, CV-31084, CV-31102, CV-31089 CORRECT PLANT 10 NUMBERS FOR THIS UNIT: CV-31098, CV-31099, CV-31084, CV-31089 Note:

Limit switches CV-31116, CV-3117, and CV-31102 are all useo in Unit 2 functions and are included in Equipment Item 31 for Unit 2.

ITEMIZED DEFICIENCIES AND RESPONSES:

1.

Equipment modification required to establish qualification.

RESPONSE

A Conax Electric Conductor Seal Assembly (ECSA) has been installed to hermeti-cally seal the limit switch enclosure. Categorization in Category I.A, Equip-ment Qualified, was not established because of the absence of a Conax ECSA.

Since the ECSA has been installed, this equipment item is now categorized in Category I.A and is fully qualified.

In addition, a thermal aging evaluation was performed for NAMCO limit switches to determine component replacement intervals based on installed location in the plant [1]. The results of this evaluation are being incorporated into plant maintenance activities.

EQUIPMENT ITEM SPECIFIC

REFERENCES:

1.

EDS Calculation File 0910-200-TA-01, Revision 1, "NAMCO Limit Switch Thermal Aging Evaluation," April 1982.

NORTHERN STATES POWER COMPANY TER Response PRAIRIE ISLAND NUCLEAR GENERATING PLANT July 29, 1983 Page 2.1-32 UNIT NUMBER:

1 TER EQUIPMENT ITEM NUMBER: 32 EQUIPMENT DESCRIPTION: NAMC0 Limit Switch Model EA-180 EQUIPMENT LOCATION: Reactor Building Unit 1 TER QUALIFICATION CATEGORY:

I.B TER-IDENTIFIED PLANT ID NUMBERS:

CV-31325, CV-31326, CV-31327, CV-31313, CV-31570, CV-31311, CV-31634, CV-31019, CV-31092, CV-31296, CV-31298, CV-31300, CV-31303, CV-31305, CV-31307, CV-31637, CV-31638, CV-31741, CORRECT PLANT ID NUMBERS FOR THIS UNIT: CV-31325, CV-31326, CV-31327, CV-31019, CV-31092, CV-31637, CV-31638, CV-31741 Note:

Limit switches CV-31313, CV-31570, CV-31311 and CV-31634 have been removed from the safety-related equipment master list because of modi-fication to the Containment Purge System. Limit switches CV-31296, CV-31298, CV-31300, CV-31303, CV-31305, and CV-31307 are identical to Equipment Item 26 and are addressed with that equipment item.

ITEMIZED DEFICIENCIES AND RESPONSES:

1.

Equipment modification required to establish qualification.

RESPONSE

A Conax Electric Conductor Seal Assembly (ECSA) has been installed to hermeti-cally seal the limit switch enclosure. Categorization in Category I.A Equip-ment Qualified, was not established because of the absence of a Conax ECSA.

l Since the ECSA has been installed, this equipment item is now categorized in Category I.A and is fully qualified.

In addition, a thermal aging evaluation was performed for NAMC0 limit switches to determine component replacement intervals based on installed location in the plant [1]. The results of this evaluation are being incorporated into plant maintenan:e activities.

EQUIPMENT ITEM SPECIFIC

REFERENCES:

1.

EDS Calculation File 0910-200-TA-01, Revision 1, "NAMC0 Limit Switch Thermal Aging Evaluation," April 1982.

l l

4 NORTHERN STATES POWER COWANY TER Response PRAIRIE ISLAND NUCLEAR GENERATING PLANT July 29, 1983 Page 2.1-33a UNIT NUMBER:

1 TER EQUIPMENT ITEM NUMBER:

33 EQUIPMENT DESCRIPTION: Electric Machinery Manufacturing Co. Electric Motors EQUIPMENT LOCATION: Auxiliary Building TER QUALIFICATION CATEGORY:

II.A TER-IDENTIFIED PLANT ID NUMBERS:

15-9, 16-01, 26-01, 25-9 CORRECT PLANT ID NUMBERS FOR THIS UNIT:

15-9, 16-01 Note:

Electric Motors 26-01 and 25-9 are used in Unit 2 functions and are included in Equipment Item 33 for Unit 2.

ITEMIZED DEFICIENCIES AND RESPONSES:

1.

Equipment qualification not established.

A.

Qualified life or replacement schedule not identified.

B.

Program established to identify aging degradation.

C.

Criteria regarding radiation not satisfied.

The licensee has not established the qualification of a lubricant for use....

In addition, the radiation evaluation states that the only material that will not withstand the radiation environment is the motor winding RTD cable....

The failure analysis does not indicate if the operator could be misled by the failure of this device and could possibly shut off the motor....

The analysis concludes that the motors should withstand an accident dose of 2.8x106 Rads, not the 1.0x108 Rads level shown on the licensee's SCEW sheets."

RESPONSE

An evaluation has been performed to determine the thermal aging characteristics of this motor [1]. The evaluation was based on the motor materials of con-struction, material testing, ambient and motor operating temperatures, and the operating requirements of the motor. On the basis of this evaluation, it is concluded that the Electric Machinery Manufacturing Company motors used as containment spray pump motors at Prairie Island are qualified for 40 years of operation.

There are no equipment ; qualification maintenance or replacement requirements, outside of normal preventative maintenance. Preventative maintenance includes general inspection of the motor and periodic replacement of the motor lubri-cant, Chevron SRI-2. This lubricant has been environmentally qualified (see Equipment Item 62) and was therefore not specifically addressed in this evaluation.

NORTHERN STATES POWER COMPANY TER Response PRAIRIE ISLAND NUCLEAR GENERATING PLANT July 29,198; Page 2.1-33b ITEMIZED DEFICIENCIES AND RESPONSES (Cont.):

The radiation evaluation of these motors states that the only material.poten-tially unqualified to the required dose of 2.8x106 rads is the motor winding RTD extension cable. The temperature signal is used for indication purposes only and is not used as an automatic shut-down mechanism. Failurb of the RTD extension cable resulting in erroneus motor winding temperature data will not mislead the plant operator.

The SCEW for this equipment item has been revised to include the results of the analyses performed on these motors.

On the basis of the evaluations performed, and summarized herein, all concerns raised in the TER have been adequately resolved. This equipment item is there-fore categorized in Category I.A and is fully qualified.

EQUIPMENT ITEM SPECIFIC

REFERENCE:

1.

EDS/Impell Calculation File 0910-200-RA-01, Revision 2, " Radiation and Thermal Aging Analysis of Containment Spray Pump Motors," July 1983.

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l NORTHERN STATES F0WER COMPANY TER Response PRAIRIE ISLAND WCLEAR GENERATING PLANT July 29,1983 Page 2.1-34a UNIT NUMER:

1 TER EQUIPMENT ITEM NUMBER: 34 EQUIPMENT DESCRIPTION:

Joy / Reliance Electric Motor Model 60027769 EQUIPMENT LOCATION: Reactor Building Unit 1 TER QUALIFICATION CATEGORY:

II.A TER-IDENTIFIED PLANT ID NUMBERS:

116-18, 126-18, 116-19, 126-32, 215-18, 226-18, 216-19, 226-32 CORRECT PLANT ID NUMBERS FOR THIS UNIT: 116-18, 126-18, 116-19, 126-32

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Note:

Electric motors 216-18, 226-18, 216-19, and 226-32 are used in Unit 2 functions and are included in Equipment Item 34 for Unit 2.

ITEMIZED DEFICIENCIES AND RESPONSES:

1.

Equipment qualification not established.

A.

Adequate similarity between equipment and test specimen not estab-lished.

...The licensee does not, however, provide evidence from the manuf acturer that the report is applicable to the installed motors and that they are from the 'line' of motors referenced in the report."

B.

Aging degradation not evaluated adequately.

C.

Qualified life or replacement schedule not established.

"The approach used by Joy to develop an accelerated aging program for the Reliance motors is based on the assumption that the insulation system is the limiting conponent. In many instances this would be correct; however, a material evaluation should be undertaken to substantiate this hypothe-sis. The lead cable insulation degraded to the pc.nt of f ailure l

(ent)rittlement) before the motor insulation failed during the post-l event testing. Joy stated the following with respect to the anomaly:

'This separation of leads was caused by a cont >ination of lead wire embrittlement due to the tenperature and chemicals and vibration in the leads because of the manner in which the leads were connected.

The problem occurred outside the conduit pipe where the leads were bent to allow for connection to the terminal plate before it was bolted down.

In an actual installation, this severe bend does not exist and, there-fore, the problem should not occur....

a.

the licensee has not presented a maintenance / surveillance program for the motor-insulation-to-lead splice, lead cable, or bearing system that could preclude age-related f ailure of these components.

b.

the licensee did not present the data that the ' life characteris-tics plot of the motor insulation' was based on.

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NORTHERN STATES POWER COMPANY TER Response PRAIRIE ISLAND NUCLEAR GENERATING PLANT July 29, 1983 Page 2.1-34b ITEMIZED DEFICIENCIES add RESPONSES (Cont.):

c.

a materials. evaluation program was not performed to establish the basis of the thermal aging program."

D.

Criteria regarding radiation not satisfied.

"Although a separate effects radiation analysis was performed, the materials discussed were identified by Reliance specification number and not by chemical compo-sition so that the radiation damage threshold values could be verified.

The licensee has provided an engineering analysis of the shielding pro-vided by the motor housing against the effects of beta radiation. The licensee has not verified that the motor housing completely encases the materals susceptible to beta exposure."

RESPONSE

The environmental qualification of this equipment item was completely re-evaluated. Correspondence with the motor vendcr, Reliance, indicates that the qualification report previously used was not applicable to the installed motor; however, applicable reports were identified. Utilizing the applicab.le qualification reports, environmental qualification including a 40 year qualified life and six months post-accident operation was justified. These results are documented in [1].

Thermal aging qualification is cased on motor material degradation characterics and extrapolates test data to the Prairie Island specific parameters using the Arrhenius method. This qualification is based on test data from the motor vendor on insulation identical to that installed. A maintenance / surveillance program does exit for these motors that includes periodic inspection of the motor-to-lead splice, lead cable, bearings, and motor lubicants.

On the basis of the evaluation performed in [1] and summarized aDove, all concerns raised have been adequately addressed and these motors are fully qualified for their intended survice at Prairie Island. This equipment item is now categorized in Category I.A. and is fully qualified.

EQUIPMENT ITEM SPECIFIC

REFERENCES:

1.

Impell Calculation File 0910-200-Joy-01, " Environmental Evaluation of Joy / Reliance Fan Motors," July 1983.

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l NORTHERN STATES POWER COMPANY TER Response PRAIRIE ISLAND NUCLEAR GENERATING PLANT July 29, 1983 Page 2.1-35a UNIT NUMBER:

1 TER EQUIPMENT ITEM NUMBER: 35 EQUIPMENT DESCRIPTION: Westinghouse Electric Motor Model Ll'054-1760/875 EQUIPMENT LOCATION: Reacter Building Unit 1 TER QUALIFICATION CATEGORY:

II.A TER-IDENTIFIED PLANT ID NUMBERS:

117-2, 127-2, 117-3, 127-3, 217-2, 227-2, 217-3, 227-3 CORRECT PLANT ID NUMBERS FOR THIS UNIT:

117-2, 127-2, 117-3, 127-3 Note:

Electric motors 217-2, 227-2, 217-3, and 227-3 are used in Unit 2 functions and are included in Equipment Item 35 for Unit 2.

ITEMIZED DEFICIENCIES AND RESPONSES:

1.

Equipment qualification not established.

A.

Adequate similarity between equipment and test specimen not estab-lished.

"The licensee has not stated that the installed motors have an integral air-to-water heat exchanger,..., has not established the bearing lubricant currently used in the motor,...

has not established the similarity of the motor-to-lead splice in the installed motor to the tested device,..., has not provided any documentation that indi-cates that the insulation system in the installed device is the same as that tested."

B.

Aging degraaation nct evaluated adequately.

C.

Qualified life or replacement schedule not established.

"Although the test report states that aging was performed to simulate 40 years in service, the licensee has not provided any analysis to show that the simulation applies to the plant-specific conditions.... The licensee has not provided a replacement / maintenance schedule for subcomponents."

D.

Criteria regarding temperature / pressure exposure duration not adequate.

"The licensee has not provided any basis for the 2-month operating time."

In addition, the following comment was provided.

"The licensee has not indicated if the motor is equipped with an air-to-water heat exchanger.

If it is, the licensee has not evaluated the effect of beta entering through

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the air intake of the heat exchanger."

RESPONSE

The Westinghouse fan cooler motors installed at Prairie Island are mounted j

vertically and are equipped with an integral air-to-water heat exchanger.

The i

l

NORTHERN STATES POWER C0W ANY TER Response PRAIRIE ISLAND NUCLEAR GENERATING PLANT July 29, 1983 Page 2.1-3Sb ITEMIZED DEFICIENCIES AND. RESPONSES (Cont.):

motor, heat exchanger, arid ' ans aie totally enclosed. Chevron SRI-2 lubricating f

grease is used for bearing lubrication. This lubricant has been environmentally qualified with no identified deficiencies (see Equipment Item 62). All field splices are installed following NSP Work Instruction 000-03-001 for cable splicing ard terminations. Each of the. splices and terminations used in safety-related applications have been environmentally qualified. The installed motor insulation system is thermalastic epoxy. identical to that tested in WCAP 7829..

Correspondence with the equipment vendor, Westinghouse, indicates that qualifi-cation testing, documented in WCAP 7829 is directly applicaole to the RCFC motors installed at Prairie Island [1].

An aging evaluation has been perforned to correlate the simulated aging in the test program to the in ~ service conditions at' Prairie Island [2]. The results of this evaluation show that a qualified life in excess of 40 years has been simulated by the test, using the Arrhenius methodology. There are no require-ments for subcomponent replacement in the 40.-year qualified life of the motors.

Alth6 ugh thsre'are no' specific equipment ~ qualification maintenance require-ments, these motors are on a preventative maintenance program that periodically inspects the motors.

WCAP 7829 documents the qualificaion to long te6n (up to one year) post accident! operating requirements based on testing and analysis.

In essence, the motor heat exchanger maintains bearing and insulation temperatures low enough.during post accident conditions to preclude. adverse degradation.

=

As noted above, these rh.otors are tothllhencIosed with an integral air-to-water heat exchanger. There are.no vent openings on the motor and no potential for intrusion of beta radiation through the Water (intake.

Thus, the motor enclo-sure does provide sufficient shielding against beta radiation.

. 00 the. basis of the evaluations performed and the discussion provided above,

~all identified deficiencies:in the environmental qualification of this equip-ment item have been adequately resolved. Westinghouse fan cooler motors are l

~

therefore class'ified in Category 1.A and are fully qualified.

EQUIPM5T1 ITEM SPECIFIC

REFERENCES:

i 1.

Westingho'use Electric Company, Water Reactor Divisions letter from P. Van Teslaar to K. Becker of EDS Nuclear, February 1,1982.

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2.

Impell Calculation File 0910-200-hES-01, Revision 0, " Thermal Aging l

Analysis of Westinghouse, Motors," July 1983.

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s NORTHERN STATES POWER COMPANY TER Response PRAIRIE ISLAND NUCLEAt GENERATING PLANT.

July 29, 1983 x'

i Page 2.1-36

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UNIT NUMBER:< 1 TER EQUIPMENT ITEM HUMBER: 36 EQUIPMENT 0ESCRIPTION:

Westinghouse Electric Motor 14odel HSDP EQUIPMENT LOCATION: Auxilfary Building

,4 TER QUALIFICATION CATEGORY:'- II.A TER-IDENTIFIED PLANTLID NUMBERh ',15-1, 16-5, 26-3, 25-5 CORRECT PLANT ID NUMBERS FOR THIS TNIT:

15-1, 16-5 1

Note:

Electric moto:s 26-3 an62525 are used in'hnft 2 functions and are included in Equipaent Item 36 for Unit 2.

s

' n ITEMIZED DEFICIENCIEG AND RESP 07.SES:

hauipmentqualificaIonnot. established.

1.

ed" A.

Adequate simila'rf ty Letween. equiotent and test specimen not estab-t

'.s-referenced report to the,installdd' device. WCAP-8754 states that the

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lished.

"The license'. hts not establishti the applicability of the

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device tested was a formette made of Class 8 thermaiastic epoxy stator insulation. WCAP-7B?S' relates to testing of windings of the same type for radiation tolerancelanet testing of Westinghouse Si723A773-G05 lubricant for radiationiresistance. The licensee's SCEW states:

' Motor, Westinghouse, $ 0-P'.

No attempt has been made by the licensee to establish that the irrtalled' motor and subcomponents are the same as those tested."

RESPONSE

i A project has been initiated to re-evaluate the environmental qualification of Westinghouse motors. The motor vendor has been contacted to identify the applicable qualification test report, based on motor materials of construc-tion. Once this identification has been made, a complete qualification evalua-tion will be performed for'all environmental parameters. We expect that this evaluation will be completed by January 1, 1984, and that any necessary modifications or replacements will be performed prior to November 30, 1985.

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NORTHERN STATES POWER COMPANY TER Response PRAIRIE ISLAND NUCLEAR GENERATING PLANT July 29, 1983 Page 2.1-37 UNIT NUMBER:

1 TER EQUIPMENT ITEM NUMBER: 37 EQUIPMENT DESCRIPTION: Westinghouse Electric Motor Model HSDP EQUIPNENT LOCATION: Auxiliary Building TER QUALIFICATION CATEGORY:

II.A TER-IDENTIFIED PLANT ID NUMBERS:

15.4, 16-4, 25-4, 26-4 CORRECT PLANT ID NUMBERS FOR THIS UNIT:

15-4, 16-4 Note:

Electric motors 25-4 and 26-4 are used in Unit 2 functions and are included in Equipment Item 37 for Unit 2.

ITEMIZED DEFICIENCIES AND RESPONSES:

1.

Equipment qualification not established.

A.

Adequate similarity between equipment and test specimen not estab-lished.

"The licensee has not established the applicability of the referenced report to the installed device. WCAP-8754 states that the device tested was a formette made of Class B thermalastic epoxy stator insulation. WCAP-7829 relates to testing of windings of the same type for radiation tolerance and testing of Westinghouse S#723A773-G05 lub-ricant for radiation resistance. The licensee's SCEW states:

' Motor, Westinghouse, HSD-P'.

No. attempt has been made by the licensee to establish that the installed motor and subcomponents are the same as those tested."

i

RESPONSE

A project has been initiated to re-evaluate the environmental qualification of Westinghouse motors. The motor vendor has been contacted to identify the applicable qualification test report, based on motor materials of construc-tion. Once this identification has been made, a complete qualification evalua-tion will be performed for all environmental parameters. We expect that this evaluation will be completed by January 1,1984, and that any necessary modifications or replacements will be performed prior to November 30, 1985.

m.

NORTHERN STATES POWER COMPANY TER Response PRAIRIE ISLAND NUCLEAR GENERATING PLANT July 29, 1983 Page 2.1-38 UNIT NUMBER:

1 TER EQUIPMENT ITEM NUMBER: 38 EQUIPMENT DESCRIPTION: Barton Flow Transmitter Model 332 EQUIPMENT LOCATION: Auxiliary Building TER QUALIFICATION CATEGORY:

I.B TER-IDENTIFIED PLANT ID NUMBERS:

23073, 23074, 23075, 23076 CORRECT PLANT ID NUMBERS FOR THIS UNIT: 23073, 23074 Note:

Flow transmitters 23075 and 23076 are used in Unit 2 functions and are included in Equipment Item 38 for Unit 2.

ITEMIZED DEFICIENCIES AND RESPONSES:

1.

Equipment modification required to establish qualification.

RESPONSE

These transmitters were originally identified for relocation to a mild environ-ment. However, for maintenance reasons, they will be replaced with qualified transmitters.

Rosemount 1153 Series B transmitters have been ordered and will be installed during Unit 1 Cycle 9 and prior to November 30, 1985. Once this replacement has taken place, this equipment item will be classified in Category I.A and will be fully qualified.

NORTHERN STATES POWER C0ffANY TER Response PRAIRIE ISLAND NUCLEAR GENERATING PLANT July 29, 1983 Page 2.1-39 UNIT NUMBER:

1 TER EQUIPMENT ITEM NUMBER: 39 EQUIPMENT DESCP.IPTION:

Foxboro Flow Transmitter Model E13DH(MCA)

EQUIPMENT LOCATION: Auxiliary Building TER QUALIFICATION CATEGORY:

II.A TER-IDENTIFIED PLANT ID NUMBERS: 23021, 23022, 23023, 23024, 23025, 23026, 23027, 23028 CORRECT PLANT ID NUMBERS FOR THIS UNIT: 23021, 23022, 23023, 23024 Note:

Flow transmitters 23025, 23026, 23027, and 23028 are used in Unit 2 functions and are included in Equipment Item 39 for Unit 2.

ITEMIZED DEFICIENCIES AND RESPONSES:

1.

Equipment qualification not established.

A.

Adequate similarity between equipment and test specimen not estab-lished. "The licensee has not stated the output current range of their Foxboro transmitters.

(The tables of note 1 differentiate between 4-20 and 10-50 ma models.) Therefore, accuracy tolerances of -12% for the E11GM and -9% for the E13DH must be assumed. Since the licensee has failed to specify the required accuracy for these transmitters, compliance with accuracy criteria is suspect."

RESPONSE

Safety-related equipment accuracies are currently being reviewed and defined as part of the Prairie Island emergency preparedness program. These instrument accuracies will be plant-specific and based on various postulated accident scenarios. Based on the functional requirements of these transmitters, we expect the instrument accuracies experienced in qualification testing to be acceptable.

If it is determined that the accuracies experienced in the qualification testing are unacceptable, accident operating procedures will be modified accordingly.

i i

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a.

NORTHERN STATES POWER COMPANY TER Response PRAIRIE ISLAND NUCLEAR GENERATING PLANT July 29, 1983 Page 2.1-40 UNIT NUMBER:

1 TER EQUIPMENT ITEM NUMBER: 40 EQUIPMENT DESCRIPTION:

Barton Flow Transmitter Model 384 EQUIPMENT LOCATION: Reactor Building Unit 1 TER QUALIFICATION CATEGORY:

I.B TER-IDENTIFIED PLANT ID NUMBERS: 23013, 23014, 23015, 23016 CORRECT PLANT ID NUMBERS FOR THIS UNIT: 23013, 23014, 23015, 23016 ITEMIZED DEFICIENCIES AND RESPONSES:

1.

Equipment modification required to establish qualification.

RESPONSE

Barton model 384 flow transmitters have been replaced with Rosemount 1153 Series D transmitters. The 1153 Series 0 transmitter series have recently com-pleted a qualification test program and are fully qualified for the installed application. Because replacement with a qualified transmitter has already taken place, this equipment item is now classified in Category I.A and is fully qualified.

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NORTHERN STATES POWER COMPANY TER Response PRAIRIE ISLAND NUCLEAR GENERATING PLANT July 29, 1983 Page 2.1-41 UNIT NUMBER:

1 TER EQUIPMENT ITEM NUMBER:

41 EQUIPMENT DESCRIPTION: Magnetrol Level Transmitter Model A153FEP/VPXYTD EQUIPMENT LOCATION:

Reactor Building Unit 1 TER QUALIFICATION CATEGORY:

I.B TER-IDENTIFIED PLANT ID NUMBERS:

16796, 16811, 16909, 16910 CORRECT PLANT ID NUMBERS FOR THIS UNIT:

ILT-725, ILT-726, ILT-727A, ILT-7278, ILT-728A, ILT-7288 ITEMIZED DEFICIENCIES AND RESPONSES:

1.

Equipment modification required to establish qualification.

RESPONSE

Magnetrol level transmitters have been replaced with qualified containment sump water level transmitters.

Delaval level transmitters model XM-54854-323 were installed and have recently completed a qualification test program which fully qualifies the level transmitters for the environmental conditions associated with the installed location.

Because replacement with a qualified transmitter has already taken place, this equipment item is now classified in Category I.A and is fully qualified.

NORTHERN STATES POWER COMPANY TER Response PRAIRIE ISLAND NUCLEAR GENERATING PLANT July 29, 1983 Page 2.1-42 UNIT NUMBER:

1 TER EQUIPMENT ITEM NUMBER: 42 EQUIPMENT DESCRIPTION: Barton Level Transmitter Model P386-351 EQUIPMENT LOCATION: Reactor Building Unit 1 TER QUALIFICATION CATEGORY:

I.B TER-IDENTIFIED PLANT ID NUMBERS: 24041, 24042, 24043, 24046, 24047, 24048 CORRECT PLANT ID NUMBERS FOR THIS UNIT: 24041, 24042, 24043 Note:

Level transmitters 24046, 24047, and 24048 are all used in Unit 2 functions and are included in Equipment Item 42 for Unit 2.

ITEMIZED DEFICIENCIES AND RESPONSES:

1.

Equipment modification required to establish qualification.

RESPONSE

Qualified replacement transmitters have been ordered and will be installed during Unit 1, Cycle 8/9 and prior to the end of the second refueling outage after March 31, 1982. Barton model 764-351 level transmitters, which have successfully completed qualification testing, will be installed, and will then be classified in Category I.A and be fully qualified.

i

NORTHERN STATES POWER COMPANY TER Response PRAIRIE ISLAND NUCLEAR GENERATING PLANT July 29, 1983 Page 2.1-43 UNIT NUMBER:

1 TER EQUIPMENT ITEM NUMBER: 43 EQUIPMENT DESCRIPTION:

Foxboro Level Transmitter Model E13DHSAMI EQUIPMENT LOCATION: Reactor Building Unit 1 TER QUALIFICATION CATEGORY:

I.B TER-IDENTIFIED PLANT ID NUMBERS:

24080, 24081, 24082, 24083, 24084, 24085, 24086, 24087 CORRECT PLANT ID NUMBERS FOR THIS UNIT:

ILT-487, ILT-488 Note:

Qualified transmitters with Plant ID numaers ILT-487 and ILT-488 for Unit 1 and 2LT-487 and 2LT-488 for Unit 2 were installed. Unit 2 transmitters are included in Equipment Item 43 for Unit 2.

ITEMIZED DEFICIENCIES AND RESPONSES:

1.

Equipment modification required to establish qualification.

RESPONSE

Qualified level transmitters have been installed and are designated with Plant ID numbers ILT-487 and ILT-488 for Unit 1. Foxbor., N-E120H-IIAF level transmit-ters, which have successfully completed qualificp. ion testing, were installed.

Because installation of qualified transmiters has already taken place, this equipment item is now classified as Category I.A and is fully qualified.

I l

.s NORTHERN STATES POWER COMPANY TER Response PRAIRIE ISLAND NUCLEAR GENERATING PLANT July 29, 1983 Page 2.1-44 UNIT NUMBER:

1 TER EQUIPMENT ITEM NUMBER: 44 EQUIPMENT DESCRIPTION: Foxboro Pressure Transmitter Model EllGH EQUIPMENT LOCATION: Reactor Building Unit 1 TER QUALIFICATION CATEGORY:

I.B TER-IDENTIFIED PLANT ID NUMBERS: 21101, 21152 CORRECT PLANT ID NUMBERS FOR THIS UNIT:

IPT-709, 1PT-710 Note:

Qualified transmitters with Plant ID numbers 1PT-709 and 1PT-710 were installed for Unit 1.

ITEMIZED DEFICIENCIES AND RESPONSES:

1.

Equipmerit modification required to establish qualification.

RESPONSE

1 Qualified pressure transmitters have been installed and are designated with Plant ID numbers IPT-709 and IPT-710.

It was previously identified that Rosemount 1153GD9 transmitters were installed; however, the correct model number of the transmitter installed in Unit 1 is Rosemount ll53GA9.

1153GA9 transmitters were evaluated by FRC and classified in TER Category II.b, equip-ment not qualified. A separate evaluation was transmitted to the NRC by NSP which addressed the qualification deficiencies cited for the ll53GA9 transmit-ters and concluded that the correct qualification category is II.C [1]. An evaluation will be performed to determine the required maintenance and replace-ment intervals. Following the completion of this evaluation, this equipment item will be categorized in Category I.A and will be fully qualified.

i EQUIPMENT ITEM SPECIFIC

REFERENCES:

1.

NRC letter from Robert Clark to D. M. Musolf (NSP) dated June 3, 1983, and 3

attached Safety Evaluation Concerning Justification for Continued Operation for Prairie Island Nuclear Generating Plant, Unit Nos. 1 and 2, as Related to Environmental Qualification of Safety-Related Electrical Equipment Clas-sified as Not Qualified.

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NORTHERN STATES POWER COMPANY TER Response PRAIRIE ISLAND NUCLEAR GENERATING PLANT July 29, 1983 Page 2.1-45 UNIT NUMBER:

1 TER EQUIPMENT ITEM NUMBER:

45 EQUIPMENT DESCRIPTION: Foxboro Pressure Transmitter Model EllGMSAD1 EQUIPMENT LOCATION: Reactor Building Unit 1 TER QUALIFICATION CATEGORY:

I.B TER-IDENTIFIED PLANT ID NUMBERS: PT-21164, PT-21165, PT-21166, PT-21167 PT-21168, PT-21169, PT-21170, PT-21171 CORRECT PLANT ID NUMBERS FOR THIS UNIT: PT-21164, PT-21165, PT-21166, PT-21167 Note:

Pressure transmitters PT-21168, PT-21169, PT-21170, and PT-21171 are all used in Unit 2 functions and are included in Equipment Item 45 for Unit 2.

ITEMIZED DEFICIENCIES AND RESPONSES:

1.

Equipment modification required to establish qualification.

RESPONSE

Foxboro Model N-EllGM-H101-AE pressure transmitters, which have successfully have been installed. Because replacement has passed qualification testing,ipment item is now classified as Category I.A and already taken place, this equ is fully qualified.

. i l

NORTHERN STATES POWER COMPANY TER Response i

PRAIRIE ISLAND NUCLEAR GENERATING PLANT July 29,1983 Page 2.1-46 UNIT NUMBER:

1 TER EQUIPMENT ITEM NUMBER: 46 EQUIPMENT DESCRIPTION:

Foxboro Pressure Transmitter Model EllGM-SAE1 (MCA)

EQUIPMENT LOCATION: Reactor Building Unit 1 TER QUALIFICATION CATEGORY:

I.8 TER-IDENTIFIED PLANT ID NUMBERS: 21146, 21147, 21148, 21150, 21154, 21155 21156, 21157 CORRECT PLANT ID NUMBERS FOR THIS UNIT: 21146, 21147, 21148, 21150 Note:

Pressure transmitters 21154, 21155, 21156, and 21157 are all used in Unit 2 functions and are included in Equipment Item 46 for Unit 2.

ITEMIZED DEFICIENCIES AND RESPONSES:

1.

Equipment modification required to establish qualification.

RESPONSE

Safety-related equipment accuracies are currently being reviewed and defined as part of the Prairie Island emergency preparedness program. These instrument accuracies will be plant-specific and based on various postulated accident scenarios. Based on the functional requirements of these transmitters, we expect the instrument accuracies experienced in qualification testing to be acceptable. If it is determined that the accuracies experienced in the qualification testing are unacceptable, accident operating procedures will be modified accordingly.

l l

i 1

NORTHERN STATES POWER COMPANY TER Response PRAIRIE ISLAND NUCLEAR GENERATING PLANT July 29, 1983 Page 2.1-47 UNIT NUMBER:

1 TER EQUIPMENT ITEM NUMBER: 47 EQUIPMENT DESCRIPTION:

Rosemount Pressure Transmitter 1153GA9 EQUIPMENT LOCATION: Reactor Building Unit 1 TER QUALIFICATION CATEGORY:

II.B TER-IDENTIFIED PLANT ID NUMBERS:

1-PT-729, 2-PT-729 CORRECT PLANT ID NUMBERS FOR THIS UNIT:

1-PT-729 i

Note:

Presure Transmitter 2-PT-729 is used in Unit 2 functions and is included in Equipment Item 47 for Unit 2.

ITEMIZED DEFICIENCIES AND RESPONSES:

l.

Equipment not qualified.

"We note the following information abstracted from applicable and available 4

qualification documentation associated with the overall NRC equipment envi-ronmental qualification review program:

"I Rosemount testing to qualify a transmitter to meet IEEE 323-1974 require-ments has resulted in failure. A combination of thermal aging, irradia-tion, and chemical spray test specification parameters has resulted in failed components. The initial failed element was an 0-ring comprised of sulphur-cured polyethylene rubber. This allowed steam / chemical spray to affect electronic components. The 0-ring mode of failure is attributed to high temperature vs. time necessary for the Arrhenius curve time compres-sion to satisfy aging test requirements.'

" Based on the above considerations, this equipment item is placed in NRC qualification Category II.B because applicable and available qualification information abstracted from documentation presented to NRC as a result of the overall NRC equipment environmental qualification program reports current Rosemont testing to IEEE-323(74) criteria which resulted in failure of the test specimen."

RESPONSE

This equipment item h A been deleted from the safety-related equipment master-list and no longer requires environmental qualification.

\\

l NORTHERN STATES POWER COMPANY TER Response PRAIRIE ISLAND NUCLEAR GENERATING PLANT July 29, 1983 Page 2.1-48 UNIT NUMBER:

1 TER EQUIPMENT ITEM NUMBER: 48 EQUIPMENT DESCRIPTION: Foxboro Pressure Transmitter Model EllGM(MCA)

EQUIPMENT LOCATION: Auxiliary Building TER QUALIFICATION CATEGORY:

II.A TER-IDENTIFIED PLANT ID NUMBERS: 21203, 21204, 21205, 21209, 21210, 21211 CORRECT PLANT ID NUMBERS FOR THIS UNIT:

21203, 21204, 21205 Note:

Pressure transmitters 21209, 21210, and 21211 are used in Unit 2 functions and are included in Equipment Item 48 for Unit 2.

ITEMIZED DEFICIENCIES AND RESPONSES:

1.

Equipment qualification not established.

A.

Adequate similarity between equipment and test specimen not estab-lished. "The licensee has not stated the output current range of their Foxboro transmitters.

(The tables of note 1 differentiate between 4-20

~

and 10-50 ma models.) Therefore, accuracy tolerances of -12% for the EllGM and -9% for the E13DH must be assumed.

Since the licensee has failed to specify the required accuracy for these transmitters, compli-ance with accuracy criteria is suspect."

RESPONSE

Safety-related equipment accuracies are currently being reviewed and defined as part of the Prairie Island emergency preparedness prcgram. These instrument accuracies will be plant-specific and based on various postulated accident scenarios. Based on the functional requirements of these transmitters, we expect the instrument accuracies experienced in qualification testing to be acceptable.

If it is determined that the accuracies experienced in the qualification testing are unacceptable, accident operating procedures will be modified accordingly.

NORTHERN STATES POWER COMPANY TER Response PRAIRIE ISLAND NUCLEAR GENERATING PLANT July 29, 1983 Page 2.1-49 UNIT NUMBER:

1 TER EQUIPMENT ITEM NUMBER: 49 EQUIPMENT DESCRIPTION: Foxboro Presure Transmitter Model E11GM(MCA)

EQUIPMENT LOCATION: Auxiliary Building TER QUALIFICATION CATEGORY:

II.A TER-IDENTIFIED PLANT ID NUMBERS: 21200, 21201, 21202.

CORRECT PLANT ID NUMBERS FOR THIS UNIT: 21200, 21201, 21202 ITEMIZED DEFICIENCIES AND RESPONSES:

1.

Equipment qualification not established.

A.

Adequate similarity between equipment and test specimen not estab-lished.

"The licensee has not stated the output current range of their Foxboro transmitters.

(The tables of note 1 differentiate between 4-20 and 10-50 ma models.) Therefore, accuracy tolerances of -12% for the E11GM and -9% for the E13DH must be assumed. Since the licensee has failed to specify the required accuracy for these transmitters, compli-ance with accuracy criteria is suspect."

RESPONSE

Safety-related equipment accuracies are currently being reviewed and defined as part of the Prairie Island emergency preparedness program. These instrument accuracies will be plant-specific and based on various postulated accident

. scenarios. Based on the functional requirements of these transmitters, we expect the instrument accuracies experienced in qualification testing to be acceptable.

If it is determined that the accuracies experienced in the qualification testing are unacceptable, accident operating procedures will be modified accordingly.

l l

i

NORTHERN STATES POWER COMPANY TER Response PRAIRIE ISLAND NUCLEAR GENERATING PLANT July 29, 1983 Page 2.1-50 UNIT NUMBER:

1 TER EQUIPMENT ITEM NUMBER: 50 EQUIPMENT DESCRIPTION: Endevco Accelerometer Model 2273AM20 EQUIPMENT LOCATION: Reactor Building Unit 1 TER QUALIFICATION CATEGORY:

I.B TER-IDENTIFIED PLANT ID NUMBERS: None CORRECT PLANT ID NUMBERS FOR THI5 UNIT:

IEQ-443, IEQ-444, IEQ-445 ITEMIZED DEFICIENCIES AND RESPONSES:

1.

Equipment modification required to establish qualification.

RESPONSE

The testing on this component is nearly complete.

If, as a result of testing, modifications to the installed equipment are required, the modifications will be performed during Unit i refuling cycle 9/10 and prior to November 30, 1985.

Once the qualification testing is complete and all necessary modifications have been made, this equipment item will be categorized in Category I.A and will be fully qualified.

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NORTHERN STATES POWER COMPANY TER Response PRAIRIE ISLAND NUCLEAR GENERATING PLANT July 29, 1983 Page 2.1-51 UNIT NUMBER:

1 TER EQUIPMENT ITEM NUMBER: 51 EQUIPMENT DESCRIPTION: Unholtz-Dickey Amplifier Model 22CA-2TR EQUIPMENT LOCATION: Reactor Building Unit 1 TER QUALIFICATION CATEGORY:

I.B TER-IDENTIFIED PLANT ID NUMBERS: None CORRECT PLANT ID NUMBERS FOR THIS UNIT:

IEE-443, IEE-444, IEE-445 ITEMIZED DEFICIENCIES AND RESPONSES:

1.

Equipment modification required to establish qualification.

RESPONSE

The testing on this component is nearly complete.

If, as a result of testing, modifications to the installed equipment are required, the modifications will be performed during Unit I refuling cycle 9/10 and prior to November 30, 1985.

Once the qualification testing is complete and all necessary modifications have been made, this equipment item will be categorized in Category I.A and will be fully qualified.

l i

NORTHERN STATES POWER COMPANY TER Response PRAIRIE ISLAND NUCLEAR GENERATING PLANT July 29, 1983 Page 2.1-52 UNIT NUMBER:

1 TER EQUIPMENT ITEM NUMBER: 52 EQUIPMENT DESCRIPTION: Fisher Controls Signal Converter Model 546 EQUIPMENT LOCATION: Auxiliary Building TER QUALIFICATION CATEGORY:

II.A TER-IDENTIFIED PLANT ID NUMBERS: SC-35085, SC-35028 CORRECT PLANT ID NUMBERS FOR THIS UNIT:

SC-35085, SC-35028 ITEMIZED DEFICIENCIES AND RESPONSES:

1.

Equipment Qualification Not Established.

A.

Documented evidence of qualification not adequate. "In reviewing the licensee's introductory letter to this response dated August 26, 1981, no specific information with respect to this equipment could be located."

RESPONSE

The safety function of this equipment item has been reviewed, and it is con-cluded that it should be removed from the safety-related equipment masterlist.

The April 30, 1982, SER response provided this information.

1 l

NORTHERN STATES POWER COMPANY TER Response PRAIRIE ISLAND NUCLEAR GENERATING PLANT July 29, 1983 Page 2.1-53 UNIT NUMBER:

1 TER EQUIPMENT ITEM NUMBER:

53 EQUIPMENT DESCRIPTION: Trinity Electric Thermometer Model K81 EQUIPMENT LOCATION: Reactor Building Unit 1 TER QUALIFICATION CATEGORY:

1.8 TER-IDENTIFIED PLANT ID NUMBERS:

15456, 15457, 15458, 15459, 15610, 15611 15612, 15613 CORRECT PLANT ID NUMBERS FOR THIS UNIT:

15456, 15457, 15458, 15459 Note:

Thermometers 15610,15611,15612, and 15613 are used in Unit 2 functions an'd are included in equipment item 53 for Unit 2.

ITEMIZED DEFICIENCIES AND RESPONSES:

1.

Equipment modification required to establish qualification.

RESPONSE

Incore thermocouple reference junction boxes have been deleted from the harsh environment safety-related equipment masterlist. A new system utilizing qualified incore thermocouple cable exiting containment through qualified containment penetrations has been installed.

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NORTHERN STATES POWER COMPANY TER Response PRAIRIE ISLAND NUCLEAR GENERATING PLANT July 29, 1983 Page 2.1-54 UNIT NUMBER:

1 TER EQUIPMENT ITEM NUMBER:

54 EQUIPMENT DESCRIPTION: Rosemount RTD Model 176KS EQUIPMENT LOCATION:

Reactor Building Unit i TER QUALIFICATION CATEGORY:

II.A TER-IDENTIFIED PLANT ID NUMBERS:

15314 CORRECT PLANT ID NUMBERS FOR THIS UNIT: None Note:

RTD 15314 is used in Unit 2 functions and 'is included in Equipment Item 54 for Unit 2.

ITEMIZED DEFICIENCIES AND RESPONSES:

Because this equipment item is only used in Unit 2 functions, all identified deficiencies and responses are provided in Equipment Item 54 for Unit 2.

n 0

J NORTHERN STATES POWER COMPANY TER Response PRAIRIE ISLAND NUCLEAR GENERATING PLANT July 29, 1983 Page 2.1-55 UNIT NUMBER:

1 TER EQUIPMENT ITEM NUMBER:

55 EQUIPMENT DESCRIPTION: Sostman RTD Model 11901B EQUIPMENT LOCATION: Reactor Building Unit 1 TER QUALIFICATION CATEGORY:

II.A TER-IDENTIFIED PLANT ID NUMBERS:

15331, 15332, 15333, 15334, 15315, 15322, 15323 CORRECT PLANT ID NUMBERS FOR THIS UNIT:

15331, 15332, 15333, 15334 Note:

RTDs 15315,15322, and 15323 are used in Unit 2 functions and are included in Equip.aent Item 55 for Unit 2.

ITEMIZED DEFICIENCIES AND RESPONSES:

1.

Equipment qualification not established.

A.

Documented evidence of qualification not adequate.

B.

Aging degradation not evaluated adequately.

C.

Qualified life or replacement schedule not established.

D.

Required profile not enveloped adequately.

E.

Criteria regarding spray not adequate.

F.

Criteria regarding functional testing not satisfied.

G.

Criteria regarding instrument accuracy not satisfied.

The detailed evaluation and coments resulting in 'the identification of l

these defiicencies was not provided due to the proprietary nature of the information.

RESPONSE

A detailed evaluation was not provided in the TER due to the proprietary nature of the information, thus a detailed technical response cannot be provided.

Environmental qualification is based on testing described in WCAP 9157.

In essence, environmental qualification is limited by the radiation resistance of the RTD. Based on the functional requiremer.ts and radiation exposure at the installed location, RCS wide range RTDs are qualified for 12 years of normal operation and two weeks of monitoring following a secondary system line break.

Replacement of these RTDs is currently scheduled in 1985 for Unit 1.

On the basis of the testing described above, these RTDs are fully qualified for their intended use until replacement occurs at the end of the 12-year qualified life.

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NORTHERN STATES POWER COMPANY TER' Response PRAIRIE ISLAND NUCLEAR GENERATING PLANT July 29, 1983 Page 2.1-56 UNIT NUMBER:

1 TER EQUIPMENT ITEM NUMBER:

56 EQUIPMENT DESCRIPTION:

Boston Insulated Wire Electrical Control Cable Model Bostrad 7 EQUIPMENT LOCATION:

Reactor Buildinj Unit 1 and Auxiliary Building TER QUALIFICATION CATEGORY:

II.A TER-IDENTIFIED PLANT ID NUMBERS: None CORRECT PLANT ID NUMBERS FOR THIS UNIT: None ITEMIZED DEFICIENCIES AND RESPONSES:

1.

Equipment qualification not established.

A.

Documented evidence of qualification not established.

B.

Criteria regarding submergence not satisfied. "The licensee SCEW sheet indicates that the cables can become submerged and states that an accelerated water absorption test qualifies the cable for submergence.

The water absorption tests demonstrate suitability for demineralized water at atmospheric pressure, but do not simulate the pressure, temperature, chemistry, and radiation conditions of the liquid in the containment sump after LOCA."

RESPONSE

Several tests have been performed on BIW cable: to evaluate their ability to operate in a submerged condition. The tests fallow the outline of IEEE 383-1974 which specifically states that voltage withstand tests be performed on cables submerged in tap water.

BIW cable was immersed in tap water at 75'C (167'F) for 14 days with no deleterious effects.

In addition to water absorp-tion tests, the cables were exposed to oil immersion aging at 121*C (250*F) and boric acid aging of irradiated samples in varying pH solutions was performed with no noted anomalies. Cable samples were also exposed to a 7 day LOCA test with high temperatures, high pressures,100% RH, and a boric acid / sodium hydroxide ch'emical solution. The combination of these tests far exceeds the tests necessary to show submergence qualifiation.

In general, the combination of LOCA testing and water absorption testing of immersed samples adequately simulates the postulated accident environment to document submergence quali-fication in accordance with IEEE 383-1974.

NORTHERN STATES POWER C0WANY TER Response PRAIRIE ISLAND NUCLEAR GENERATING PLANT July 29, 1983 Page 2.1-57a UNIT NUMBER:

1 57 TER EQUIPMENT ITEM NUMBER:

EQUIPMENT DESCRIPTION: Kerite Electrical Control Cable Models FR/FR and HTK/FR EQUIPMENT LOCATION: Reactor Building Unit 1 and Auxiliary Building TER QUALIFICATION CATEGORY:

II.A TER-IDENTIFIED PLANT ID NUMBERS: None CORRECT PLANT ID NUMBERS FOR THIS UNIT: None ITEMIZED DEFICIENCIES AND RESPONSES:

1.

Equipment qualification not established.

A.

Adequate similarity between equipment and test specimen not established.

B.

Aging degradation not evaluated adequately.

C.

Qualified life or replacement schedule not established.

D.

Criteria regarding spray satisfied.

The detailed evaluation and comments resulting in the identification of these deficiencies was not provided due to the proprietary nature of the information.

RESPONSE

Because a detailed evaluation was not provided in the TER due to the proprie-tary nature of the information, a detailed technical response cannot be provided.

Three types of Kerite cable are used in safety-related applications at Prairie Island: HT-Kerite/FR, FR/FR, and HT-Kerite/HTNS. Each of these cables have been evaluated and their environmental qualification is documented in [1].

Correspondence with the equipment vendor, Kerite, has resulted in obtaining the applicable qualification reports for each cable type [2]. Aging qualification is based on aging tests performed on cable samples correlated to the Prairie Island environment using the Arrhenius methodology. The results of this evalu-ation show that the cables are qualified for greater than 40 years of service with no replacement required. Chemical spray qualification has been estab-lished based on type testing to chemical solutions simulating the Prairie Island containment spray solution.

l

. e NORTHERN STATES POWER COMPANY TER Response PRAIRIE ISLAND NUCLEAR GENERATING PLANT July 29, 1983 Page 2.1-57b ITEMIZED DEFICIENCIES AND RESPONSES (Cont.):

Based on the environmental evaluation summarized above, all identified defi-ciencies have been adequately resolved. Kerite electrical cable is therefore categorized in Category I.A and is fully qualified.

EQUIPMENT ITEM SPECIFIC

REFERENCES:

1.

EDS Calculation File 0910-205-KER-01, Revision 1

" Environmental Qualifica-tion of Kerite Electrical Cables," December 8, 1981.

2.

Kerite Company letter from the office of E. N. Sleight to Terry M. Maxey, EDS Nuclear, December 8, 1981.

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NORTHERN STATES POWER COW ANY TER Response PRAIRIE ISLAND NUCLEAR GENERATING PLANT July 29, 1983 Page 2.1-58 l

UNIT NUMBER:

1 4

TER EQUIPMENT ITEM NUMBER:

58 EQUIPMENT DESCRIPTION:

Okonite Electrical Cable Model Okonite/ Neoprene EQUIPMENT LOCATION: Reactor Building Unit 1 and Auxiliary Building TER QUALIFICATION CATEGORY:

II.A TER-IDENTIFIED PLANT ID NUMBERS: None CORRECT PLANT ID NUMBERS FOR THIS UNIT: None ITEMIZED DEFICIENCIES AND RESPONSES:

1.

Equipment qualification not estcblished.

A.

Criteria regarding submergence not satisfied.

"The licensee has pro-vided documentation which references several Okonite test reports and laboratory test reports for the cable which would establish qualifica-tion for the cable in the Auxiliary Building but does not provide qualification for submergence in containment"...

"The water absorption tests demonstrate suitability for demineralized water at atmospheric pressure, but do not simulate the pressure, temperature, chemistry, and radiation conditions of the liquid in the containment sump after LOCA.

RESPONSE

Submergence qualification of Okonite cables is based on sequential-type testin which included high temperature, high pressure, 100% RH, chemical spray simulag l

tion, irradiation, and submergence testing. These tests were performed follow-ing the guidelines of IEEE 383-1974. While it is true that water absorption testing alone does not simulate the post-LOCA environment in the containment sump, the combination of tests described above does simulate this environment.

The accelerated water absorption test after the LOCA testing was of sufficient duration, in excess of 18 months at 90*C (194*F), to provide adequate margin for submergence qualification.

On the basis of the environmental evaluation performed and for which the sub-mergence qualifiation is summarized above, all deficiencies have been ade-i quately resolved and this equipment item is fully qualified. Okonite cables are therefore categorized in Category I.A.

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i

.o NORTHERN STATES POWER COMPANY TER Response PRAIRIE ISLAND NUCLEAR GENERATING PLANT July 29, 1983 Page 2.1-59a UNIT NUMBER:

1 TER EQUIPMENT ITEM NUMBER:

59 EQUIPMENT DESCRIPTION: Okonite Electrical Cable Splice Model 604-92-1571 EQUIFMENT LOCATION: Reactor Building Unit 1 and Auxiliary Building TER QUALIFICATION CATEGORY:

II.A TER-IDENTIFIED PLANT ID NUMBERS: None CORRECT PLANT ID NUMBERS FOR THIS UNIT: None ITEMIZED DEFICIENCIES AND RESPONSES:

1.

Equipment qualification not established.

A.

Adequate similarity between equipment and test specimen not estab-l lished. "The letters reproduced on page 5a are not certification that the test report applies."

8.

Aging degradation not evaluated adequately.

C.

Qualified life or replacement schedule not established.

D.

Criteria regarding submergence not satisfied. "The licensee's SCEW sheet indicates that the cables can become submerged and states that an accelerated water absorption test qualifies the cable for submergence.

The water absorption test demonstrates sutiability for demineralized water at atmospheric pressure, but does not simulate the pressure, temperature, chemistry, and radiation conditions of the liquid in the containment sump after LOCA."

RESPONSE

Correspondence with the equipment vendor [1] resulted both in the identifica-tion of the materials used in the splice and the procurement of the applicable qualification test [2]. Utilizing this test data, the environmental qualifica-tion of the splice was documented [3]. Thermal aging qualification is based on pre-aging performed on the test specimens correlated to the Prairie Island environment utilizing the Arrhenius methodology.

As a result of the thermal aging evaluation, this equipment item is qualified for an excess of 40 years service with no requirements for replacement. Sub-4 mergence qualification is based on immersion testing in water following acci-dent testing (which included chemical spray exposure). This test sequence and method does follow the qualification requirements outlined in IEEE 383-1974.

While it is true that water absorption testing alone does not simulate the post-LOCA environment in the containment sump, the combination of tests described above does simulate this environment.

= -

NORTHERN STATES POWER COMPANY TER Response PRAIRIE ISLAND NUCLEAR GENERATING ^ PLANT July 29, 1983

)

Page 2.1-59b ITEMIZED DEFICIENCIES AND RESPONSES (Cont.):

On the basis of the environmental evaluation performed and summarized above, all deficiencies have been adequately resolved and this equipment item is fully qualified. Okonite splice kit 604-92-1571 is therefore categorized in Category I.A.

EQUIPMENT ITEM SPECIFIC

REFERENCES:

1.

Record of conversation between Mr. J. Rodgers (0konite) and Mr. W. Fargo (EDS) dated August 18, 31, and September 11, 1981.

2.

LOCA Qualification Report for Okoguard Insulating Cables and T-95 and T-35 Splicing Tapes, Okonite Report NQRN-3, June 23, 1980.

3.

EDS Calculation File 0910-205-0K0-02, Revision 0, " Environmental Qualifi-cation of Okonite Splices," December 1981.

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f NORTHERN STATES POWER COMPANY TER Response

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PRAIRIE ISLAND NUCLEAR GENERATING PLANT July 29, 19,83.

Page 2.1-60 UNIT NUMBER:

1 TER EQUIPMENT ITEM NUMBER:

60 EQUIPMENT DESCRIPTION: Allen Bradley Terminal Strips Model 1492-CD3 c EQUIPMENT LOCATION: Reactor Building Unit l'and Auxiliary Building' TER QUALIFICATION CATEGORY:

I.B TER-IDENTIFIED PLANT ID NUMBERS: None CORRECT PLANT ID NUMBERS FOR THIS UNIT:

None ITEMIZED DEFICIENCIES AND RESPONSES:

1.

Equipment modification required to establish qualification.

RESPONSE

Environmental qualification testing is still in progress. Assuming succ'essful, completion of the testing, this equipment item will be categorized in Ca'tegory I.A and will be completely qualified.

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.v NORTHERN STATES ~ POWER COMPANYs TER Response PRAIRIE ISLAND NUCLEAR GENERATING PLANT July 29, 1983 Page 2.1-61 p

D UNIT' NUMBER:

1 TER EQUIPMENT ITEM NUMBER:

61 EQUIPMENT DESCRIPTION: General Electric' Epoxy Model 7010/74010A EQUIPMENT' LOCATION: Reactor Building Unit 1 and Auxiliary Building TER QUALIFICATION CATEGORY:

I.B TER-IDENTIFIED PLANT ID NUMBERS:

None i

~ ' CORRECT PLANT.ID NUMBERS FOR THIS UNIT: None

+

ITEMIZED DEFICIENCIES ND RESPONSES:

1.

Equipment modification-required to establish qualification.

RESPONSE

This equipment item is used in conjunction with Equipment Item 60, Allen 2-Bradley terminal strips, for which environ ~ mental qualification testing is still i

in progress.-Assuming successful completion of the testing, this equipment item

'will be categorized in Category I.A and will be fully qualified.

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NORTHERN STATES PedER COMPANY TER Response PRAIRIItISLAND NUCLEAR GENERATING PLANT July 29, 1983 Page 2.1-62 UNIT NUMBER:

1 TER EQUIPMEKT ITEM NUMBER:

62 EQUIPMENT DESCRIPTION: Chevron SRI-2 Lubricant EQUIPMENT LOCATION: Reactor Building Unit 1 TER QUALIFICATION CATEGORY: 1.A TER-IDENTIFIED PLANT ID NUMBERS: None i

CORRECT PLANT ID NUMBERS FOR THIS UNIT: None i

ITEMIZED DEFICIENCIES AND RESPONSES:

There are no deficiencies identified in the environmental qualification of this equipment item.

C l

6 NORTHERN STATES POWER COMPANY TER Response PRAIRIE ISLAND NUCLEAR GENERATING PLANT July 29, 1983 Pagc 2.1-63 UNIT NUMBER:

1 TER EQUIPMENT ITEM NUMBER: 63 EQUIPMENT DESCRIPTION: Mobile DTE Lubricant EQUIPMENT LOCATION: Auxiliary Building TER QUALIFICATION CATEGORY:

1.A TER-IDENTIFIED PLANT ID NUMBERS: None CORRECT PLANT 10 NUMBERS FOR THIS UNIT: None ITEMIZED DEFICIENCIES AND RESPONSES:

There are no deficiencies identified in the environmental qualification of this equipment item.

)

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1 NORTHERN ' STATES POWER COMPANY TER Response PRAIRIE ISLAND NUCLEAR GENERATING PLANT July 29, 1983 i

Page 2.1-64 i

a l

UNIT NUMBER:

1 1

TER EQUIPMENT ITEM NUMBER: 64 l

EQUIPMENT DESCRIPTION: Bussman Fuseholder.Model HEBA 1

EQUIPMENT LOCATION: Auxiliary Building TER QUALIFICATION CATEGORY:

II.A TER-IDENTIFIED PLANT ID NUMBERS:

None CORRECT PLANT ID NUMBERS FOR THIS UNIT: None i

ITEMIZED DEFICIENCIES AND RESPONSES:

i 1.

Equipment qualification not established.

A.

Criteria regarding steam exposure not adequate.

"An oven aging test i

does not provide qualification for steam exposure."

RESPONSE

Bussman HEB-A fuseholders are waterproof fuseholders which completely encapsu-late the fuse and protect it against damage from water, weather, salt spray, corrosive fumes, and the like. Correspondence with the equipment vendor indicates that the HEB-A fuseholders have been qualified for innersion in accordance with military specification MIL-STD-2020, April 14, 1969. More specifically, this test consists of 5 cycles of 60-minute immersions in a hot bath of tap water at 65'C, followed by 60-minute immersions in a saturated 4

solution of sodium chloride and water at 0*C.

The test sample successfully passed this innersion testing. The waterproof fuseholders are enclosed in NEMA-4 boxes, which provide further protection against the effects of moisture.

0 On the basis of the testing performed and installation of NEMA-4 enclosures, there is adequate assurance of qualification to relative humidity conditions.

l This equipment item is therefore categorized in Cateagory I.A and is fully qualified.

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b NORTHERN STATES POWER COMPANY TER Response PRAIRIE ISLAND NUCLEAR GENERATING PLANT July 29, 1983 i

Page 2.1-65 UNIT NUMBER:

1 TER EQUIPMENT ITEM NUMBER:

65 EQUIPMENT DESCRIPTION: General Electric Motor Control Center Model 7700 Series EQUIPMENT LOCATION: Auxiliary Building TER QUALIFICATION CATEGORY:

I.B TER-IDENTIFIED PLANT ID NUMBERS:

lLA1, ILA2, 2LAl, 2LA2, IM1, IMA2 CORRECT PLANT ID NUMBERS FOR THIS UNIT:

1LAl, 2LA1, IM1 Note:

Motor Control Centers ILA2, 2LA2 and 1MA2 are all used in Unit 2 functions and are included in Equipment Item 65 for Unit 2.

ITEMIZED DEFICIENCIES AND RESPONSES:

1.

Equipment modification required to establisn qualification.

RESPONSE

New motor control centers have been ordered and will be used to relocate required safety-related loads to a mild environment.

Installation will be completed during Unit 1 Cycle 9 and prior to November 30, 1985. Once this has occurred, this item will no longer be on the harsh environment safety-related equipment masterlist.

NORTHERN STATES POWER COMPANY TER Response PRAIRIE ISLAND NUCLEAR GENERATING PLANT July 29, 1983 Page 2.1-66 UNIT NUMBER:

1 TER EQUIPMENT ITEM NUMBER: 66 EQUIPMENT DESCRIPTION:

Creiger Electrical DC Distribution Panel EQUIPMENT LOCATION: Reactor Building Unit 1 TER QUALIFICATION CATEGORY:

I.B TER-IDENTIFIED PLANT ID NUMBERS: None CORRECT PLANT ID NUMBERS FOR THIS UNIT: Panel 153, 163 Note:

All safety-related loads from these panels have been relocated to Panels 153 and 163.

ITEMIZED DEFICIENCIES AND RESPONSES:

1.

Equipment modification required to establish qualification.

RESPONSE

All safety-related loads to these panels have been relocated to distribution panels installed in the auxiliary building. Therefore, this equipment item has l

been deleted from the safety-related equipment masterlist. Distribution panels located in the auxiliary building have been added to the safety-related equip-ment masterlist, and environmental qualification for these panels is nearing completion.

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NORTHERN STATES POWER COWANY TER Response PRAIRIE ISLAND NUCLEAR GENERATING PLANT July 29, 1983 Page 2.1-67 UNIT NUMBER:

1 TER EQUIPMENT ITEM NUMBER:

67 EQUIPMENT DESCRIPTION: Barton Flow Switch Model 288A EQUIPMENT LOCATION: Auxiliary Building TER QUALIFICATION CATEGORY:

II.C TER-IDENTIFIED PLANT ID NUMBERS:

18252, 18253, 18268, 18269 CORRECT PLANT ID NUMBERS FOR THIS UNIT:

18252, 18253 Note:

Flow switches 18268 and 18269 are used in Unit 2 functions and are included in Equipment Item 67 for Unit 2.

ITEMIZED DEFICIENCIES AND RESPONSES:

1.

Equipment satisifes all requirements except qualified life or replacement schedule justified.

A.

Aging degradation not evaluated adequately.

B.

Qualified life or replacement schedule not established. "The licensee has provided PGR 3252 as evidence of qualification for this equipment item. This test report envelopes the plant-specific conditions for the expected radiation environment. The licensee has not, however, iden-tified the materials of construction or evaluated the effects of aging on the device."

RESPONSE

A project was initiated to thoroughly evaluate the qualified life of Barton Model 288A flow switches, based on the aging degradation properties of the constituent materials. This evaluation is documented in [1]. The results show that these flow switches have a qualified life in excess of 40 years at the installed location in the Prairie Island auxiliary building. The completion of this thermal aging evaluation addresses the deficiencies cited above. This equipment item is now categorized in Category I.A and is fully qualified.

EQUIPMENT ITEM SPECIFIC

REFERENCES:

1.

Impell Calculation File 0910-200-BAR-01, "Barton 288A Thermal Aging Evaluation," July 1983.

NORTHERN STATES POWER COMPANY TER Response PRAIRIE ISLAND NUCLEAR GENERATING PLANT July 29, 1983 Page 2.1-68 UNIT NUMBER:

1 TER EQUIPMENT ITEM NUMBER:

68 EQUIPMENT DESCRIPTION:

D. G. O'Brien Electrical Penetration Model PR-2(TI)

EQUIPMENT LOCATION: Reactor Building Unit 1 TER QUALIFICATION CATEGORY:

I.A TER-IDENTIFIED PLANI ID NUMSERS: hone CORRECT PLANT ID NUMBERS FOR THIS UNIT: hone ITEMIZED DEFICIENCIES AND RESPONSES:

There are no deficiencies identified in th6 erwironmental qualifiestion of this equipment item.

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NORTHERN STATES POWER COMPANY TER Response PRAIRIE ISLAND NUCLEAR GENERATING PLANT July 29, 1983 Page 2.1-69 UNIT NUMBER:

1 TER EQUIPMENT ITEM NUMBER: 69 EQUIPMENT DESCRIPTION:

D. G. O'Brien Electrical Penetration Model PR-12(LYP)

EQUIPMENT LOCATION: Reactor Building Unit 1 TER QUALIFICATION CATEGORY:

1.A TER-IDENTIFIED PLANT ID NUM8ERS: None CORRECT PLANT 10 NUMBERS FOR THIS UNIT:

None ITEM 1 ZED DEFICIENCIES AND RESPONSES:

There are no deficiencies identified in the environmental qualification of this equipmer.t item.

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. o NORTHERN STATES POWER COMPANY TER Response PRAIRIE ISLAND NUCLEAR GENERATING PLANT July 29, 1983 Page 2.1-70 UNIT NUMBER:

1 TER EQUIPMENT ITEM NUMBER:

70 EQUIPMENT DESCRIPTION:

D. G, O'Brien Electrical Penetration Model PR-110(MVP)

EQUIPMENT LOCATION: Reactor Building Unit 1 TER QUALIFICATION CATEGORY:

I.A TER-IDENTIFIED PLANT ID NUMBERS: None CORRECT PLANT ID NUMBERS FOR THIS UNIT:

None ITEMIZED DEFICIENCIES AND RESPONSES:

There are no deficiencies identified in the environmental qualification of tnis equipment item.

. a NORTHERN STATES POWER COMPANY TER Response PRAIRIE ISLAND NUCLEAR GENERATING PLANT July 29, 1983

)

Page 2.1-71 UNIT NUMBER:

1 TER EQUIPMENT ITEM NUMBER:

71 EQUIPMENT DESCRIPTION: Kerite Electrical Cable Splice D51001/051002 EQUIPMENT LOCATION: Reactor Building Unit 1 and Auxiliary Building TER QUALIFICATION CATEGORY:

II.A TER-IDENTIFIED PLANT ID NUMBERS:

None CORRECT PLANT ID NUMSERS FOR THIS UNIT: None ITEMIZED DEFICIENCIES AND RESPONSES:,

1.

Equipment oualification not established.

A.

Adequate similarity between equipment and test specimen not estab-lished. "In lieu of the detailed description discussed above it would be acceptable for the licensee to obtain certification from the manu-Tacturer identifying what test report (s) apply the the cables furnished for installation.

If applicability is established the splice would be qualified."

RESPONSE

The equipment manufacturer, Kerite, was contacted prior to initiating the envi-ronmental qualification evaluation of Kerite splices DS-1001 and DS-1002. The result of this correspondence [1] was the identification and procurement of the applicable qualification test [2]. This confirmation of test report applica-bility by the equipment manufacturer satisfies the certification requirement described in the TER deficiency. Therefore, this equipment item is fully qualified and is categorized in Category I.A.

EQUIPMENT ITEM SPECIFIC REFERENCES-l 1.

Kerite Company letter from the office of Mr. E. N. Sleight to Mr. T. M.

Maxey (EDS Nuclear) dated November 4, 1981.

2.

Tests of Electrical Cables Under Simultaneous Exposure to Gamma Radiation, Steam, and Chemical Spray while Electrically Energized," FIRL Final Report F-C4020-2, March 1975.

NORTHERN STATES POWER C0W ANY TER Response PRAIRIE ISLAND NUCLEAR GENERATING PLANT July 29, 1983 Page 2.1-72a a

UNIT NUMBER:

1 TER EQUIPMENT ITEM NUMBER:

72 EQUIPMENT DESCRIPTION: 0xonite Electrical Splicing Tape Model T95 EQUIPMENT LOCATION: Reactor Building Unit I and Auxiliary Building TER QUALIFICATION CATEGORY:

II.A TER-IDENTIFIED PLANT ID NUMBERS: None CORRECT PLANT ID NUMBERS FOR THIS UNIT: Nons 4

ITEMIZED DEFICIENCIES AND RESPONSES:

1.

Equipment qualification not establish 6d.

A.

Criteria regarding submergence not satisfied.

"The test report also contains a description of water absorption tests. However., the accelerated water absorption testing in deminaralized water at atmospheric pressure does not simulate or qualify the equipment for the pressure, temperature, radiation and chemistry of the liquid in the containment sump after a LOCA."

RESPONSE

Okonite electrical cable splicing tapes T-95 and T-35 are integral components in the Okonite splice kit model 604-92-1571 (Equipment Item 59). The environ-mental qualification testing on the 604-92-1571 splice kit included testing on the T-95 and T-35 splicing tapes [1] and is directly applicable to the installed splices at Prairie Island as documented in [2]. Submergence quali-

~

l fication is based on innersion testing in water following accident testing (which included chemical spray exposure). This test sequence and method does follow the qualification requirements outlined in IEEE 383-1974. While it's true that water absorption testing alone does not simulate the post-LOCA environment in the containment sump, the combination of tests described above does simulate this environment.

On the basis of the environmental evaluation performed [3] and summarized above, all deficiencies have been adequately resolved and this equipment item is fully qualified. Okonite splicing tapes T-95 and T-35, contained in splicing l

kit 604-92-1571, are fully qualified. This equipment item is therefore cate-gerized in Category I.A.

l

NORTHERN STATES POWER COMPANY TER Response PRAIRIE ISLAND NUCLEAR GENERATING PLANT July 29, 1983 Page 2.1-72b ITEMIZED DEFICIENCIES AND RESP 0'NSES (Cont.):

EQUIPMENT ITEM SPECIFIC

REFERENCES:

1.

LOCA Qualification Report for Okoguard Insulating Cables and T-95 and T-35 Splicing Tapes, Okonite Report NQRN-3, June 23, i980.

2.

Record of Conversation between Mr. J. Rodgers (0konite) and Mr. W. Fa.go (EDS) dated August 18, 31, and September 11, 1951, 3.

EDS Calculation File 0910-205-0KO-2, Revision 0, " Environmental Qualifi-cation of Okonite Splices," December 1981.

NORTHERN STATES POWER COMPANY TER Response PRAIRIE ISLAND NUCLEAR GENERATING PLANT July 29, 1983 Page 2.1-73a UNIT NUMBER:

1 TER EQUIPMENT ITEM NUMBER:

73 EQUIPMENT DESCRIPTION: Okonite Electrical Cable Splice Model T35 EQUIPMENT LOCATION: Reactor Building Unit 1 and Auxiliary Building TER QUALIFICATION CATEGORY:

II.A TER-IDENTIFIED PLANT ID NUMBERS: None CORRECT PLANT ID NUMBERS FOR THIS UNIT: None ITEMIZED DEFICIENCIES AND RESPONSES:

1.

Equipe.ent qualification not established.

A.

Criteria regarding submergence not established.

"The test report also contains a description of rater absorption tests. However, the accelerated water absorption testing in demineralized water at atmospheric pressure does not simulate or qualify the equipment for pressure, temperature, radiation and chemistry of the liquid in the containment sump after LOCA."

RESPONSE

Okonite electrical cable splicing tapes T-95 and T-35 are integral components in the Okonite splice kit model 604-92-1571 (Equipment Item 59). The environ-

[

mental qualification testing on the 604-92-1571 splice kit included testing on the T-95 and T-35 splicing tapes [1] and is directly [ applicable to the I

installed splices at Prairie Island as documented in 2]. Submergence qualification is based on immersion testing in water following accident testing l

(which included chemical spray exposure). This test sequence and method does follow the qualification requirements outlined in IEEE 383-1974. While it's l

true that water absorption testing alone does not simulate the post-LOCA i

environment in the containment sump, the combination of tests described above does simulate this environment.

On the basis of the environmental evaluation performed [3] and summarized above, all deficiencies have been adequately resolved and this equipment item is fully qualified. Okonite splicing tapes T-95 and T-35, contained in splicing kit 604-92-1571, are fully qualified. This equipment item is therefore cate-gorized in Category I.A.

l

NORTHERN STATES POWER COMPANY TER Response PRAIRIE ISLAND NUCLEAR GENERATING PLANT July 29, 1983 Page 2.1-73b ITEMIZED DEFICIENCIES AND RESPONSES (Cont.):

EQUIPMENT ITEM SPECIFIC

REFERENCES:

1.

LOCA Qualification Report for Okoguard Insulating Cables and T-95 and T-35 Splicing Tapes, Okonite P.eport NQRN-3, June 23, 1980.

2.

Record of Conversation between Mr. J. Rodgers (Okonite) and Mr. W. Fargo (EDS) dated August 18, 31, sad September 11, 1981.

3.

EDS Calculation File 0910-205-0KO-2, Revision 0, " Environmental Qualift-cation of Okenite Splica:," December 1981.

l l

NORTHERN STATES POWER COMPANY TER Response PRAIRIE ISLAND NUCLEAR GENERATING PLANT July 29, 1983 Page 2.1-74 UNIT NUMBER:

1 TER EQUIPMENT ITEM NUMBER:

74 EQUIPMENT DESCRIPTION: Limitorque Motorized Valve Actuator.Model SMB-00 EQUIPMENT LOCATION: Auxiliary Building TER QUALIFICATION CATEGOP.Y:

II.A TER-IDENTIFIED PLANT ID liUM6ERS: MV-32016, MV-32017, MV-32019, MV-32020 CORRECT PLANT ID NUMBERS FOR THIS UNIT: MV-32016, MV-32017 Note:

Valve actuat. ors MV-32019 and MV-32020 are used in Unit 2 functions and are included in Equipment item 74 for Unit 2.

ITEMIZED DEFICIENCIES AND RESPONSES:

1.

Equipment qualification not established.

A.

Adequate similarity between equipment and test specimen not established.

B.

Aging degradation not evaluated adequately.

C.

Qualified life or replacement schedule not established.

Several pages of detailed notes were provided in the TER pertaining to deficiencies in the environmental qualification of this equipment item.

RESPONSE

A project has been initiated to thoroughly evaluate and document the envi-ronmental qualification of Limitorque valve actuators. Eacn of the concerns raised in.the TER will be addressed in that evaluation. We expect that the evaluation will be finalized by January 1,1984, and that any necessary modi-fications or replacements will be performed ptfor to November 30, 1985.

,6 l

NORTHERN STATES POWER COPFANY TER Response PRAIRIE ISLAND NUCLEAR GENERATING PLANT July 29, 1983 Page 2.2-1 UNIT NUMBER: 2 TER EQUIPMENT ITEM NUMBER:

1 EQUIPMENT DESCRIPTION: Limitorque Motorized Valve Actuator Model SMB-00 EQUIPMENT LOCATION: Reactor Building Unit 2 TER QUALIFICATION CATEGORY:

II.A TER-IDENTIFIED PLANT ID NUMBERS: MV-32199, MV-32210 CORRECT PLANT ID NUMBERS FOR THIS UNIT: MV-32210 Note:

Valve actuator FN-32199 is used in Unit 1 functions and is included in Equipment Item 1 for Unit 1.

ITEMIZED DEFICIENCIES AND RESPONSES:

1.

Equipment qualification not established.

A.

Adequate similarity between equipment and test specimen not established.

B.

Aging degradation not evaluated adequately.

C.

Qualified life or replacement schedule not established.

Several pages of detailed notes were provided in the TER pertaining to deficiencies in the environmental qualification of this equipment item.

RESPONSE

A project has been initiated to thoroughly evaluate and document the environ-mental qualification of Limitorque valve actuators. Each of the concerns raised in the TER will be addressed in that evaluation. We expect that the evaluation will be finalized by January 1,1984, and that any necessary modifications or replacements will be performed prior to November 30, 1985.

NORTHERN STATES POWER COMPANY TER Response PRAIRIE ISLAND NUCLEAR GENERATING PLANT July 29, 1983 Page 2.2-2 UNIT NUMBER: 2 TER EQUIPMENT ITEM NUMBER: 2 EQUIPMENT DESCRIPTION: Limitorque Motorized Valve Actuator Model SMB-3 EQUIPMENT LOCATION: Reactor Building Unit 2 TER QUALIFICATION CATEGORY:

III.A TER-IDENTIFIED PLANT ID NUMBERS:

MV-32174, MV-32175 CORRECT PLANT ID NUMBERS FOR THIS UNIT: MV-32174, MV-32175 ITEMIZE 0 DEFICIENCIES AND RESPONSES:

These valvo actuatcrs &re in a locked-open position with power removed and cannot, therefore, change position. This equipment item is exempt from quali-fication and has been re,moveo from the safety-related equipment masterlist.

i o.

NORTHERN STATES POWER COWANY TER Response PRAIRIE ISLAND NUCLEAR GENERATING PLANT July 29, 1983 Page 2.2-3 UNIT NUMBER: 2 TER EQUIPMENT ITEM NUMBER: 3 EQUIPMENT DESCRIPTION: Limitorque Motorized Valve Actuator Model SMB-00 EQUIPMENT LOCATION: Reactor Building Unit 2 TER CUALIFICATION CATEGORY:

II.A TER-IDENTIFIED PLANT ID NUMBERS: MV-32132, MV-32135, MV-32138, MV-32141, MV-32043, MV-32040, MV-32046, MV-32049 CORRECT PLANT ID NUMBERS FOR THIS UNIT: MV-32046, MV-32049 Note:

Valve actuators MV-32132, MV-321235, M7-32138, MV-32141, MV-32043, and MV-32040 aro used in Unit i functions and are included in Equipr.1ent Item 3 for Unit 1.

ITEMIZED DEFICIENCIES AND RE5F0fiSES:

1.

Equipment qualification not established.

A.

Adequate similarity betwee:: equipment and test specimen not established.

B.

Aging degradation not evaluated adequately.

C.

Qualified life or replacement schedule not established.

Several pages of detailed notes were provided in the TER pertaining to deficiencies in the environmental qualification of this equipment item.

RESPONSE

A project has been initiated to thoroughly evaluate and document the environ-mental qualification of Limitorque valve actuators. Each of the concerns raised in the TER will be addressed in that evaluation. We expect that the evaluation will be finalized by January 1, 1984, and that any necessary modifications or replacements will be performed prior to November 30, 1985.

+u-.

w + = e em.

J NORTHERN STATES POWER COMPANY TER Response PRAIRIE ISLAND NUCLEAR GENERATING PLANT July 29, 1983 Page 2.2-4 UNIT NUMBER: 2 4

TER EQUIPMENT ITEM NUMBER:

EQUIPMENT DESCRIPTION: Limitorque Motorized Valve Actuator Model SMB-1 EQUIPMENT LOCATION: Reactor Building Unit 2 TER QUALIFICATION CATEGORY:

II.A TER-IDENTIFIED PLANT ID NUMBERS: MV-32167, MV-32168, MV-32064, MV-32065 CORRECT PLANT ID NUMBERS FOR THIS UNIT: MV-32167, MV-32168 Note:

Valte actuators MV-32064 and MV-32065 are used in Unit 1 functions and are included in Equipment Item 4 for Unit 1.

ITEMIZED DEFICIENCIES AtlD RESPONSES:

1.

Equipment qualification not established.

A.

Adequate similarity between equipment and test spaciraen not established.

8.

nging degradation not evaluated adequately.

C.

Qualified life or replacement schedule not established.

Several pages of detailed notes were provided in the TER pertaining to deficiencies in the environmental qualification of this equipment item.

RESPONSE

A project has been initiated to thoroughly evaluate and document the environ-nmental qualification of Limitorque valve actuators. Each of the concerns raised in the TER will be addressed in that evaluation. We expect that the evaluation will be finalized by January 1, 1984, and that any necessary modifications or replacements will be performed prior to November 30, 1985.

_. _ _ _.. _,. _ _ ~, _. _

1 NORTHERN STATES POWER COMPANY TER Response PRAIRIE ISLAND NUCLEAR GENERATING PLANT July 29, 1983 Page 2.2-5 UNIT NUMBER: 2 TER EQUIPMENT ITEM NUMBER:

5 EQUIPMENT DESCRIPTION:

Limitorque Motorized Valve Actuator Model SMB-00 EQUIPMENT LOCATION: Reactor Building Unit 2 TER QUALIFICATION CATEGORY:

II.A TER-IDENTIFIED PLANT ID NUMBERS: MV-32170, MV-32067,

CORRECT PLANT 10 NUMBERS FOR THIS UNIT: MV-32170 Note:

Valve actuator HV-32067 is used in Unit 1 functions and is included in Equipment Item 5 for Unit 1.

ITEMIZED DEFICIENCIES AND RESPONSES:

1.

Equipment qualification not establisnad.

A.

Adequate similarity between equipment and test specimen not established.

B.

Aging degradation not evaluated adequately.

C.

Qualifieo life or replacement schedule not established.

Several pages of detailed notes were provided in the TER pertaining to deficiencies in the environmental qualification of this equipment item.

RESPONSE

A project has been initiated to thoroughly evaluate and occument the environ-mental qualification of Limitorque valve actuators. Each of the concerns raised in the TER will be addressed in that evaluation. We expect that the evaluation will be finalized by January 1,1984, and that any necessary modifications or replacements will be performeo prior to November 30, 1985.

p r-

i

. o NORTHERN STATES POWER COMPANY TER Response PRAIRIE ISLAND NUCLEAR GENERATING PLANT July 29, 1983 Page 2.2-6 UNIT NUMBER: 2 TER EQUIPMENT ITEM NUMBER:

6 EQUIPMENT DESCRIPTION: Limitorque Motorized Valve Actuator Models SMB-00 and SMB-000 EQUIPMENT LOCATION:

Reactor Building Unit 2 TER QUALIFICATION CATEGORY:

II..A TER-IDENTIFIED PLANT 10 NUMBERS: MV-32069, MV-32271, MV-32273, MV-32290, MV-32292 CORRECT PLANT ID NUMBERS FOR THIS UNIT: MV-32290, MV-32292 Note:

Valve actuators MV-32069, MV-32271 and MV-32273 are used in Unit i functions and are included in Equipment Item 6 for Unit 1.

ITEMIZF0 DEFICIENCIES AND RESPONSES:

1.

Equipment qualification not Established.

A.

Adequate similarity between equipreent and test specimen not established.

B.

Aging degradation not evaluated adequately.

C.

Qualified life or replacement schedule not established.

Several pages of detailed notes were provided in the TER pertaining to deficiencies in the environmental qualification of this equipment item.

RESPONSE

A project has been initiated to thoroughly evaluate and document the environ-mental qualification of Limitorque valve actuators. Each of the concerns raised in the TER will be addressed in that evaluation. We expect that the evaluation will be finalized by January 1,1984, and that any necessary modifications or replacements will be performed prior to November 30, 1985.

4

~

~

NORTHERN STATES POWER COMPANY TER Response PRAIRIE ISLAND NUCLEAR GENERATING PLANT July 29, 1983 Page 2.2-7 UNIT NUMBER: 2 TER EQUIPMENT ITEM NUMBER:

7 EQUIPMENT DESCRIPTION: Limitorque Motorized Valve Actuator Model SMB-00 EQUIPMENT LOCATION: Reactor Building Unit 2 TER QUALIFICATION CATEGORY:

II.A TER-IDEATIFIED PLANT ID NUMBERS:

MV-32195, MV-32196, MV-32197, MV-32198 CORRECT PLANT ID NUMBERS FOR THIS UNIT: MV-32197, MV-32198 Note:

Valve actuators MV-32195 and MV-32196 are used in Unit 1 functions and are included in Equipment Item 7 for Unit 1.

ITEMIZED DEFICIENCIES AND RESPONSES:

1.

Equipment qualification not established.

A.

Adequate similarity between equipment and test specimen not established.

B.

Aging degradation not evaluated adequately.

C.

Qualified life or replacement schedule not established.

Several pages of detailed notes were provided in the TER pertaining to deficiencies in the environmental qualification of this equipment item.

RESPONSE

A project has been initiated to thoroughly evaluate and document the environ-mental qualification of Limitorque valve actuators. Each of the concerns raised in the TER will be addressed in that evaluation. We expect tnat the evaluation will be finalized by January 1, 1984, and that any necessary modifications or replacements will be performed prior to November 30, 1985.

NORTHERN STATES POWER COMPANY TER Response PRAIRIE ISLAND NUCLEAR GENERATING PLANT July 29, 1983 Page 2.2-8 UNIT NUMBER: 2 TER EQUIPMENT ITEM NUMBER:

8 EQUIPMENT DESCRIPTION: Limitorque Motorized Valve Actuator Model SMB-00 EQUIPMENT LOCATION: Reactor Building Unit 2 TER QUALIFICATION CATEGORY:

III.A TER-IDENTIFIED PLANT ID NUMBERS: MV-32171, MV-32173, MV-32070, MV-32068, MV-32172 CORRECT PLANT ID NUMBERS FOR THIS UNIT: MV-32171, MV-32173, MV-32172 Note:

Valve actuators MV-32070 and MV-32068 are used in Unit I functions and are included in Equipment Item 8 for Unit 1.

ITEMIZED DEFICIENCIES AND RESPONSES:

These valve actuators are in a locked-open position with power removed and cannot, therefore, change position. This equipment item is exempt from quali-fication and has been removed from the safety-related equipment masterlist.

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I NORTHERN STATES POWER COMPANY TER Response PRAIRIE ISLAND NUCLEAR GENERATING PLANT July 29, 1983 Page 2.2-9 UNIT NUMBER: 2 TER EQUIPMENT ITEM NUMBER:

9 EQUIPMENT DESCRIPTION:

Limitorque Motorized Valve Actuators Models SMB-0 and SMB-1 EQUIPMENT LOCATION:

Reactor Building Unit 2 TER QUALIFICATION CATEGORY.:

II.A TER-IDENTIFIED PLANT ID NUMBERS: MV-32064, MV-32193, MV-32165, MV-32231, MV-32233, MV-32066, MV-32169, MV-32192, MV-32164, MV-32230, MV-32232 CORRECT PLANT 10 NUMBERS FOR THIS UNIT:

MV-32193, MV-32233, MV-32169, MV-32192, MV-32232 Note:

Valve actuators MV-32064, MV-32165, MV-32231, MV-32066, MV-32164, and MV-32230 are used in Unit 1 functions and are included in Equipment Item 9 for Unit 1.

ITENIZED DEFICIENCIES AND RESPONSES:

1.

Equipment qualification not established.

A.

Adequate similarity between equipment and test specimen not established.

B.

Aging degradation not evaluated adequately.

C.

Qualified life or replacement schedule not established.

Several pages of detailed notes were provided in the TER pertaining to deficiencies in the environmental qualification of this equipment item.

RESPONSE

All valve actuators in this equipment item with the exception of MV-32064 were included in the NSP cold shutdown response, Response to IE Bulletin 79-OlB, Supplement 3, January 22, 1980, and have therefore been removed from the IE Bulletin 79-018 safety-related equipment masterlist.

A project has been initiated to thoroughly evaluate and document the environ-mental qualification of Limitorque valve actuators. Valve actuator MV-32064 will be included in this evaluation. Each of the concerns raised in the TER will be addressed in that evaluation. We expect that the evaluation will be finalized by January 1,1984, and that any necessary modifications or replace-ments will be performed prior to November 30, 1985.

NORTHERN STATES POWER COMPANY TER Response PRAIRIE ISLAND NUCLEAR GENERATING PLANT July 29, 1983 Page 2.2-10 UNIT NUMBER: 2 TER EQUIPMENT ITEM NUMBER:

10 EQUIPMENT DESCRIPTION: Limitorque Motorized Valve Actuator Model SMB-00 EQUIPMENT LOCATION: Auxiliary Building TER QUALIFICATION CATEGORY:

III.A TER-IDENTIFIED PLANT ID NUMBERS:

MV-32242, MV-32243, MV-32248, MV-32249 CORRECT PLANT ID NUMBERS FOR THIS UNIT: MV-32248, MV-32249 Note:

Valve actuators MV-32242 and MV-32243 are used in Unit 1 functions and are included in Equipment Item 10 for Unit 1.

ITEMILED DEFICIENCIES AND RESPONSES:

These valve actuators are in a locked-open position with power removed and cannot, therefore, change position. This equipment item is exempt from quali-fication and has been removed from the safety-related equipment ma terlist.

NORTP.ERN STATES POWER COMPANY TER Response PRAIRIE ISLAND NUCLEAR GENERATING PLANT July 29, 1983 Page 2.2-11 UNIT NUMBER: 2 TER EQUIPMENT ITEM NUMBER:

11 EQUIPMENT DESCRIPTION: Limitorque Motorized Valve Actuator Model SMB-3 EQUIPMENT LOCATION: Auxiliary Building TER QUALIFICATION CATEGURY:

II.A TER-IDENTIFIED PLANT ID NUMBERS: MV-32023, MV-32024, MV-32028, MV-32029 CORRECT PLANT ID NUMBERS FOR THIS UNIT: MV-32028, MV-32029 Note:

Valve actuators MV-32023 and MV-32024 are used in Unit i functions and are included in Equipment Item 11 for Unit 1.

ITEMIZED DEFICIENCIES AND RESPONSES:

1.

Equipment qualification not established.

A.

Adequate similarity between equipment and test specimen not established.

B.

Aging degradation.not evaluated adequately.

C.

Qualified life or replacement schedule not established.

Several pages of detailed notes were provided in the TER pertaining te deficiencies in the environmental qualification of this equipment item.

I

RESPONSE

l l

A project has been initiated to thoroughly evaluate and document the environ-mental qualification of Limitorque valve actuators. Each of the concerns raised in the TER will be addressed in that evaluation. We expect that the evaluation will be finalized by January 1, 1984, and that any necessary modifications or replacements will be performed prior to November 30, 1985.

l 1

l l

l l

NORTHERN STATES POWER COMPANY TER Response PRAIRIE ISLAND NUCLEAR GENERATING PLANT July 29, 1983 Page 2.2-12 UNIT NUMBER: 2 TER EQUIPMENT ITEM NUMBER:

12 EQUIPMENT DESCRIPTION: Limitorque Motorized Valve Actuator Model SMB-00 EQUIPMENT LOCATION: Auxiliary Building TER QUALIFICATION CATEGORY:

II.A TER-IDENTIFIED PLANT ID NUMBERS: MV-32166, MV-32194 CORRECT PLANT ID NUMBERS FOR THIS UNIT: MV-32194 Note:

Valve actuator MV-32166 is used in Unit 1 functions and is included in Equipment Item 12 for Unit 1, ITEMIZED DEFICIENCIES AND RESPONSES:

1.

Equipment qualification not ' established.

A.

Adequate similarity between equipment and test specimen not established.

B.

Aging degradation not evaluated' adequately.

C.

Qualified life o.r replacement schedule not established.

Several pages of detailed notes were provided in the TER pertaining to deficiencies in the environmental qualification of this equipment item.

RESPONSE

A project has been initiated to thoroughly evaluate and document the environ-mental qualification of Limitorque valve actuators. Each of the concerns raised in the TER will be addressed in that evaluation. We expect that the evaluation will be finalized by January 1, 1984, and that any necessary mocifications or replacements will be performed prior to November 30, 1985.-

.w NORTHERN STATES POWER COMPANY:

TER Response PRAIRIE ISLAND NUCLEAR GENERATING PLANT July 29, 1983 Page 2.2-13 M

UNIT NUNSER: -2 TER EQUIPMENT ITEM iMiBER:

13

~

EQUIPMENT DESCRIPTION: Limitorque Motorized Valve Actuator Models SMB-0, SMB-00< and SMB-i EQUIPMENT LOCATION: Auxiliary Building TER QUALIFICATI0N' CATEGORY:

II.A TER-IDENTIFIED PLANT ID NUMCERSf MV-32206, MV-32207, MV-32208, MV-32209, MV-32163, MV-32162, MV-32190, MV-32191, MV-32077, MV-32078, MV-32178, MV-32179, MV-32180, MV-32181, MV-32075, MV-32076, MV-32084, MV-32085, MV-32187, MV-32188, MV-32184, MV-32185, MV-32186, MV-32081, MV-32082, MV-32083, MV-32096, MV-32097, MV-32108, MV-32109, MV-32103, MV-32105, MV-32114, MV-32116 CORRECT PLANT ID NUMBERS FOR THIS UNIT:

MV-32208, MV-32209, MV-32190, MV-32191, MV-32178, MV-32179, MV-32180, MV-32181, MV-32187, MV-32188, MV-32081, MV-32082, MV-32083, MV-32018, MV-32109, MV-32114, MV-32116 Note:

Valve actuators MV-32206, MV-32207, MV-32163, MV-32162, MV-32077,

' MV-32078, MV-32075, MV-32076, MV-32084, MV-32085, MV-32184, MV-32185, MV-32186, MV-32096, MV-32097, MV-32103, and MV-32105 are used in Unit 1 functions and are included in' Equipment Item 13 for Unit 1.

~

ITEMIZED DEFICIENCIES AND RESPONSES:

1 Ecuipment'qu_a,lification not. established.

~

A.

Adequate' similarity between equipment and test specimen not Tastanlished.

B.

Aging degradati.on not evaluatec adequately.

C.

Qualified life or replacement schedule not established.

Several pages of detailed notes were provided in the TER pertaining to deficiencies in the environmental qualification of this equipment item.

RESPONSE

A project has been initiated to thoroughly evaluate and document the environ-mental qualification of Limitorque valve actuators. Each of the concerns raised in the TER'Will be adaressed in that evaluation. We expect that the evaluation will be finalized by January 1, 1984, and that any necessary modifications or replacements will-be performed prior to November 30, 1985.

4

NORTHERN STATES PCWER COMPANY TER Response PRAIRIE ISLAND NUCLEAR GENERATING PLANT July 29, 1983 Page 2.2-14 UNIT NUMBER: 2 TER EQUIPMENT ITEM NUMBER:

14 EQeIPMENT DESCRIPTION: Limitorque Motorized Valve Actuator Model SM3-000 EQUIPMENT LOCATION:

Shield Building Unit 2 TER QUALIFICATION CATEGORY:

II.A TER-IDENTIFIED PLANT ID NUMBERSr MV-32293, MV-32295, MV-32274, MV-32276,

CORRECT ' PLANT ID NUMBERS FOR Tl!IS UNIT: MV-32293, MV-32295 hote:

Valve actuators MV-32274 ard MV-32276 are used in Unit 1 functions and are included in Equipsent Item 14 for Unit 1.

ITEMIZED DEFICIENCIES AND RESPONSES:

1.

Equipment qualification not established.

A.

Adequate similarity between equipment and test specimen not established.

B.

Aging degradation not evaluated adequately.

C.

Qualified life or replacement schedule not established.

Several pages of detailed notes were provided in the TER pertaining to deficiencies in the environmental qualification of this equipment item.

RESPONSE

A project has been initiated to thoroughly evaluate and document the environ-mental qualification of Limitorque valve actuators. Each of the concerns raised in the TER will'be addressed ~in.that evaluation. We expect that the evaluation will be finalized by January 1,1984, and that any necessary modifications or replacements will be performed prior to' November 30, 1985.

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o.

NORTHERN STATES POWER COMPANY TER Response PRAIRIE ISLAND NUCLEAR GENERATING PLANT July 29, 1983 Page 2.2-15 UNIT NUMBER: 2 TER EQUIPMENT ITEM NUMBER:

15 EQUIPMENT DESCRIPTION: Limitorque Motorized Valve Actuator Model SMB-00 EQUIPMENT LOCATION:

Shield Building Unit 2 TER QUALIFICATION CATEGORY:

II.A TER-IDENTIFIED PLANT ID NUMBERS:

MV-32177, MV-32073, MV-32176, MV-32074 CORRECT PLANT ID NUMBERS FOR THIS UNIT: MV-32177, MV-32176, Note:

Valve actuators MV-32073 and MV-32074 are used in Unit 1 functions and are included in Equipment Item 15 for Unit 1.

ITEMIZED DEFICIENCIES AND RESPONSES:

1.

Equipment qualification not established.

A.

Adequate similarity between equipment and test specimen not established.

B.

Aging degradation not evaluated adequately.

C.

Qualified life or replacement schedule not established.

Several pages of detailed notes were provided in the TER pertaining to deficiencies in the environmental qualification of this equipment item.

RESPONSE

A project has been initiated to thoroughly evaluate and document the environ-mental qualification of Limitorque valve actuators. Each of the concerns raised in the TER will be addressed in that evaluation. We expect that the evaluation will be finalized by January 1,1984, and that any necessary modifications or replacements will be performed prior to November 30, 1985.

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NORTHERN STATES POWER COMPANY TER Response PRAIRIE ISLAND NUCLEAR GENERATING PLANT July 29, 1983 Page 2.2-16 UNIT NUMBER: 2 TER EQUIPMENT ITEM NUMBER:

16 EQUIPMENT DESCRIPTION: Target Rock Solenoid Valve Model 80B-001 EQUIPMENT LOCATION: Reactor Building Unit 2 TER QUALIFICATION CATEGORY:

IV TER-IDENTIFIED PLANT ID NUMBERS:

SV-37035, SV-37037, SV-37039, SV-37036, SV-37038, SV-37040, SV-37091, SV-37093, SV-37095, SV-37092, SV-37094, SV-37096 CORRECT PLANT ID NUMBERS FOR THIS UNIT:

SV-37091, SV-37093, SV-37095, SV-37092, SV-37094, SV-37096 Note:

Solenoid Valves SV-37035, SV-37037, SV-37039, SV-37036, SV-37038, and SV-37040 are all used in Unit 1 functions and are included in Equipment Item 16 for Unit 1.

ITEMIZED DEFICIENCIES AND RESPONSES:

1.

Documentation not made available to FRC for review.

RESPONSE

Documentation was not provided to FRC because it was not included in the Request for Information submitted to NSP. However, this component is fully qualified for the installed environment and application at Prairie Island based on environmental qualification testing [1] and component specific analysis [2].

This qtalification data is available for inspection upon NRC request. This equipment item is therefore categorized in Category I.A and is fully qualified.

EQUIPMENT ITEM SPECIFIC REFERENCES-1.

Target Rock Corporation Environmental Test Report 72804B.

2.

EDS Report 04-0910-21, Revision 1, " Beta Radiation Evaluation of Safety-Related Electrical Equipment at Prairie Island Units 1 and 2," April 1982.

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NORTHERN STATES POWER COMPANY TER Response PRAIRIE ISLAND NUCLEAR GENERATING PLANT July 29, 1983 Page 2.2-17 UNIT NUMBER: 2 TER EQUIPMENT ITEM NUMBER:

17 EQUIPMENT DESCRIPTION: ASCO Solenoid Valve Model NP-831654E EQUIPMENT LOCATION:

Shield Building Unit 2 TER QUALIFICATION CATEGORY:

I.A TER-IDENTIFIED PLANT ID NUMBERS:

SV-33515, SV-33516 CORRECT PLANT ID NUMBERS FOR THIS UNIT:

SV-33515, SV-33516 ITEMIZED DEFICIENCIES AND RESPONSES:

There are no deficiencies identified in the environmental qualification of this equipment item.

O l

NORTHERN STATES POWER COMPANY TER Response PRAIRIE ISLAND NUCLEAR GENERATING PLANT July 29, 1983 Page 2.2-18 UNIT NUMBER: 2 TER EQUIPMENT ITEM NUMBER:

18 -

EQUIPMENT DESCRIPTION: ASCO Solenoid Valve Model NP-8320A194E EQUIPMENT LOCATION:

Shield Building Unit 2 TER QUALIFICATION CATEGORY:

I.A TER-IDENTIFIED PLANT ID NUMBERS: SV-33992, SV-33993 CORRECT PLANT ID NUMBERS FOR THIS UNIT:

SV-33992, SV-33993 ITEMIZED DEFICIENCIES AND RESPONSES:

There are no deficiencies identified in the environmental qualification of this equipment item.

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NORTHERN STATES POWER C0lfANY TER Response PRAIRIE ISLAND NUCLEAR GENERATING PLANT July 29, 1983 Page 2.2-19 UNIT NUMBER: 2 TER EQUIPMENT ITEM NUMBER:

19 EQUIPMENT DESCRIPTION: ASCO Solenoid Valve Model 8211835/8316C46 EQUIPMENT LOCATION: Auxiliary Building TER QUALIFICATION CATEGORY:

II.A TER-IDENTIFIED PLANT ID NUMBERS: SV-33258, SV-33262

~

CORRECT PLANT ID NUMBERS FOR THIS UNIT:

SV-33258, SV-33262 ITEMIZED DEFICIENCIES AND RESPONSES:

1.

Equipment qualification not established.

A.

Documented evidence of qualification is inad. equate.

RESPONSE

Failure of these solenoid valves will not adversely affect the closing of MSIVs and will not mislead the reactor operator. Solenoid valves SV-33258 and SV-33262 have therefore been removed from the safety-related equipment master-list, and environmental qualification is not required.

l

NORTHERN STATES POWER COMPANY TER Response PRAIRIE ISLAND NUCLEAR GENERATING PLANT July 29, 1983 Page 2.2-20 UNIT NUMBER: 2 TER EQUIPMENT ITEM NUMBER:

20 EQUIPMENT DESCRIPTION: ASCO Solenoid Valve Model NP-8321 ale EQUIPMENT LOCATION: Auxiliary Building TER QUALIFICATION CATEGORY:

I.A TER-IDENTIFIED PLANT ID NUMBERS:

SV-33283 CORRECT PLANT ID NUMBERS FOR THIS UNIT:

SV~33283 ITEMIZED DEFICIENCIES AND RESPONSES:

There are no deficiencies identified in the environmental qualification of this equipment item.

1 L

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. o NORTHERN STATES POWER COMPANY TER Response PRAIRIE ISLAND NUCLEAR GENERATING PLANT July 29, 1983 Page 2.2-21 UNIT NUMBER: 2 TER EQUIPMENT ITEM NUMBER:

21 EQUIPMENT DESCRIPTION: ASCO Solenoid Valve Model NP-8316E35E EQUIPMENT LOCATION: Auxiliary Building TER QUALIFICATION CATEGORY:

I.A TER-IDENTIFIED PLANT ID NUMBERS:

SV-33260, SV-33261, SV-33265, SV-33266 CORRECT PLANT ID NUMBERS FOR THIS UNIT:

SV-33260, SV-33261, SV-33265, SV-33266 ITEMIZED DEFICIENCIES AND RESPONSES:

There are no deficiencies identified in the environmental qualification of this equipment item.

NORTHERN STATES POWER COMPANY TER Response PRAIRIE ISLAND NUCLEAR GENERATING PLANT July 29, 1983 Page 2.2-22 UNIT NUMBER: 2 TER EQUIPMENT ITEM NUMBER:

22 EQUIPMENT DESCRIPTION: ASCO Solenoid Valve Model NP-8321 ale EQUIPMENT LOCATION: Reactor Building Unit 2 TER QUALIFICATION CATEGORY:

I.A

, TER-IDENTIFIED PLANT ID NUMBERS:

SV-33389, SV-33390, SV-33391, SV-33392, SV-33393, SV-33394, SV-33395, SV-33396 CORRECT PLANT ID NUMBERS FOR THIS UNIT:

SV-33389, SV-33390, SV-33391, SV-33392, SV-33393, SV-33394, SV-33395, SV-33396 ITEMIZED DEFICIENCIES AND RESPONSES:

There are no deficiencies identified in the environmental qualification of this equipment item.

O

.-,---7

NORTHERN STATES POWER COMPANY TER Response PRAIRIE ISLAND NUCLEAR GENERATING PLANT July 29, 1983 Page 2.2-23 UNIT NUMBER: 2 TER EQUIPMENT ITEM NUMBER:

23 EQUIPMENT DESCRIPTION: ASCO Solenoid Valve Models NP-8321 ale, NP-831654E, and NP-8320A182E EQUIPMENT LOCATION: Reactor Building Unit 2 TER QUALIFICATION CATEGORY:

I.A TER-IDENTIFIED PLANT ID NUMBERS:

SV-33763, SV-33764, SV-33740, SV-33741, SV-33661, SV-332a4 CORRECT PLANT ID NUMBERS FOR THIS UNIT:

SV-33763, SV-33764, SV-33740, SV-33741, SV-33284 Note:

SV-33661 is a Valcor solenoid valve used in the Reactor Hot Sampling System and should not be included in this equipment item.

ITEMIZED DEFICIENCIES AND RESPONSES:

There are no deficiencies identified in the environmental qualification of this equipment item.

,.-,-,------r--,,

NORTHERN STATES POWER COPPANY TER Response PRAIRIE ISLAND NUCLEAR GENERATING PLANT July 29, 1983 Page 2.2-24 UNIT NUMBER: 2 TER EQUIPMENT ITEM NUMBER: 24 EQUIPMENT DESCRIPTION: Micro Switch Limit Switch Model BZ2RW899A2 EQUIPMENT LOCATION:

Shield Building Unit 2 TER QUALIFICATION CATEGORY:

II.A TER-IDENTIFIED PLANT ID NUMBERS: CV-31625, CV-31630, CV-31631, CV-31624 CORRECT PLANT 10 NUMBERS FOR THIS UNIT: CV-31630, CV-31631 Note:

Limit Switches CV-31624, CV-31625 are used in Unit 1 functions and are included in Equipment Item 24 for Unit 1.

ITEMIZED ~ DEFICIENCIES AND RESPONSES:

1.

Equipment qualification not established.

A.

Criteria regarding steam exposure is inadequate.

"The unit is exposed to steam as shown on the profiles provided by the licensee." The note for steam qualification on the SCEW from the August 26, 1981, NSP IEB79-01B SER submittal states, "The qualification documentation per-taining to these components is currently being evaluated for inclusion in the bulletin."

RESPONSE

The April 30, 1982, IEB79-01B SER response updated the aforementioned statement to resolve all open items in the environmental qualification of this equipment item. An evaluation was performed to occument the environmental qualification of Micro Switch limit switches for Prairie Island shield building applications

[1]. On the basis of this evaluation, it was concluded that these limit switches will not be exposed to a steam environment for the accident which requires their operation. HELBs are not postulated for the shield building due to encapsulation of piping in piping penetrations. The limiting accident for this component (LOCA) does not yield steam conditions in the shield building.

l Because there is no potential for steam or significant accumulation of conden-sate, switch degradation due to steam / relative humidity conditions will not I

occur. Therefore, there are no outstanding items in the environmental quali-fication of this equipment item and it is now classified in Category I.A.

EQUIPMENT ITEM SPECIFIC REFERENCES 1.

EDS Calculation File 0910-200-EQ-01, Revisica 0, Envionmental Qualification of Micro Switch Limit Switches," December 1981.

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NORTHERN STATES POWER C0WANY TER Response PRAIRIE ISLAND NUCLEAR GENERATING PLANT July 29, 1983 Page 2.2-25 UNIT NUMBER: 2 TER EQUIPMENT ITEM NUMBER:

25 EQUIPMENT DESCRIPTION: NAMC0 Limit Switch Model EA-180 EQUIPMENT LOCATION: Reactor Building Unit 1 TER QUALIFICATION CATEGORY:

II.A TER-IDENTIFIED PLANT ID NUMBERS: CD-34072, CD-34074, CD-34076, CD-34078, CD-34080, CD-34082, CD-34084, CD-34086 CORRECT PLANT ID NUMBERS FOR THIS UNIT: CD-34080, CD-34082, CD-34084 CD-34086 Note:

Limit Switches CD-34072, CD-34074, CD-34076, and CD-34078 are all used in Unit 1 functions and are included in Equipment Item 25 for Unit 1.

ITEMIZED DEFICIENCIES AND RESPONSES:

1.

Equipment qualification not established.

A.

Documented evidence of qualification is inadequate.

"The licensee has cited as evidence of qualification a test plan for the NAMC0 EA-180 and EA-740 Limit Switches. The referenced document is a test plan and not a test report. Furthermore, the SCEW does not identify the model number.

Accordingly, qualification has not been established."

RESPONSE

The limit switches included in this equipment item are identical to those in-cluded with Equipment Item 30. Equipment Item 30 was considered to be qualified providing a Conax Conductor Seal Assembly was installed (which has been done).

System Component Evaluation Worksheets (SCEWs) for all NAMC6 limit switches have been revised to reference the NAMC0 qualification test report for EA-180 limit switches rather than the test plan.

In addition, a thermal aging evalua-tion was performed for NAMC0 limit switches to determine component replacement intervals based on installed location in the plant [1]. The results of this evaluation are being incorporated into plant maintenance activities. On the basis of testing and analysis, we have concluded that this equipment item is fully qualified and is categorized in Category I.A.

EQUIPMENT ITEM SPECIFIC

REFERENCES:

1.

EDS Calculation File 0910-200-TA-01, Revision 1, "NAMC0 Limit Switch Thermal Aging Evaluation," April 1982.

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NORTHERN STATES POWER CON ANY TER Response PRAIRIE ISLAND NUCLEAR GENERATING PLANT July 29, 1983 Page 2.2-26 UNIT NUMBER: 2 TER EQUIPMENT ITEM NUMBER:

26 EQUIPMENT DESCRIPTION: NAMC0 Limit Switch Model 02400X EQUIPMENT LOCATION: Reactor Building Unit 2 TER QUALIFICATION CATEGORY:

I.B TER-IDENTIFIED PLANT ID NUMBERS: CV-31296, CV-31298, CV-31300, CV-31303, CV-31305, CV-31307-CORRECT PLANT ID NUMBERS FOR THIS UNIT:

SV-33657, SV-33659, SV-33661 Note:

Solenoid valves with integral indication features have been installed.

Solenoid valve ID numbers have replaced the limit switch ID numbers.

ITEMIZED DEFICIENCIES AND RESPONSES:

1.

Equipment modification required to establish qualification.

RESPONSE

NAMC0 D2400X Limit Switches have been replaced with qualified Valcor Solenoid Valves with int'egral indication features. The valves used in Unit 2 applica-tions are identified with ID Numoers SV-33657, SV-33659, and SV-33661. Limit switch equipment ID numbers have been removed from the safety-related equipment masterlist and solenoid valve ID numbers have been added. Because replacement with qualified equipment has already taken place, this equipment item is now classified in Category I.A and is fully qualified.

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NORTHERN STATES POWER COMPANY TER Response PRAIRIE ISLAND NUCLEAR GENERATING PLANT July 29, 1983 Page 2.2-27 UNIT NUMBER: 2 TER EQUIPMENT ITEM NUMBER:

27 EQUIPMENT DESCRIPTION: NAMCO Limit Switch Model EA-170 EQUIPMENT LOCATION: Auxiliary Building TER QUALIFICATION CATEGORY:

I.A TER-IDENTIFIED PLANT ID NUMBERS:

CV-31235, CV-31236, CV-31237, CV-31238, CV-31239, CV-31240 CORRECT PLANT ID NUMBERS FOR THIS UNIT: CV-31238, CV-31239, CV-31240 NOTE:

Limit Switches CV-31235, CV-31236, and CV-31237 are all used in Unit I functions and are included in Equipment Item 27 for Unit 1.

ITEMIZED DEFICIENCIES AND RESPONSES:

There are no deficiencies identified in tne environmental qualification of this equipment item.

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NORTHERN STATES POWER CON ANY TER Response PRAIRIE ISLAND NUCLEAR GENERATING PLANT July 29, 1983 Page 2.2-28a UNIT NUMBER: 2 TER EQUIPMENT ITEM NUMBER: 28 EQUIPMENT DESCRIPTION: NAMC0 Limit Switch Model EA-170 EQUIPMENT LOCATION:

Shield Building Unit 2 TER QUALIFICATION CATEGORY:

II.A TER-IDENTIFIED PLANT ID NUMBERS: CV-31314, CV-31316, CV-31574, CV-31627, CV-31628, CV-31635 CORRECT PLANT ID NUMBERS FOR THIS UNIT: CV-31627, CV-31628 Note:

Limit switches CV-31314, CV-313?6, CV-31574, and CV-31635 have all been removed from tne safety-related equipment casterlist because cf modifi-cations to the Containment Purge System.

ITEMIZED DEFICIENCIES AND RESPONSES:

1.

Equipment qualification not established.

A.

Aging degradation not evaluated adequately.

B.

Qualified life or replacement schedule not established. The licensee stated in the August 26, 1981, SER Response, "The qualification docu-mentation for aging pertaining to these components is currently being evaluated for inclusion in this bulletin."

C.

Peak pressure qualification inadequate.

D.

Required profile not enveloped adequately.

"The testing envelopes the Annulus temperature profile but not the pressure profile."-

l E.

Steam exposure qualification inadequate. "In addition, the licensee has i

not addressed the sealing method used to preclude entry of moisture."

RESPONSE

A thermal aging evaluation was performed for NAMCO limit switches to determine component replacement intervals based on installed location in the plant [1].

l Depending upon the material of the particular component within the limit switch, replacement is required in the range of 7 to 40 years. The results of this evaluation are being incorporated into plant maintenance activities.

Therefore, aging degradation and qualified life / replacement schedule have been adequately addressed.

The peak pressure postulated for the installed location (shield building) is 3 inches water (0.11 psi) and going to a vacuum of approximately 3-l/2 inches water (0.13 psi). The pressure will remain at this level for the duration of l

l l

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NORTHERN STATES POWER COMPANY TER Response PRAIRIE ISLAi4D NUCLEAR GENERATING PLANT July 29, 1983 Page 2.2-28b ITEMIZED DEFICIENCIES AND RESPONSES (Cont.):

the 2-hour operating ti:ne. Pressures of this magnitude for a 2-hour duration will not impose stressas on the limit switches in excess of those occurring during pressure variations in normal operation and will not lead to switch failure.

These limit switches will not be exposed to a steam environment for the acci-dent which requires their operation. HELBs are not postulated for the shield building due to encapsulation in piping penetrations. The limiting accident for this component (LOCA) does not yield steam conditions in the shield building. Because there is no potential for steam or significant accumulation of condensate, switch degradation due to steam / relative humidity conditions will not occur.

In addition, RTV is applied to the conduit entry of all NAMC0 EA-170 limit switches to further protect against intrusion of moisture into the limit switen.

On the basis of the discussion provided above, we conclude that all deficien-cies have been resolved and this component is fully qualified. Equipment Item 28 is therefore categorized in Category I.A.

EQUIPMENT ITEM SPECIFIC REFERENCES-1.

EDS Calculation File 0910-200-TA-01, Revision 1, "NAMC0 Limit Switch Thermal Aging Evaluation," April 1982.

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NORTHERN STATES POWER COMPANY TER Response PRAIRIE ISLAND NUCLEAR GENERATING PLANT July 29, 1983 Page 2.2-29 UNIT NUMBER: 2 TER EQUIPMENT ITEM NUMBER:

29 EQUIPMENT DESCRIPTION: NAMC0 Limit Switch Model EA-180 EQUIPMENT LOCATION:

Reactor Building Unit 2 TER QUALIFICATION CATEGORY:

II.C TER-IDENTIFIED PLANT ID NUMBERS: CV-31231, CV-31232 CORRECT PLANT ID NUMBERS FOR THIS UNIT: CV-31233, CV-31234 Note:

Limit Switches CV-31231 and CV-31232 are used in Unit 1 functions and are included in Equipment Item 29 for Unit 1.

The correct Plant ID numbers for this unit are CV-31233 and CV-31234.

ITEMIZED DEFICIENCIES AND RESPONSES:

1.

Equipment satisfies all requirements except qualified life or replacement schedule justified.

A.

Qualified life or replacement schedule has not been established.

" Heat aging conditions were taken from ANSI Draft Standard N278.2.1 (Draft 3, Rev. 0). The correlation Detween these conditions and the qualified life is not known."

RESPONSE

A thermal aging evaluation was performed for NAMC0 limit switches which deter-mined component replacement intervals based on location in the plant [1]. The results of this evaluation are being incorporated into plant maintenance acti-i vities.

In addition, a Conax Electric Conductor Seal Assembly (ECSA) has been installed to hermetically seal the limit switch enclosure. This component is now classified Category I.A and is fully qualified.

EQUIPMENT ITEM SPECIFIC

REFERENCES:

1.

EDS Calculation File 0910-200-TA-01, Revision 1, "NAMC0 Limit Switch Thermal Aging Evaluation," April 1982.

~

NORTHERN STATES POWER COMPANY TER Response PRAIRIE ISLAND NUCLEAR GENERATING PLANT July 29, 1983 Page 2.2-30 UNIT NUMBER: 2 TER EQUIPMENT ITEM NUMBER: 30 EQUIPMENT DESCRIPTION: NAMC0 Limit Switch Model EA-180 EQUIPMENT LOCATION: Reactor Building Unit 2 TER QUALIFICATION CATEGORY:

II.C TER-IDENTIFIED PLANT ID NUMBERS:

CD-34080, CD-34082, CD-34084, CD-34086 CORRECT PLANT ID NUMBERS FOR THIS UNIT: CD-34080, CD-34082, CD-34084, CD-34086 ITEMIZED DEFICIENCIES AND RESPONSES:

1.

Equipment satisfies all requirements except qualified life or replacement schedule justified.

A.

Qualified life or replacement schedule has not been established.

" Heat aging conditions were taken from ANSI Draft Standard N278.2.1 (Draft 3, Rev. 0). The correlation between these conditions and the qualified life is not known."

RESPONSE

A thermal aging evaluation was performed for NAMC0 limit switches which deter-mined component replacement intervals based on location in the plant [1]. The results of this activity are being incorporated into plant maintenance activi-ties.

In addition, a Conax Electric Conductor Seal Assembly (ECSA) has been installed to hermetically seal the limit switch enclosure. This component is now classified Category I.A and is fully qualified.

EQUIPMENT ITEM SPECIFIC

REFERENCES:

1.

EDS Calculation File 0910-200-TA-01, Revision 1, "NAMC0 Limit Switch Thermal Aging Evaluation," April 1982.

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NORTHERN STATES POWER COMPANY TER Response PRAIRIE ISLAND NUCLEAR GENERATING PLANT July 29, 1983 Page 2.2-31 UNIT NUMBER: 2 TER EQUIPMENT ITEM NUMBER: 31 EQUIPMENT DESCRIPTION: NAMC0 Limit Switch Model EA-180 EQUIPMENT LOCATION: Auxiliary Building TER QUALIFICATION CATEGORY:

II.C TER-IDENTIFIED PLANT ID NUMBERS: CV-31098, CV-31099, CV-31116, CV-31117, CV-31084, CV-31102, CV-31107 CORRECT PLANT ID NUMBERS FOR THIS UNIT: CV-31116, CV-31117, CV-31102, CV-31107 Note:

Limit switches CV-31098, CV-31099, and CV-31084 are all used in Unit 1 functions and are included in Equipment Item 31 for Unit 1.

ITEMIZED DEFICIENCIES AND RESPONSES:

1.

Equipment satisfies all requirements except qualified life or replacement schedule justified.

A.

Qualified life or replacement schedule has not bean established.

" Heat aging conditions were taken from ANSI Draft Standard N278.2.1 (Draft 3, Rev. 0). The correlation between these conditions and the qualified life is not known."

RESPONSE

A thermal aging evaluation was performed for NAMC0 limit switches which deter-mined component replacement intervals based on location in the plant L1]. The results of this activity are being incorporated into plant maintenance activi-ties.

In addition, a Conax Electric Conductor Seal Assembly (ECSA) has been installed to hermetically seal the limit switch enclosure. This component is now classified Category I.A and is fully qualified.

EQUIPMENT ITEM SPECIFIC

REFERENCES:

l 1.

EDS Calculation File 0910-200-TA-01, Revision 1, "NAMC0 Limit Switch Thermal Aging Evaluation," April 1982.

l l

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NORTHERN STATES POWER COMPANY TER Response PRAIRIE ISLAND NUCLEAR GENERATING PLANT July 29, 1983 Page 2.2-32 UNIT NUMBER: 2 TER EQUIPMENT ITEM NUMBER: 32 EQUIPMENT DESCRIPTION: NAMCO Limit Switch Model EA-180 EQUIPMENT LOCATION: Reactor Building Unit 2 TER QUALIFICATION CATEGORY:

II.C TER-IDENTIFIED PLANT ID NUMBERS:

CV-31347, CV-31348, CV-31349, CV-31317, CV-31575, CV-31315, CV-31636, CV-31643, CV-31129, CV-31296, CV-31298, CV-31300, CV-31303, CV-31305, CV-31307, CV-31639, CV-31640, CV-31743 CORRECT PLANT ID NUMBERS FOR THIS UNIT: CV31347, CV-31348, CV-31349, CV-31643, CV-31129, CV-31639, CV-31640, CV-31743 Note:

Limit switches CV-31317, CV-31575, CV-31315, and CV-31636, have been removed from the safety-related masterlist because of modification to the Containment Purge System. Limit Switches CV-31296, CV-31298, CV-31300, CV-31303, CV-31305, and CV-31307 are identical to Equipment Item 26 and are addressed with that equipment item.

ITEMIZED DEFICIENCIES AND RESPONSES:

1.

Equipment satisfies all requirements except qualified life or replacement schedule justified.

A.

Qualified life or replacement schedule has not been established.

" Heat aging conditions were taken from ANSI Draft Standard N278.2.1 (Draft 3, Rev. 0). The correlation between these conditions and the qualified life is not known."

RESPONSE

A thermal aging evaluation was performed for NAMC0 limit switches which deter-mined component replacement intervals based on location in the plant [1]. The results of this activity are being incorporated into plant maintenance activi-ties.

In addition, a Conax Electric Conductor Seal Assembly (ECSA) has been installed to hermetically seal the limit switch enclosure. This component is now classified Category I.A and is fully qualified.

EQUIPMENT ITEM SPECIFIC

REFERENCES:

1.

EDS Calculation File 0910-200-TA-01, Revision 1, "NAMC0 Limit Switch Thermal Aging Evaluation," April 1982.

NORTHERN STATES POWER C0W ANY TER Response PRAIRIE ISLAND NUCLEAR GENERATING PLANT July 29, 1983 Page 2.2-33a UNIT NUMBER: 2 TER EQUIPMENT ITEM NUMBER: 33 EQUIPMENT DESCRIPTION:

Electric Machinery Manufacturing Company Electric Motor EQUIPMENT LOCATION: Auxiliary Building TER QUALIFICATION CATEGORY:

II.A TER-IDENTIFIED PLANT ID NUMBERS:

15-9, 16-01, 26-01, 25-9 CORRECT PLANT ID NUMBERS FOR THIS UNIT:

26-01, 25-9, Note:

Electric motors 15-9 and 16-01 are used in Unit 1 functions and are included in Equipment Item 33 for Unit 1.

ITEMIZED DEFICIENCIES AND RESPONSES:

1.

Equipment qualification not establis,hed.

A.

Qualified life or replacement schedule not identified.

B.

Program established to identify aging degradation.

C.

Criteria regarding radiation not satisfied.

...The licensee has not established the qualification of a lubricant for use....

In addition, the radiation evaluation states that the only material that will not withstand the radiation environment is the motor winding RTD cable....

l The failure analysis does not indicate if the operator could be misled by the failure of this device and could possibly snut off the motor....

The analysis concludes that the motors should withstand an accident dose of 2.8x106 Rads, not the 1.0x108 Rads level shown on the licensee's SCEW sheets."

RESPONSE

I An evaluation has been performed to determine the thermal aging characteristics of this motor [1]. The evaluation was based on the motor materials of construction, material testing, ambient and motor operating temperatures, and the operating requirements of the motor. On the basis of this evaluation, it i

is concluded that the Electric Machinery Manufacturing Company motors used as containment spray pump motors at Prairie Island are qualified for 40 years of l

operation.

There are no equipment qualification maintenance or replacement requirements, j

outside of normal preventative maintenance. Preventative maintenance includes general inspection of the motor and periodic replacement of the motor lubri-cant, Chevron SRI-2. This lubricant has been environmentally qualified (see Equipment Item 62) and was therefore not specifically addressed in this evaluation.

l t

J NORTHERN STATES POWER COMPANY TER Response PRAIRIE ISLAND NUCLEAR GENERATING PLANT July 29, 1983 Page 2.2-33b ITEMIZED DEFICIENCIES AND RESPONSES (Cont.):

The radiation evaluation of these motors states that the only material poten-tially unqualified to the required dose of 2.8x106 Rads is the motor-winding RTD extension cable. The temperature signal is used for indication purposes only and is not used as an automatic shut-down mechanism. Failure of the RTD extension cable resulting in erroneus motor winding temperature data will not mislead the plant operator. The SCEW for this equipment item has been revised to include the results of the analyses performed on these motors.

On the basis of the evaluations performed, and sunnarized herein, all concerns raised in the TER have been adequately resolved. This equipment item is therefore categorized in Category I.A and is fully qualified.

EQUIPMENT ITEM SPECIFIC

REFERENCE:

1.

EDS/Impell Calculation File 0910-200-RA-01, Revision 2, " Radiation and Ther'al Aging Analysis of Containment Spray Pump Motors," July 1983.

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NORTHERN STATES POWEP C0WANY TER Response PRAIRIE ISLAND NUCLEAR GENERATING PLANT July 29, 1983 Page 2.2-34a UNIT NUMBER: 2 TER EQUIPMENT ITEM NUMBER: 34 EQUIPMENT DESCRIPTION: Joy / Reliance Electric Motor Model 60027769 EQUIPMENT LOCATION: Reactor Building Unit 2 TER QUALIFICATION CATEGORY:

II.A TER-IDENTIFIED PLANT ID NUMBERS:

116-18, 126-18, 116-19, 126-32, 216-18, 226-18, 216-19, 226-32 CORRECT PLANT ID NUMBERS FOR THIS UNIT: 216-18, 226-18, 216-19, 226-32 Note:

Electric motors 116-18, 126-18, 116-19, and 126-32 are used in Unit i functions and are included in Equipment Item 34 for Unit 1.

ITEMIZED DEFICIENCIES AND RESPONSES:

1.

Equipment qualification not established.

A.

Adequate similarity between equipment and test specimen not estab-lished.

...The licensee does not, however, provide evidence from the manufacturer that the report is applicable to the installed motors and that they are from the 'line' of motors referenced in the report."

B.

Aging degradation not evaluated adequately.

C.

Qualified life or replacement schedule not established.

"The approach used by Joy to develop an accelerated aging program for the Reliance motors is based on the assumption that the insulation system is the limiting component. In many instances this would be correct; however, a material evaluation should be undertaken to substantiate this hypothe-sis. The lead cable insulation degraded to the point of failure (embrittlement) before the motor insulation failed during the post-event testing. Joy stated the following with respect to the anomaly:

'This separation of leads was caused by a combination of lead wire embrittlement due to the temperature and chemicals and vibration in the leads because of the manner in which the leads were connected. The problem occurred outside the conduit pipe where the leads were bent to allow for connection to the terminal plate before it was bolted down.

In an actual installation, this severe bend does not exist and, there-fore, the problem should not occur....

a. -the licensee has not presented a maintenance / surveillance program for the motor-insulation-to-lead splice, lead cable, or bearing system that could preclude age-related failure of these components.

b.

the licensee did not present the data that the ' life characteris-tics plot of the motor insulation' was based on.

NORTHERN STATES POWER C0ffANY TER Response PRAIRIE ISLAND NUCLEAR GENERATING PLANT July 29, 1983 Page 2.2-34b ITEMIZED DEFICIENCIES AND RESP 0'NSES (Cont.):

c.

a materials evaluation program was not performed to establish the basis of the thermal aging program."

D.

Criteria regarding radiation not satisfied.

"Although a separate effects radiation analysis was performed, the materials discussed were identified by Reliance specification number and not by chemical compo-sition so that the radiation damage threshold values could be verified.

The licensee has provided an engineering analysis of the shielding provided by the motor housing against the effects of beta radiation.

The licensee has not verified that the motor housing completely encases the materals susceptible to beta exposure."

RESPONSE

The environmental qualification of this equipment item was completely re-evaluated. Correspondence with the motor vendor, Reliance, indicates that the qualification report previously used was not applicable to the installed motor; however, applicable reports were identified. Utilizing the applicable qualification reports, environmental qualification including a 40 year qualified life and six months post-accident operation was justified. These results are documented in [1].

Thermal aging qualification is based on motor material degradation characterics and extrapolates test data to the Prairie Island specific parameters using the Arrhenius method. This qualification is based on test data from the motor vendor on insulation identical to that installed. A maintenance / surveillance program does exit for these motors that includes periodic inspection of'the motor-to-lead splice, lead cable, bearings, and motor lubicants.

On the basis of the evaluation perfonned in [1] and summarized above, all concerns raised have been adequately addressed and these motors are fully l

qualified for their intended survice at Prairie Island. This equipment item is now categorized in Category I.A. and is fully qualified.

EQUIPMENT ITEM SPECIFIC

REFERENCES:

1.

Impell Calculation File 0910-200-Joy-01, " Environmental Evaluation of Joy / Reliance Fan Motors," July 1983.

i i

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NORTHERN STATES POWER COMPANY TER Response PRAIRIE ISLAND NUCLEAR GENERATING PLANT July 29, 1983 Page 2.2-35a UNIT NUMBER: 2 TER EQUIPMENT ITEM NUMBER: 35 EQUIPMENT DESCRIPTION: Westinghouse Electric Motor Model L1054-1760/875 EQUIPMENT LOCATION: Reactor Building Unit 2 TER QUALIFICATION CATEGORY:

II.A TER-IDENTIFIED PLANT 10 NUMBERS:

117-2, 127-2, 117-3, 127-3, 217-2, 227-2, 217-3, 227-3 CORRECT PLANT ID NUMBERS FOR THIS UNIT: 217-2, 227-2, 217-3, 227-3 Note:

Electric motors 117-2, 127-2, 117-3, and 127-3 are used in Unit 1 functions and are included in Equipment Item 35 for Unit 1.

ITEMIZED DEFICIENCIES AND RESPONSES:

1.

Equipment qualification not established.

A.

Adequate similarity between equipment and test specimen not estab-lished. "The licensee has not stated that the installed motors have an integral air-to-water heat exchanger,..., has not established the bearing lubricant currently used in the motor,..., has not established the similarity of the motor-to-lead splice in the installed motor to the tested device,..., has not provided any documentation that indi-cates that the insulation system in the installed device is the same as that tested."

8.

Aging degradaton not evaluated adequately.

l C.

Qualified life or replacement schedule not established.

"Although the test report states that aging was performed to simulate 40 years in l

service, the licensee has not provided any analysis to show that the simulation applies to the plant-specific conditions.... The licensee has not provided a replacement / maintenance schedule for subcomponents."

D.

Criteria regarding temperature / pressure exposure duration not adequate.

"The licensee has not provided any basis for the 2-month operating l

time."

In addition, the following comment was provided.

The licensee has not indicated if the motor is equipped with an air-to-water heat exchanger.

If it is, the licensee has not evaluated the effect of beta entering through the air intake of the heat exchanger."

RESPONSE

The Westinghouse fan cooler motors installed at Prairie Island are mounted' vertically and are equipped with an integral air to water heat exchanger. The m,

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l NORTHERN STATES POWER CONFANY TER Response PRAIRIE ISLAND NUCLEAR GENERATING PLANT July 29, 1983 Page 2.2-35b ITEMIZED DEFICIENCIES AND RESPONSES (Cont.):

motor, heat exchanger, and fans are totally enclosed. Chevron SRI-2 lubricating grease is used for bearing lubrication. This lubricant has been environmentally qualified with no identified deficiencies (see Equipment Item 62). All field splices are installed following NSP Work Instruction 000-03-001 for cable splicing and terminations. Each of the splices and terminations used in safety-related applications have been environmentally qualified. The installed motor insulation system is thermalastic epoxy identical to that tested in WCAP 7829.

Correspondence with the equipment vendor, Westinghouse, indicates that quali-fication testing documented in WCAP 7829 is directly applicable to the RCFC motors installed.at Prairie Island [1].

An aging evaluation has been performed to correlate the simulated aging in the test program to the in-service conditions at Prairie Island [2]. The results of this evaluation show that a qualified life in excess of 40 years has been simulated by the test using the Arrhenius methodology. There are no require-ments for subcomponent replacement in the 40 year qualified life of the motors.

Although there are no specific equipment qualification maintenance require-ments, these motors are on a preventative maintenance program that periodically inspects the motors.

WCAP 7829 documents the qualification to long term (up to one year) post accident operating requirements based on testing and analysis.

In essence, the motor heat exchanger maintains bearing and insulation temperatures low enough during post accident conditions to preclude adverse degradation.

As noted above, these motors are totally enclosed with an integral air-to-water heat exchanger. There are no vent openings on the motor and no potential for intrusion of beta radiation through the water intake.

Thus, the motor enclo-sure does provide sufficient shi~elding against beta radiation.

On the basis of the evaluations performed and the discussion provided above, l

all identified deficiencies in the environmental qualification of this equip-ment item have been adequately resolved. Westinghouse fan cooler motors are therefore classified in Category I.A and are fully qualified.

EQUIPMENT _ ITEM SPECIFIC

REFERENCES:

1.

Westinghouse Electric Company, Water Reactor Divisions letter from P. Van Teslaar to K. Becker of EDS Nuclear, February 1, 1982.

2.

Impell Calculation File 0910-200-WES-01, Revision 0, " Thermal Aging Analysis of Westinghouse Motors," July 1983.

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i NORTHERN STATES POWER COMPANY TER Response PRAIRIE ISLAND NUCLEAR GENERATING PLANT July 29, 1983

~

Page 2.2-36 UNIT NUMBER: 2 TER EQUIPMENT ITEM NUMBER: 36 EQUIPMENT DESCRIPTION:

Westinghouse Electric Motor Model HSDP EQUIPMENT LOCATION: Auxiliary-Building TER QUALIFICATION CATEGORY:

II.A TER-IDENTIFIED PLANT ID NUMBERS:

'15-1, 16-5, 26-3, 25-5 CORRECT PLANT ID NUMBERS FOR THIS UNIT:

26-3, 25-5 Note:

Electric motors 15-1 and 16-5 are used in Unit 1 functions and are included in Equipment Item 36 for Unit 1.

ITEMIZED DEFICIENCIES AND RESPONSES:

1.

Equipment qualification not ' established.

A.

Adequate similarity between equipment and test specimen not estab-lished.

"The licensee has-not established the applicability of the referenced report to the installed device. WCAP-8754 states that'the

~

device tested was a formette made of Class B thermalastic epoxy stator j

insulation. WCAP-7829 relates to testing of windings of the same type for radiation tolerance and testing of Westinghouse S#723A773-G05 i

lubricant for radiation resistance. The licensee's SCEW states: ' Motor, Westinghouse, HSD-P'. No attempt has been made by the licensee' to establish that the installed motor and subcomponents are the same as those tested."

l

RESPONSE

l A project-has been initiated to re-evaluate the environmental qualification of Westinghouse motors. The motor vendor has been contacted to identify the applicable qualification test report, based on motor materials of construc-tion. Once this identification has been made, a complete qualification evalua-tion will be performed for all environmental parameters. We expect that this t

evaluation will be completed by January 1, 1984, and that any necessary modifications or replacements will be performed prior to November 30, 1985.

i

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N'ORTHERN S'TATES POWER COPFANY TER Response 1

PRAIRIE ISLAiID NUCLEAR GENERATING PLANT July 29, 1983 Page 2.2-37 UNIT NUMBER: 2 s

TER EQUIPMENT ITEM tlUMBER:

37 EQUIPMENT DESCRIPTION: Westingnouse Electric Motor Model HSDP EQUIPMENT LOCATION: Auxiliary Building TER QUALIFI. CATION CATEGORY:

II.A TER-IDENTIFIED PLANT ID NUMBERS:

15-4, 16-4, 25-4, 26-4 CORRECT PLANT ID NUMBERS FOR THIS UNIT:

25-4, 26-4 Note:

Electric motors 15-4 and 16-4 are used in Unit 2 functions and are included in Equipment Item 37 for Unit 1.

ITEMlZED DEFICIENCIES AND RESPONSES:

l.

Equipment qualification not established.

e' f[

A.

Adequate similarity between equipment and test specimen not estab-lished.

"The licen:;ee has not e:;tablished the applicability of the referereed report to the installed device. WCAP-8754 states that the device teste'd was a formette made of Clas.s B thermalastic epoxy stator insulation. WCAP-7629 relates to. testing of windings of the same type for radiation tolerance and testing of Westinghouse S#723A773-G05 lubricant.for radiation resistance. The licensee's SCEW states: ' Motor,

+

Westinghouse, HSD-P'.

No attempt has been made by the licensee to establish that the installed motor and subcomponents are the same as those tested."

RESPONSE

A project has been initiated to re-evaluate the environmental qualification of Westinghouse motors. The motor vendor has been contacted to identify the applicable qualifict. tion test report, based on motor materials of construc-tion. Once this identification has been made, a complete qualification evalua-tion will be performed for all environmental parameters. We expect that this evaluation will De completed by January 1, 1984, and that any necessary modifications or replacements will be performed prior to November 30, 1985.

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NORTHERN STATES POWER COMPANY TER Response P?AIRIE ISLAND NUCLEAR GENERATING PLANT July 29, 1983 Page 2.2-38 UNIT NUMBER: 2 TER EQUIPMENT ITEM NUMBER:

38 EQUIPMENT DESCRIPTION: Barton Flow Transmitter Model 332 EQUIPMENT LOCATION: Auxiliary Building TER QUALIFICATION CATEGORY:

I.B TER-IDENTIFIED PLANT ID NUMBERS:

23073, 23074, 23075, 23076 CORRECT PLANT ID NUMEERS FOR THIS UNIT: 23075, 23076 Note:

Flow transmitters 23073 and 23074 are used in Unit 1 functions and are included in Equipment Item 38 for Unit 1.

ITEMIZED DEFICIENCIES AND RESPONSES:

1.

Equipment modification required to establish qualification.

RESPONSE

These transmitters were originally identified for relocation to a mild envi-ronment. However, for main.tenance reasons, they will be replaced with qualified transmitters. Rosemount 1153 Series B transmitters have been ordered and will be installed during Unit 2 Cycle 8 and prior to November 30, 1985. Once this replacement has taken place, this equipment item will be classifed in Category I.A and will be fully qualified.

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= _ _

NORTHERN STATES POWER COPFANY TER Response PRAIRIE ISLAND NUCLEAR GENERATING PLANT July 29, 1983 Page 2.2-39 UNIT NUMBER: 2 TER EQUIPMENT ITEM NUMBER: 39 EQUIPMENT DESCRIPTION: Foxboro Flow Transmitter Model E13DH(MCA)

EQUIPMENT LOCATION: Auxiliary Building TER QUALIFICATION CATEGORY:

II.A TER-IDENTIFIED PLANT ID NUMBERS: 23021, 23022, 23023, 23024, 23025, 23026, 23027, 23028 i

CORRECT PLANT ID NUMBERS FOR THIS UNIT: 23025, 23026, 23027, 23028 Note:

Flow transmitters 23021 23022, 23023, and 23024 are used in Unit 1 functionsandthatareIncludedinEquipmentItem39forUnit1.

ITEMIZED DEFICIENCIES AND RESPONSES:

1.

Equipment qualification not established.

j A.

Adequate similarity between equipment and test specimen not estab-lished. "The licensee has not stated the output current range of their Foxboro transmitters.

(The tables of note 1 differentiate between 4-20 i

and 10-50 ma models.) Therefore, accuracy tolerances of -12% for the EllGM and -9% for the E13DH must be assumed. Since the licensee has failed to specify the required accuracy for these transmitters, com-pliance with accuracy criteria is suspect."

RESPONSE

I Safety-related equipment accuracies are currently being reviewed and defined as part of the Prairie Island emergency preparedness program. These instrument accuracies will be plant-specific and based on various postulated accident scenarios. Based on the functional requirements of these transmitters, we expect the instrument accuracies experienced in qualification testing to be acceptable.

If it is determined that the accuracies experienced in the qualification testing are unacceptable, accident operating procedures will be modified accordingly.

s NORTHERN STATES POWER COMPANY TER Response PRAIRIE ISLAND NUCLEAR GENERATING PLANT July 29, 1983 Page 2.2-40a UNIT NUMBER: 2 TER EQUIPMENT ITEM NUMBER: 40 EQUIPMENT DESCRIPTION:

Rosemount Flow Transmitter Model ll53HA6 EQUIPMENT LOCATION: Reactor Building Unit 2

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TER QUALIFICATION CATEGORY:

II.B TER-IDENTIFIED PLANT ID NUMBERS: 23017, 23018, 23019, 23020 CORRECT PLANT ID NUMBERS FOR THIS UNIT: 23017, 23018, 23019, 23020 ITEMIZED DEFICIENCIES AND RESPONSES:

1.

Equipment not qualified.

"We note the following information abstracted from applicable and available qualification documentation associated with the overall NRC equipment environmental qualification review program:

"'Rosemount testing to gaalify a transmitter to meet IEEE 323-1974 require-ments has resulted in fatiure. A combination of thermal aging, irradiation, and chemical spray test specification parameters has resulted in failed components. The initial failed element was an 0-ring comprised of sulphur cured polyethylene rubber. This allowed steam / chemical spray to affect electronic components. The 0-ring mode of failure is attributed to high temperature vs. time necessary for the Arrhenius curve time compression to satisfy aging test requirements.'

" Based on the above considerations, this equipment item is placed in NRC qualification category II.B because applicable and available qualification information abstracted from documentation presented to the NRC as a result of the overall NRC equipment environmental qualification program reports current Rosemount testing to IEEE-323(74) criteria which resulted in failure of the test specimen."

RESPONSE

The TER deficiencies cited above have been addressed in a separate transmittal to the Director of Nuclear Reactor Regulation at the NRC. The evaluation submitted requested that this equipment item be reclassified as Category II.C based on the technical discussion presented. That position was accepted as noted in [1]. The aging qualification of this equipment item is being evaluated based on recently completed testing on the Rosemount 1153 Series B and 1153 Series D transmitters. Once that evaluation is complete, this equipment item will be fully qualified and classified in Category I.A.

I NORTHERN STATES POWER COMPANY TER Response PRAIRIE ISLAND NUCLEAR GENERATING PLANT July 29, 1983 Page 2.2-40b EQUIPMENT ITEM SPECIFIC

REFERENCES:

1.

NRC letter from Robert Clark to D. M. Musolf (NSP) dated June 3,1973, and attached safety evaluation concerning justification for continued operation for Prairie Island Nuclear Generating Plant, Unit Nos. I and 2, as Related to Environmental Qualification of Safety-Related Electrical Equipment Classified as Not Qualified.

A

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e NORTHERN STATES POWER COMPANY TER Response PRAIRIE ISLAND NUCLEAR GENERATING PLANT July 29, 1983 Page 2.2-41 UNIT NUMBER: 2 TER EQUIPMENT ITEM NUMBER:

41 EQUIPMENT DESCRIPTION: Magnetrol Level Transmiter Model A153FEP/VPXYTD EQUIPMENT LOCATION:

Reactor Building Unit 2 TER QUALIFICATION CATEGORY:

I.B TER-IDENTIFIED PLANT ID NUMBERS:

16796, 16811, 16909, 16910 CORRECT PLANT ID NUMBERS FOR THIS UNIT: 2LT-725, 2LT-726, 2LT-727A, 2LT-727B, 2LT-728A, 2LT-7288 ITEMIZED DEFICIENCIES AND RESPONSES:

1.

Equipment modification required to establish qualification.

RESPONSE

Magnetrol level transmitters have been replaced with qualified containment sump water level transmitters.

Delaval level transmitters model XM-54854-323 were installed and have recently completed a qualification test program which fully qualifies the level transmitter for the environmental conditions associated with the installed location.

Because replacement with a qualified transmitter has already taken place, this equipment item is now classified in Category I A and is fully qualified.

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6

. o NORTHERN STATES POWER C0ffANY TER Response '

PRAIRIE ISLAND NUCLEAR GENERATING PLANT July 29, 1983 Page 2.2-42 UNIT NUMBER: 2 TER EQUIPMENT ITEM NUMBER: 42 EQUIPMENT DESCRIPTION:

Barton Level Transmitter Model P386-351 EQUIPMENT LOCATION: Reactor Building Unit 2 TER QUALIFICATION CATEGORY:

I.B TER-IDENTIFIED PLANT ID NUMBERS: 24041, 24042, 24043, 24046, 24047, 24048 CORRECT' PLANT ID NUMBERS FOR THIS UNIT: 24046, 24047, 24048 Note:

Level transmitters 24041, 24042 and 24043 are all used in Unit i functions and are included in Equipment Item 42 for Unit 1.

ITEMIZED DEFICIENCIES AND RESPONSES:

1.

Equipment modification required to establish qualification.

RESPONSE

Qualified replacement transmitters have been ordered and will be installed during Unit 2, Cycle 7/8, and prior to the end of the second refueling outage after March 31, 1982.

Barton Model 764-351 level transmitters, which have successfully completed qualification testing, will be installed and will then be classified in Category I.A and be fully qualified.

NORTHERN STATES POWER COMPANY TER Response PRAIRIE ISLAND NUCLEAR GENERATING PLANT July 29, 1983 Page 2.2-43 UNIT NUMBER: 2 TER EQUIPMENT ITEM NUMBER: 43 EQUIPMENT DESCRIPTION: Foxboro Level Transmitter Model E13DHSAMI EQUIPMENT LOCATION: Reactor Building Unit 2 TER QUALIFICATION CATEGORY:

I.B TER-IDENTIFIED PLANT ID NUMBERS:

24080, 24081, 24082, 24083, 24084, 24085, 24086, 24087 CORRECT PLANT ID NUMBERS FOR THIS UNIT:

2LT-487, 2LT-488

~

Note:

Qualified transmitters with Plant ID numbers ILT-487 and lLT-488 for Unit 1 and 2LT-487 and 2LT-488 for Unit 2 were installed. Unit 1 transmitters are included as Equipment Item 43 for Unit 1.

ITEMIZED DEFICIENCIES AND RESPONSES:

1.

Equipment modification required to establish qualification.

RESPONSE

Qualified level transmitters have been installed and are designated with Plant ID numbers 2LT-487 and 2LT-488 for Unit 2.

Foxboro N-E13DH-IIAF level trans-mitters, which have successfully completed qualification testing, were installed. Because installation of qualified transmitters has already taken place, this equipment item 1s now classified on Category I.A and is fully qualified.

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l I

NORTHERN STATES POWER COMPANY TER Response PRAIRIE ISLAND NUCLEAR GENERATING PLANT July 29, 1983 Page 2.2-44a UNIT NUMBER: 2 TER EQUIPMENT ITEM NUMBER: 44 EQUIPMENT DESCRIPTION: Rosemount Pressure Transmitter ll53HA6 EQUIPMENT LOCATION: Reactor Building Unit 2 TER QUALIFICATION CATEGORY:

II.B TER-IDENTIFIED PLANT ID NUMBERS:

21102, 21159 CORRECT PLANT ID NUMBERS FOR THIS UNIT:

1-PT-709, 1-PT-710 Note:

These tranmitters are actually installed in Unit 1.

A new system was installed to monitor RCS-wide range pressure and plant ID numbers 1-PT-709 and 1-PT-710 have been assigned to these transmitters. The deficiencies identified for this equipment item will be addressed below.

ITEMIZED DEFICIENCIES AND RESPONSES:

1.

Equipment not qualified.

"We note the following information abstracted from applicable and available qualification documentation associated with the overall NRC equipment environmental qualification review program:

"'Rosemount testing to qualify a transmitter to meet IEEE 323-1974 require-ments has resulted in failure. A combination of thermal aging, irradia-j tion, and chemical spray test specification parameters has resulted in failed components. The initial failed element was an 0-ring comprised of sulphur-cured polyethylene rubber. This allowed steam / chemical spray to i

I affect electronic components. The 0-ring mode of failure is attributed to high temperature vs. time necessary for the Arrhenius curve time compression to satisfy aging test requirements.'

" Based on the above considerations, this equipment item is placed in NRC qualification category II.B because applicable and available qualification information abstracted from documentation presented to the NRC as a result of the overall NRC equipment environmental qualification program reports current Rosemount testing to IEEE-323(74) criteria which resulted in failure of the test specimen."

RESPONSE

The TER deficiencies cited above have been addressed in a separate transmittal to the Director of Nuclear Reactor Regulation at the NRC. The evaluation sub-mitted requested that this equipment item be reclassified as Category II.C

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NORTHERN STATES POWER C0WANY TER Response PRAIRIE ISLAND NUCLEAR GENERATING PLANT July 29, 1983 Page 2.2-44b based on the technical discussion presented. That position was accepted as noted in [1]. The aging qualification of this equipment item is being evalu-ated based on recently completed testing on the Rosemount 1153 Series B and 1153 Series 0 transmitters. Once that evaluation is complete, this equipment item will be fully qualified and classified in Category I.A.

EQUIPMENT ITEM SPECIFIC

REFERENCES:

1.

NRC letter from Robert Clark to D. M. Musolf (NSP) dated June 3, 1973, and attached safety evaluation concerning justification for continued operation for Prairie Island Nuclear Generating Plant, Unit Nos. 1 and 2, as Related to Environmental Qualification of Safety-Related Electrical Equipment Classified as Not Qualified.

l l

l l

o NORTHERN STATES POWER COMPANY TER Response PRAIRIE ISLAND NUCLEAR GENERATING PLANT July 29, 1983 Page 2.2-45 UNIT NUMBER: 2 TER EQUIPMENT ITEM NUMBER: 45 EQUIPMENT DESCRIPTION: Foxboro.Presure Transmitter Model E11GMSA01 EQUIPMENT LOCATION: Reactor Building Unit 2 TER QUALIFICATION CATEGORY:

I.8 TER-IDENTIFIED PLANT ID NUMBERS: PT-21164, PT-21165, PT-21166, PT-21167, PT-21168, PT-21169, PT-21170, PT-21171 CORRECT PLANT ID NUMBERS FOR THIS UNIT: PT-21168, PT-21169, PT-21170, PT-21171 Note:

Pressure transmitters PT-21164, PT-21165, PT-21166, and PT-21167 are all used in Unit i functions and are included in Equipment Item 45 for Unit 1.-

ITEMIZED DEFICIENCIES ANO RESPONSES:

1.

Equipment modification required to establish qualification.

RESPONSE

Foxboro model N-EllGM-H101-AE pressure transmitters, which have successfully passed qualification testing, have been installed. Because qualification has already taken place, this equipment item is now classified as Category I.A and is fully qualified.

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NORTHERN STATES POWER C0WANY TER Response PRAIRIE ISLAND NUCLEAR GENERATING PLANT July 29, 1983 Page 2.2-46 UNIT NUMBER: 2 TER EQUIPMENT ITEM NUMBER:

46 EQUIPMENT DESCRIPTION: Foxboro Pressure Transmitter Model E11GM-SAE1 (MCA)

EQUIPMENT LOCATION: Reactor Building Unit 2 TER QUALIFICATION CATEGORY:

I.B TER-IDENTIFIED PLANT ID NUMBERS:

21146, 21147, 21148, 21150, 21154, 21155, 21156, 21157 CORRECT PLANT ID NUMBERS FOR THIS UNIT: 21154, 21155, 21156, 21157 Note:

Pressure transmitters 21146, 21147, 21148, and 21150 are all used in Unit 1 functions and are included in Equipment Item 46 for Unit 1 ITEMIZED DEFICIENCIES AND RESPONSES:

1.

Equipment modification required to establish qualification.

RESPONSE

Safety-related equipment accuracies are currently being reviewed and defined as'part of the Prairie Island emergency preparedness program. These instrument accuracies will be plant-specific and based on various postulated accident scenarios. Based on the functional requirements of these transmitters, we expect the instrument accuracies experienced in '1ualification testing to be acceptable.

If it is determined that the accuracies experienced in the qualification testing are unacceptable, accident operating procedures will be modified accordingly.

NORTHERN STATES POWER COPFANY TER Response PRAIRIE ISLAND NUCLEAR GENERATING PLANT July 29, 1983 Page 2.2-47 UNIT NUMBER: 2 TER EQUIPMENT ITEM NUMBER: 47 EQUIPMENT DESCRIPTION:

Rosemount Pressure Transmitter Model ll53GA9 EQUIPMENT LOCATION: Reactor Building Unit 2 TER QUALIFICATION CATEGORY:

II.B TER-IDENTIFIED PLANT ID NUMBERS:

1-PT-729, 2-PT-729 CORRECT PLANT ID NUMBERS FOR THIS UNIT: 2-PT-729 Note:

Pressure transmitter 1-PT-729 is used in Unit 1 functions and is included in Equipment Item 47 for Unit 1.

ITEMIZED DEFICIENCIES AND RESPONSES:

1.

Equipment not qualified.

"We note the following information abstracted from applicable and available qualification documentation associated with the overall NRC equipment environmental qualification review program:

"'Rosemount testing to qualify a transmitter to meet IEEE 323-1974 require-ments has resulted in failure. A combination of thermal aging, irradia-tion, and chemical spray test specification parameters has resulted in failed components. The initial failed element was an 0-ring comprised of sulphur-cured polyethylene rubber. This allowed steam / chemical spray to affect electronic components. The 0-ring mode of failure is attributed to high temperature vs. time necessary for the Arrhenius curve time compression to satisfy aging test requirements.'

" Based on the above considerations, this equipment item is placed in NRC qualification category II.B because applicable and available qualification information abstracted from documentation presented to the NRC as a result of the overall NRC equipment environmental qualification program reports current Rosemount testing to IEEE-323(74) criteria which resulted in failure of the test specimen."

RESPONSE

This equipment item has been deleted from the safety-related equipment masterlist and no longer requires environmental qualification.

l l

NORTHERN STATES POWER COPPANY TER Response PRAIRIE ISLAND NUCLEAR GENERATING PLANT July 29, 1983 Page 2.2-48 UNIT NUMBER: 2 i

TER EQUIPMENT ITEM NUMBER: 48 EQUIPMENT DESCRIPTION:

Foxboro Pressure Transmitter Model EllGM(MCA)

EQUIPMENT LOCATION: Auxiliary Building TER QUALIFICATION CATEGORY:

II.A TER-IDENTIFIED PLANT ID NUMBERS: 21203, 21204, 21205, 21209, 21210, 21211 CORRECT PLANT ID NUMBERS FOR THIS UNIT:

21209, 21210, 21211 Note:

Pressure transmitters 21203, 21204, and 21205 are used in Unit 1 functions and are incuded in Equipment Item 48 for Unit 1.

ITEMIZED DEFICIENCIES AND RESPONSES:

.l. Equipment qualification not established.

A.

Adequate similarity between equipment and test specimen not estab-lished.

"The licensee has not stated the output current range of their Foxboro transmitters.

(The tables of note 1 differentiate between 4-20 and 10-50 ma models.) Therefore, accuracy tolerances of -12% for the EllGM and -9% for the E13DH must be assumed. Since the licensee has failed to specify the required accuracy for these transmitters, com-pliance with accuracy criteria is suspect."

RESPONSE

Safety-related equipment accuracies are currently being reviewed and defined as part of the Prairie Island emergency preparedness program. These instrument accuracies will be plant-specific and based on various postulated accident 1

scenarios. Based on the functional requirements of these transmitters, we expect tne instrument accuracies experienced in qualification testing to be acceptable.

If it is determined that the accuracies experienced in the qualification testing are unacceptable, accident operating procedures will be modified accordingly.

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NORTHERN STATES POWER COMPANY TER Response PRAIRIE ISLAND NUCLEAR GENERATING PLANT July 29, 1983 Page 2.2-49 UNIT NUMBER: 2 TER EQUIPMENT ITEM NUMBER:

49 EQUIPMENT DESCRIPTION: Foxboro Pressure Transmitter Model EllGM(MCA)

EQUIPMENT LOCATION: Auxiliary Building TER QUALIFICATION CATEGORY:

II.A TER-IDENTIFIED PLANT ID NUMBERS: 21206, 21207, 21208 CORRECT PLANT ID NUMBERS FOR THIS UNIT:

21206, 21207, 21208 ITEMIZED DEFICIENCIES AND RESPONSES:

1.

Equipment qualification not established.

A.

Adequate similarity between equipment and test specimen not estab-lished.

"The licensee has not stated the output current range of their Foxboro transmitters.

(The tables of note 1-differentiate between 4-20 and 10-50 ma models.) Therefore, accuracy tolerances of -12% for the EllGM and -9% for the E130H must be assumed.

Since the licensee has failed to specify the required accuracy for these transmitters, com-pliance with accuracy criteria is suspect."

RESPONSE

Safety-related equipment accuracies are currently being reviewed and defined as part of the Prairie Island emergency preparedness program. These instrument accuracies will be plant-specific and based on various postulated accident scenarios. Based on the functional requirements of these transmitters, we expect the instrument accuracies experienced in qualification testing to be acceptable.

If it is determined that the accuracies experienced in the qualification testing are unacceptable, accident operating proceaures will be modified accordingly.

NORTHERN STATES POWER COMPANY TER Response PRAIRIE ISLAND NUCLEAR GENERATING PLANT July 29, 1983 Page 2.2-50 UNIT NUMBER: 2 TER EQUIPMENT ITEM NUMBER:

50 EQUIPMENT DESCRIPTION:

Endevco Accelerometer Model 2273AM20 EQUIPMENT LOCATION: Reactor Building Unit 2 TER QUALIFICATION CATEGORY:

I.B TER-IDENTIFIED PLANT ID NUMBERS: None CORRECT PLANT ID NUMBERS FOR THIS UNIT:

2EQ-443, 2EQ-444, 2EQ-445 ITEMIZED DEFICIENCIES AND RESPONSES:

1.

Equipment modification required to establish qualification.

RESPONSE

The testing on this component is nearly complete.

If, as a result of testing, modifications to the installed equipment are required, the modifications will be performed during Unit 2 refueling cycle 8/9 and prior to November.30, 1985.

Once the qualification testing is complete and all necessary modifications have been made, this equipment item will be categorized in Category I.A and will be fully qualified.

l i

NORTHERN STATES POWER COMPANY TER Response PRAIRIE ISLAND NUCLEAR GENERATING PLANT July 29, 1983 Page 2.2-51 UNIT NUMBER: 2 TER EQUIPMENT ITEM NUMBER: 51 EQUIPMENT DESCRIPTION: Unholtz-Dickey Amplifier Model 22CA-2TR EQUIPMENT LOCATION: Reactor Building Unit 2 TER QUALIFICATION CATEGORY:

I.8 TER-IDENTIFIED PLANT ID NUMBERS: None CORRECT PLANT ID NUMBERS FOR THIS UNIT: 2EE-443,.2EE-444, 2EE-445 ITEMIZED DEFICIENCIES AND RESPONSES:

1.

Equipment modification required to establish qualification.

RESPONSE

The testing on this component is nearly complete.

If, as a result of testing, modifications to the installed equipment are required, the modifications will be performed during Unit 2 refueling cycle 8/9 and prior to November 30, 1985.

Once the qualification testing is complete and all necessary modifications have been made, this equipment item will be categorized in Category I.A and will be fully qualified.

4 NORTHERN STATES POWER COMPANY.

TER Response PRAIRIE ISLAND NUCLEAR GENERATING PLANT July 29, 1983 Page 2.2-52 UNIT NUMBER: 2 TER EQUIPMENT ITEM NUMBER:

52 EQUIPMENT DESCRIPTION: Fisher Controls Signal Converter Model 546 EQUIPMENT LOCATION: Auxilary Building TER QUALIFICATION CATEGORY:

II.A TER-IDE:ITIFIED PLANT ID NUMBERS:

SC-35084, SC-35029 CORRECT PLANT ID NUMBERS FOR THIS UNIT:

SC-35084, SC-35029 ITEMIZED DEFICIENCIES AND RESPONSES:

1.

Equipment qualification not established.

A.

Documented evidence of qualification not adequate.

"In reviewing the licensee's introductory letter to this response dated August 26, 1981, no specific information with respect to this equipment could be located."

RESPONSE

The safety function of this equipment item has been reviewed, and it is con-cluded that it should be removed from the safety-related equipment masterlist.

The April 30, 1982, SER response provided this information.

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e NORTHERN STATES POWER COMPANY TER Response PRAIRIE ISLAND NUCLEAR GENERATING PLANT July 29, 1983 Page 2.2-53 UNIT NUMBER: 2 TER EQUIPMENT ITEM NUMBER:

53 EQUIPMENT DESCRIPTION: Trinity Electric Thermometer Model K81 EQUIPMENT LOCATION: Reactor Building unit 2 TER QUALIFICATION CATEGORY:

1.B TER-IDENTIFIED PLANT ID NUMBERS:

15456, 15457, 15458, 15459, 15610, 15611, 15612, 15613 CORRECT PLANT ID NUMBERS FOR THIS UNIT:

15610, 13611, 15612, 15613 Note:

Thermometers 15456, 15457, 15458, and 15459 are all used in Unit 1 functions and are included in Equipment Item 53 for Unit 1.

ITEMIZED DEFICIENCIES AND RESPONSES:

1.

Equipment modification required to establish qualification.

RESPONSE

Incore thermocouple reference junction boxes have been deleted from the harsh environment safety-related equipment masterlist. A new system utilizing quali-fied incore thermocouple cable exiting containment through qualified contain-ment penetrations has been installed.

NORTHERN STATES POWER COMPANY TER Response PRAIRIE ISLAND NUCLEAR GENERATING PLANT July 29, 1983 Page 2.2-54 UNIT NUMBER: 2 TER EQUIPMENT ITEM NUMBER: 54 EQUIPMENT DESCRIPTION: Rosemount RTD Model 176KS EQUIPMENT LOCATION: Reactor Building Unit 2 TER QUALIFICATION CATEGORY:

II.2 TER-IDENTIFIED PLANT ID NUMBERS:

15314 CORRECT PLANT ID NUMBERS FOR THIS UNIT:

15314 ITEMIZED DEFICIENCIES AND RESPONSES:

1.

Equipment qualification not established.

A.

Documented evidence of qualification not adequate.

B.

Aging degradation not evaluated adequately.

C.

Qualified life or replacement schedule not established.

D.

Required profile not enveloped adequately.

E.

Criteria regarding spray not satisfied.

F.

Criteria regarding functional testing not satisfied.

G.

Criteria regarding instrument accuracy not satisfied.

The detailed evaluation and comments resulting in the identification of these deficiencies was not provided due to the proprietary nature of the information.

RESPONSE

A detailed evaluation was not provided in the TER due to the proprietary nature of the information, thus, a detailed technical response cannot be provided.

Environmental qualification is based on testing described in WCAP-9157.

In essence, environmental qualification is limited by the radiation resistance of l

the RTD. Based on the functional requirements and radiation exposure at the i

installed location, RCS wide-range RTDs are qualified for 12 years of normal operation and two weeks of monitoring following a secondary system line break.

Replacement of these RTDs is currently scheduled in 1986 for Unit 2.

On the basis of the testing described above, these RTDs are fully qualified for their intended use until replacement occurs at the end of the 12-year qualified life.

NORTHERN STATES POWER C0WANY TER Response PRAIRIE ISLAND NUCLEAR GENERATING PLANT July 29, 1983 Page 2.2-55 i

i l

UNIT NUMBER: 2 TER EQUIPMENT ITEM NUMBER: 55 EQUIPfENT DESCRIPTION: Sostman RTD Model 119018 EQUIPMENT LOCATION: Reactor Building Unit 2 TER QUALIFICATION CATEGORY:

II.A TER-IDENTIFIED PLANT ID NUMBERS:

15331, 15332, 15333, 15334, 15315, 15322, 15323 CORRECT PLANT ID NUMBERS FOR THIS UNIT:

15315, 15322, 15323 Note:

RTDs 15331, 15332, 15333, and 15334 are used in Unit 1 functions and are included in Equipment Item 55 for Unit 1.

ITEMIZED DEFICIENCIES AND RESPONSES:

1.

Equipment qualification not established.

s A.

Documented evidence of qualification not adequate.

B.

Aging degradation not evaluated adequately.

C.

Qualified life or replacement schedule not established.

D.

Required profile not enveloped adequately.

E.

Criteria regarding spray not satisfied.

F.

Criteria regarding instrument accuracy not satisfied.

The detailed evaluation and comments resulting in the identification of these deficiencies was not provided due to the proprietary nature of the i

information.

RESPONSE

A detailed evaluation was not provided in the TER due to the proprietary nature of the information, thus, a detailed technical response cannot be provided.

Environmental qualification is based on testing described in WCAP-9157.

In i

essence, environmental qualification is limited by the radiation resistance of the RTD. Based on the functional requirements and radiation exposure at the installed location, RCS wide range RTDs are qualified for 12 years of normal operation and two weeks of monitoring following a secondary system line break.

Replacement of these RTDs is currently scheduled in 1986 for Unit 2.

On the basis of the testing described above, these RTDs are fully qualified for their j

intended use until replacement occurs at the end of the 12-year qualified life.

4

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r NORTHERN STATES POWER C0W ANY TER Response PRAIRIE ISLAND NUCLEAR GENERATING PLANT July 29, 1983 Page 2.2-56 UNIT NUMBER: 2 TER EQUIPMENT ITEM NUMBER:

56 EQUIPMENT DESCRIPTION:

Boston Insulated Wire Electrical Control Cable Model Bostrad 7 EQUIPMENT LOCATION: Reactor Building Unit 2 and Auxiliary Building TER QUALIFICATION CATEGORY.:

II.A TER-IDENTIFIED PLANT ID NUMBERS:

None CORRECT PLANT ID NUMBERS FOR THIS UNIT: None ITEMIZED DEFICIENCIES AND RESPONSES:

1.

Equipment qualification not established.

A.

Documented evidence of qualification not established.

B.

Criteria regarding submergence not satisfied.

"The licensee SCEW sheet indicates that the cables can become submerged and states that an accelerated water absorption test qualifies the cable for submergence.

The water absorption tests demonstrate suitability for demineralized water at atmospheric pressure, but do not simulate the pressure, temperature, chemistry, and radiation conditions of the liquid in the containment sump after LOCA."

RESPONSE

Several tests have been performed on BIW cables to evaluate their ability to operate in a submerged condition. The tests follow the outline of IEEE 383-1974, which specifically states that voltage withstand tests be performed on cables submerged in tap water. BIW cable was immersed in tap water at 75*C (167'F) for 14 days with no deleterious effects.

In addition to water absorp-tion tests, the cables were exposed to 0.1 immersion aging at 121*C (250*F) and boric acid aging of irradiated samples in varying pH solutions was performed with no noted anomalies.

Cable samples were also exposed to a 7-day LOCA test with high temperatures, high pressures, 100% RH, and a boric acid / sodium hydroxide chemical solution. The combination of these tests far exceeds the test necessary to show submergence qualification.

In general, the combination of LOCA testing and water absorption testing of immersed samples adequately simulates the postulated accident environment to document submergence quali-fication in accordance with IEEE 383-1974.

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NORTHERN STATES POWER C0WANY TER Response PRAIRIE ISLAND NUCLEAR GENERATING PLANT July 29, 1983 Page 2.2-57a UNIT NUMBER: 2 TER EQUIPMENT ITEM NUMBER: 57 EQUIPMENT DESCRIPTION: Kerite Electrical Control Cable Models FR/FR and HTK/FR EQUIPMENT LOCATION: Reactor Building Unit 2 and Auxiliary Building TER QUALIFICATION CATEGORY:

II.A TER-IDENTIFIED PLANT ID NUMBERS: None CORRECT PLANT ID NUMBERS FOR THIS UNIT: None ITEMIZED DEFICIENCIES AND RESPONSES:

1.

Equipment qualification not established.

A.

Adequate similarity between equipment and test specimen not established.

B.

Aging degradation not evaluated adequately.

C.

Qualified life or replacement schedule not established.

D.

Criteria regarding spray satisfied.

The detailed evaluation and comments resulting in the identification of these deficiencies was not provioed due to the proprietary nature of the information.

RESPONSE

Because a detailed evaluation was not provided in tne TER due to the proprie-tary nature of the information, a detailed technical response cannot be i

provided.

Three types of Kerite cable are used in safety-related applications at Prairie Island: HT-Kerite/FR, FR/FR, and HT-Kerite/HTNS. Each of these cables have been evaluated and their environmental qualification is documented in [1].

Correspondence with the equipment vendor, Kerite, has resulted in obtaining the applicable qualification reports for each cable type [2]. Aging qualificaticn is based on aging tests performed on cable samples correlated to the Prairie Island environment using the Arrhenius methodology. The results of this evalu-ation show that the cables are qualified for greater than 40 years of service with no replacement required. Chemical spray qualification has been established based on type testing to chemical solutions simulating the Prairie Island containment spray solution.

NORTHERN STATES POWER COMPANY TER Response PRAIRIE ISLAND NUCLEAR GENERATING PLANT July 29, 1983 Page 2.2-57b ITEMIZED DEFICIENCIES AND RESPONSES (Cont.):

~

Based on the environmental evaluation summarized above, all identified defi-ciencies have been adequately resolved. Kerite electrical cable is therefore categorized in Category I.A and is fully qualified.

EQUIPMENT ITEM SPECIFIC

REFERENCES:

1.

EDS Calculation File 0910-205-KER-01, Revision 1, " Environmental Qualifica-tion of Kerite Electrical Cables," December 8, 1981.

2.

Kerite Company letter from the office of E. N. Sleight to Terry M. Maxey, EDS Nuclear, December 8, 1981.

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I NORTHERN STATES POWER COMPANY TER Response PRAIRIE ISLAND NUCLEAR GENERATING PLANT July 29, 1983 Page 2.2-58 UNIT NUMBER: 2 TER EQUIPMENT ITEM NUMBER:

58 EQUIPMENT DESCRIPTION:

Okonite Electrical Cable Model Okonite/ Neoprene EQUIPMENT LOCATION: Reactor Building Unit 2 and Auxiliary Building TER QUALIFICATION CATEGORY:

II.A TER-IDENTIFIED PLANT ID NUMBERS: None CORRECT PLANT ID NUMBERS FOR THIS UNIT: None ITEMIZED DEFICIENCIES AND RESPONSES:

1.

Equipment qualification not established.

A.

Criteria.regarding submergence not satisfied.

"The licensee has pro-vided documentation which references several Okonite test reports and laboratory test reports for the cable which would establish qualifica-tion for the cable in the auxiliary building but does not provide qual-ification for submergence in containment"... "The water absorption tests demonstrate suitability for demineralized water at atmospheric pressure, but do not simulate the pressure, temperature, chemistry and radiation conditions of the liquid in the containment sump after LOCA.

RESPONSE

Submergence qualifiation of Okonite cables is based on sequential type testing which included high temperature, high pressure, 100% RH, chemical spray simula l

tion, irradiation, and submergence testing. These tests were performed follow-l ing the guidelines of IEEE 383-1974. While it is true that water absorption testing alone does not simulate the post-LOCA environment in the containment sump, the combination of tests described above does simulate this environment.

i The accelerated water absorption test after the LOCA testing was of sufficient duration, in excess of 18 months at 90*C (194*F), to provide adequate margin for submergence qualification.

On the basis of the environmental evaluation performed and for which the submergence qualifiation is summarized above, all deficiencies have been adequately resolved and this equipment item is fully qualified. Okonite cables are therefore categorized in Category I.A.

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NORTHERN STATES POWER C0WANY TER Response PRAIRIE ISLAND NUCLEAR GENERATING PLANT July 29, 1983 Page 2.2-59a UNIT NUMBER: 2 TER EQUIPMENT ITEM NUMBER:

59 EQUIPMENT DESCRIPTION: Okonite Electrical Cable Splice Model 604-92-1571 EQUIPMENT LOCATION: Reactor Building Unit 2 and Auxiliary Building TER QUALIFICATION CATEGORY:

II.A TER-IDENTIFIED PLANT ID NUMBERS: None CORRECT PLANT ID NUMBERS FOR THIS UNIT: None ITEMIZED DEFICIENCIES AND RESPONSES:

1.

Equipment qualification not established.

A.

Adequate similarity between equipment and test specimen not estab-lished.

"The letters reproduced on page Sa are not certification that the test report applies."

B.

Aging degradation not evaluated adequately.

C.

Qualified life or replacement schedule not established.

D.

Criteria regarding submergence not satisfied.

"The licensee's SCEW sheet indicates that the cables can become submerged and states that an accelerated water absorption test qualifies the cabli for submergence.

The water absorption test demonstrates suitability for demineralized water at atmospheric pressure, but does not simulate the pressure, temperature, chemistry, and radiation conditions of the liquid in the containment sump after LOCA."

RESPONSE

Correspondence with the equipment vendor [1] resulted both in the identifica-tion of the materials used in the splice and the procurement of the applicable qualification test [2]. Utilizing this test data, the environmental qualifica-tion of the splice was documented [3]. Thermal aging qualification is based on pre-aging performed on the test specimens correlated to the Prairie Island environment utilizing the Arrhenius methodology.

As a result of the thermal aging evaluation, this equipment item is qualified for an excess of 40 years of service with no requirements for replacement.

j Submergence qualification is based on imersion testing in water following accident testing (which included chemical spray exposure). This test sequence and method does follow the qualification requirements outlined in IEEE 383-1974. While it is true that water absorption testing alone does not simulate

NORTHERN STATES POWER COMPANY TER Response PRAIRIE ISLAND NUCLEAR GENERATING PLANT July 29, 1983 Page 2.2-59b 1

ITEMIZED DEFICIENCIES AND RESPONSES (Cont.):

the post-LOCA environment in the containment sump, the combination of tests described above does simulate this environment.

On the basis of the environmental evaluation performed and summarized above, all deficiencies have been adequately resolved and this equipment item is fully qualified. Okonite splice kit 604-92-1571 is therefore categorized in Category I.A.

EQUIPMENT ITEM SPECIFIC

REFERENCES:

1.

Record of conversation between Mr. J. Rodgers (Okonite) and Mr. W. Fargo (EDS) dated August 18, 31, and September 11, 1981.

2.

LOCA Qualification Report for Okoguard Insulating Cables and T-95 and T-35 Splicing Tapes. Okonite Report NQRN-3, June 23, 1980.

3.

EDS Calculation File 0910-205-0KO-02, Revision 0, " Environmental Qualifica-tion of Okonite Splices," December 1981.

I I

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NORTHERN STATES POWER COMPANY TER Response PRAIRIE ISLAND NUCLEAR GENERATING PLANT July 29, 1983 Page 2.2-60 UNIT NUMBER: 2 TER EQUIPMENT ITEM NUMBER:

60 EQUIPMENT DESCRIPTION: Allen Bradley Terminal Strips Model 1492-CD3 EQUIPMENT LOCATION: Reactor Building Unit 2 and Auxiliary Building TER QUALIFICATION CATEGORY:

I.B TER-IDENTIFIED PLANT ID NUMBERS: None CORRECT PLANT ID NUMBERS FOR THIS UNIT: None ITEMIZED DEFICIENCIES AND RESPONSES:

1.

Equipment modification required to establish qualification.

RESPONSE

Environmental qualification testing is still in progress. Assuming successful completion of the testing, this equipment item will be c.ategorized in Category I.A and will be completely qualified.

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NORTHERN STATES POWER COMPANY TER Response PRAIRIE ISLAND NUCLEAR GENERATING PLANT July 29, 1983 Page 2.2-61 UNIT NUMBER: 2 TER EQUIPMENT ITEM NUMBER:

61 EQUIPMENT DESCRIPTION: General Electric Epoxy Model 7010/74010A EQUIPMENT LOCATION:. Reactor Building Unit 2 and Auxiliary Building TER QUALIFICATION CATEGORY:

I.B TER-IDENTIFIED PLANT ID NUMBERS: None CORRECT PLANT 10 NUMBERS FOR THIS UNIT:

None i

ITEfflZEDDEFICIENCIESANDRESPONSES:

1.

Equipment modification required to establish qualification.

RESPONSE

This equipment item is used in conjunction with Equipment Item 60, Allen Bradley terminal strips, for which environmental qualification testing is still in progress. Assuming successful completion of the testing, this equipment item will be categorized in Category I.A and will be fully qualified.

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NORTHERN STATES POWER COMPANY TER Response PRAIRIE ISLAND NUCLEAR GENERATING PLANT July 29, 1983 Page 2.2-62 UNIT NUMBER: 2 TER EQUIPMENT ITEM NUMBER:

62 EQUIPMENT DESCRIPTION: Chevron SRI-2 Lubricant EQUIPMENT LOCATION: Reactor Building Unit 2 TER QUALIFICATION CATEGORY:

I.A TER-IDENTIFIED PLANT ID NUMBERS:

None CORRECT PLANT ID NUMBERS FOR THIS UNIT:

None ITEMIZED DEFICIENCIES AND RESPONSES:

There are no deficiencies identified in the environmental qualification of this equipment item.

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l NORTHERN STATES POWER COMPANY TER Response PRAIRIE ISLAND NUCLEAR GENERATING PLANT July 29, 1983 Page 2.2-63 UNIT NUMBER: 2 TER EQUIPMEhT ITEM NUMBER: 63 EQUIPMENT DESCRIPTION: Mobil DTE Lubricant EQUIPMENT LOCATION: Auxiliary Building TER QUALIFICATION CATEGORY:

I.A TER-IDENTIFIED PLANT ID NUMBERS: None CORRECT PLANT ID NUMBERS FOR THIS UNIT: None ITEMIZED DEFICIENCIES AND RESPONSES:

There are no deficiencies identified in the environmental qualification of this equipment item.

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4 NORTHERN STATES POWER COMPANY TER Response PRAIRIE ISLAND NUCLEAR GENERATING PLANT July 29, 1983 Page 2.2-64 UNIT NUMBER: 2 TER EQUIPMENT ITEM NUMBER: 64 EQUIPMENT DESCRIPTION:

Bussman Fuseholder Model HEBA EQUIPMENT LOCATION: Auxiliary Building TER QUALIFICATION CATEGORY:

II.A TER-IDENTIFIED PLANT ID NUMBERS: None CORRECT PLANT ID NUMBERS FOR THIS UNIT: None ITEMIZED DEFICIENCIES AND RESPONSES:

1.

Equipment qualification not established.

A.

Criteria regarding steam exposure not adequate.

"An oven aging test does not provide qualification for steam exposure."

RESPONSE

Bussman HEB-A fuseholder. Tre waterproof fuseholders which completely encapsu-late the fuse and protect it against damage from water, weather, salt spray, corrosive fumes, and the like. Correspondence with the equipment vendor indicates that the HEB-A fuseholders have been qualified for immersion in accordance with military specification MIL-STD-2020, April 14, 1969. More specifically, this test consists of 5 cycles of 60-minute immersions in a hot bath of tap water at 65*C, followed by 60-minute immersions in a saturated solution of sodium chloride and water at O'C.

The test sample successfully passed this inmersion testing. The waterproof fuseholders are enclosed in NEMA-4 boxes, which provide further protection against the effects of moisture.

On the basis of the testing performed and installation of NEMA-4 enclosures, there is adequate assurance of qualification to relative humidity conditions.

This equipment item is therefore categorized in Cateagory I.A and is fully qualified.

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NORTHERN STATES POWER COMPANY TER Response PRAIRIE ISLAND NUCLEAR GENERATING PLANT July 29, 1983 Page 2.2-65 UNIT NUMBER: 2 TER EQUIPMENT ITEM NUMBER:

65 EQUIPMENT DESCRIPTION: General Electric Motor Control Center Model 7700 Series EQUIPMENT LOCATION: Auxiliary Building TER QUALIFICATION CATEGORY:

I.B TER-IDENTIFIED PLANT ID NUMBERS:

lLAl, ILA2, 2LAl, 2LA2, IM1, IMA2 CORRECT PLANT ID NUMBERS FOR THIS UNIT:

lLA2, 2LA2, IMA2 Note:

Motor Control Centers ILA1, 2LAl, IM1 are all used in Unit 1 functions and are included in Equipment Item 65 for Unit 1.

ITEMIZED DEFICIENCIES AND RESPONSES:

1.

Equipment modification required to establish qualification.

RESPONSE

New motor control centers have been ordered and will be used to relocate required safety-related loads to a mild environment.

Installation will be completed during Unit 2 Cycle 8 and prior to November 30, 1985. Once this has occurred, this item will no longer be on the harsh environment safety-related equipment masterlist.

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NORTHERN STATES POWER COMPANY TER Response PRAIRIE ISLAND NUCLEAR GENERATING PLANT July 29, 1983 Page 2.2-66 UNIT NUMBER: 2 TER EQUIPMENT ITEM NUMBER:

66 EQUIPMENT DESCRIPTION: Creiger Electrical DC Distribution Panel EQUIPMENT LOCATION: Reactor Building Unit 2 TER QUALIFICATION CATEGORY:

I.B TER-IDENTIFIED PLANT ID NUMBERS: Noria CORRECT PLANT ID NUMBERS FOR THIS UNIT: Panel 253, 263 Note:

All safety-related loads from these panels have been relocated to Panels 153 and 163.

ITEMIZED DEFICIENCIES AND RESPONSES:

1.

Equipment modification required to establish qualification.

RESPONSE

All safety-related loads to these panels have been relocated to distribution panels installed in the auxiliary building. Therefore, this equipment item has been deleted from the safety-related equipment masterlist. Distribution panels located in the auxiliary building have been added to the safety-related equip-ment masterlist, and environmental qualification for these panels is nearing completion.

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NORTHERN STATES POWER COMPANY TER Response PRAIRIE ISLAND NUCLEAR GENERATING PLANT July 29, 1983 Page 2.2-67 UNIT NUMBER: 2 TER EQUIPMENT ITEM NUMBER:

67 EQUIPMENT DESCRIPTION: Barton Flow Switch Model 288A EQUIPMENT LOCATION: Auxiliary Building TER QUALIFICATION CATEGORY:

II.C TER-IDENTIFIED PLANT ID NUMBERS:

18252, 18253, 18268, 18269 CORRECT PLANT ID NUMBERS FOR THIS UNIT:

18268, 18269 No vu Flow switches 18252 and 18253 are used in Unit i function and are included in Equipment Item 67 for Unit 1.

ITEMIZED DEFICIENCIES AND RESPONSES:

1.

Equipment satisifes all requirements except qualified life or replacement schedule justified.

A.

Aging degradation not evaluated adequately.

B.

Qualified life or replacement schedule not established.

"The licensee has provided PGR 3252 as evidence of qualification for this equipment item. This test report envelopes the plant-specific conditions for the expected radiation environment. The licensee has not, however, identi-fied the materials of construction or evaluated the effects of aging on the device."

RESPONSE

A project was initiated to thoroughly evaluate the qualified life of Barton Model 288A flow switches, based on the aging degradation properties of the constituent materials. This evaluation is documented in [1]. The results show that these flow switches have a qualified life in excess of 40 years at the installed location in the Prairie Island auxiliary building. The completion of this thermal aging evaluation addresses the deficiencies cited above. This equipment item is now categorized in Category I.A and is fully qualified.

EQUIPMENT ITEM SPECIFIC

REFERENCES:

1.

Impell Calculation File 0910-200-BAR-01, "Barton 288A Thermal Aging Evaluation," July 1983.

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NORTHERN STATES POWER COMPANY TER Response PRA1RIE ISLAND NUCLEAR GENERATING PLANT July 29, 1983 Page 2.2-68 UNIT NUMBER: 2 TER EQUIPMENT ITEM NUMBER:

68 EQUIPMENT DESCRIPTION:

D. G. O'Brien Electrical Penetration Model PR-2 (TI)

EQUIPMENT LOCATION: Reactor Building Unit 2 TER QUALIFICATION CATEGORY:

I.A TER-IDENTIFIED PLANT ID NUMBERS: None CORRECT PLANT ID NUMBERS FOR THIS UNIT:

None ITEMIZEC DEFICIENCIES AND RESPONSES:

There are no deficiencies identified in the environmental qualification of this equipment item.

a NORTHERN STATES POWER COMPANY TER Response PRAIRIE ISLAND NUCLEAR GENERATING PLANT July 29, 1983 Page 2.2-69 UNIT NUMBER: 2 TER EQUIPMENT ITEM NUMBER: 69 EQUIPMENT DESCRIPTION:

D. G. O'Brien Electrical Penetration Model PR-12 (LVP)

EQUIPMENT LOCATION: Reactor Building Unit 2 TER QUALIFICATION CATEGORY:

I.A TER-IDENTIFIED PLANT 10 NUMBERS: None CORRECT PLANT ID NUMBERS FOR THIS UNIT:

None ITEMIZED DEFICIENCIES AND RESPONSES:

There are no deficiencies identified in the environmental qualification of this equipment item.

/

1 NORTHERN STATES POWER COMPANY TER Response PRAIRIE ISLAND NUCLEAR GENERATING PLANT July 29, 1983 j

Page 2.2-70 UNIT NUMBER: 2 TER EQUIPMENT ITEM NUMBER:

70 EQUIPMENT DESCRIPTION:

D. G. O'Brien Electrical Penetration Model PR-110 (MVP)

EQUIPMENT LOCATION: Reactor Building Unit 2 TER QUALIFICATION CATEGORY:

I.A TER-IDENTIFIED PLANT ID NUMBERS: None CORRECT PLANT ID NUMBERS FOR THIS UNIT: None ITEMIZED DEFICIENCIES AND RESPONSES:

There are no deficiencies identified in the environmental qualification of this equipment item.

NORTHERN STATES POWER C0W ANY TER Response PRAIRIE ISLAND NUCLEAR GENERATING PLANT July 29, 1983 Page 2.2-71 UNIT NUMBER: 2 TER EQUIPMENT ITEM NUMBER:

71 EQUIPMENT DESCRIPTION: Kerite Electrical Cable Splice D51001/0S1102 EQUIPMENT LOCATION: Reactor Building Unit 2 and Auxiliary Building TER QUALIFICATION CATEGORY:

II.A TER-IDENTIFIED PLANT ID NUMBERS:

None CORRECT PLANT ID NUMBERS FOR THIS UNIT:

None ITEMIZED DEFICIENCIES AND RESPONSES:

1.

Equipment qualification not established.

A.

Adequate similarity between equipment and test specimen not estab-lished.

"In lieu of the detailed description discussed above it would be acceptable for the licensee to obtain certification from the manufacturer identifying what test report (s) apply to the cables furnished for installation.

If applicability is established the splice would be qualified."

RESPONSE

The equiment manufacturer, Kerite, was contacted prior to initiating the envi-ronmental qualification evaluation of Kerite splices 05-1001 and DS-1002. The result of this correspondence [1] was the identification and procurement of the applicable qualification test [2]. This confirmation of test report appli-cability by the equipment manufacturer satisfies the certification requirement described in the TER deficiency.

Therefore, this equipment item is fully qualified and is categorized in Category I.A.

EQUIPMENT ITEM SPECIFIC

REFERENCES:

1.

Kerite Company letter from the office of Mr. E. N. Sleight to Mr. T. M.

Maxey (EDS Nuclear) dated November 4,1981.

2.

Tests of Electrical Cables Under Simultaneous Exposure to Gama Radiation, Steam, and Chemical Spray while Electrically Energized," FIRL Final Report F-C4020-2, March 1975.

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NORTHERN STATES POWER COMPANY TER Response PRAIRIE ISLAND NUCLEAR GENERATING PLANT July 29, 1983 Page 2.2-72a UNIT NUMBER: 2 TER EQUIPMENT ITEM NUMBER:

72 EQUIPMENT DESCRIPTION:

Okonite Electrical Splicing Tape Model T95 EQUIPMENT LOCATION: Reactor Building Unit 2 and Auxiliary Building TER QUALIFICATION CATEGORY:

II.A TER-IDENTIFIED PLANT ID NUMBERS: None CORRECT PLANT ID NUMBERS FOR THIS UNIT:

None ITEMIZED DEFICIENCIES AND RESPONSES:

1.

Equipment qualification not established.

A.

Criteria regarding submergence not satisfied. "The test report also contains a description of water absorption tests. However, the accelerated water absorption testing in demineralized water at atmospheric pressure does not simulate or qualify the equipment for the pressure, temperature, radiation and chemistry of the liquid in the containment sump after a LOCA.

RESPONSE

Okonite electrical cable splicing tapes T-95 and T-35 are integral components in the Okonite splice kit model 604-92-1571-(Equipment Item 59). The environ-mental qualification testing on the 604-92-1571 splice kit included testing on the T-95 and T-35 splicing tapes [1] and is directly applicable to the installed splices at Prairie Island as documented in [2]. Submergence quali-fication is based on innersion testing in water following accident testing (which included chemical spray exposure). This test sequence and method does follow the qualification requirements outlined in IEEE 383-1974. While it's true that water absorption testing alone does not simulate the post-LOCA envi-ronment in the containment sump, the combination of tests described above does simulate this environment.

On the basis of the environmental evaluation performed [3] and summarized above, all deficiencies have been adequately resolved and this equipment item is fully qualified. Okonite splicing tapes T-95 and T-35, contained in splicing kit 604-92-1571, are fully qualified. This equipment item is therefore cate-gorized in Category I.A.

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NORTHERN STATES POWER C0W ANY TER Response PRAIRIE ISLAND NUCLEAR GENERATING PLANT July 29, -1983 Page 2.2-72b ITEMIZED DEFICIENCIES AND RESPONSES (Cont.):

EQUIPMENT ITEM SPECIFIC

REFERENCES:

1.

LOCA Qualification Report for Okoguard Insulating Cables and T-95 and T-35 Splicing Tapes, Okonite Report NQRN-3, June 23, 1980.

2.

Record of Conversation between Mr. J. Rodgers (Okonite) and Mr. W. Fargo (EDS) dated August 18, 31, and September 11, 1981.

3.

EDS Calculation File 0910-205-0K0-2, Revision 0, " Environmental Qualifica-tion of Okonite Splices," December 1981.

NORTHERN STATES POWER C0lfANY TER Response PRAIRIE ISLAND NUCLEAR GENERATING PLANT July 29, 1983 Page 2.2-73a UNIT NUMBER: 2 TER EQUIPMENT ITEM NUMBER:

73 EQUIPMENT DESCRIPTION:

Okonite Electrical Cable Splice Model T35 EQUIPMENT LOCATION: Reactor Building Unit 2 and Auxiliary Building TER QUALIFICATION CATEGORY:

II.A TER-IDENTIFIED PLANT ID NUMBERS: None CORRECT PLANT ID NUMBERS FOR THIS UNIT: None ITEMIZED DEFICIENCIES AND RESPONSES:

1.

Equipment qualification not established.

A.

Criteria regarding submergence not established.

The test report also contains a description of water absorption tests. However, the accelerated water absorption testing in demineralized water at at'.cspheric pressure does not simulate or qualify the equipment for pressure, temperature, radiation and chemistry of the liquid in the coitainment sump after LOCA."

RESPONSE

Okonite electrical cable splicing tapes T-95 and T-35 are integral components in the Okonite splice kit model 604-92-1571 (Equipment Item 59). The environ-mental qualification testing on the 604-92-1571 splice kit included testing on the T-95 and T-35 splicing tapes [1] and is directly applicable to the installed splices at Prairie Island as documented in [2]. Submergence qualifi-cation is based on immersion testing in water following accident testing (which included chemical spray exposure). This test sequence and method does follow the qualification requirements outlined in IEEE 383-1974. While it's true that water absorption testing alone does not simulate the post-LOCA environment in the containment sump, the combination of tests described above does simulate l

this environment.

On the basis of the environmental evaluation performed [3] and sumarized above, all deficiencies have been adequately resolved and this equipment item is fully qualified. Okonite splicing tapes T-95 and T-35, contained in splicing kit 604-92-1571, are fully qualified. This equipment item is therefore cate-gorized in Category I.A.

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NORTHERN STATES POWER COMPANY TER Response PRAIRIE ISLAND NUCLEAR GENERATING PLANT July 29, 1983 Page 2.2-73b ITEMIZED DEFICIENCIES AND RESPONSES (Cont.):

EQUIPMENT ITEM SPECIFIC

REFERENCES:

1.

LOCA Qualification Report for Okoguard Insulating Cables and T-95 and T-35 Splicing Tapes, Okonite Report NQRN-3, June 23, 1980.

2.

Record of Conversation between Mr. J. RodgErs (0konite) and Mr. W. Fargo (EDS) dated August 18, 31, and September 11, 1981.

3.

EDS Calculation File 0910-205-0K0-2, Revision 0, " Environmental Qualifica-tion of Okonite Splices," December 1981.

NORTHERN STATES POWER COMPANY TER Response PRAIRIE ISLAND NUCLEAR GENERATING PLANT July 29, 1983 Page 2.2-74 UNIT NUMBER: 2 TER EQUIPMENT ITEM NUMBER:

74 NOTE: This equipment item number was not included in tne TER EQUIPMENT DESCRIPTION: Limitorque Motorized Valve Actuator Model SMB-00 EQUIPMENT LOCATION: Auxiliary Building TER QUALIFICATION CATEGORY:

II.A TER-IDENTIFIED PLANT ID NUMBERS:

None CORRECT PLANT ID NUMBERS FOR THIS UNIT:

MV-32019, MV-32020 Note:

These actuators were incorrectly included in Equipment Item 74 for Unit 1.

They are actually used in Unit 2 functions and are therefore included in the Unit 2 TER response.

ITEMIZED DEFICIENCIES AND RESPONSES:

1.

Equipment qualification not established.

A.

Adequate similarity between equipment and test specimen not established.

B.

Aging degradation not evaluated adequately.

C.

Qualified life or replacement schedule not established.

Several pages of detailed notes were provided in the TER pertaining to deficiencies in the environmental qualification of this equipment item.

RESPONSE

A project has been initiated to thoroughly evaluate and document the environ-mental qualification of Limitorque valve actuators. Each of the concerns raised

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in the TER will be addressed in that evaluation. We expect that the evaluation will be finalized by January 1, 1984, and that any necessary modi-fications or repl< cements will be performed prior to November 30, 1985.

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i NORTHERN STATES POWER C0WANY TER Response PRAIRIE ISLAND NUCLEAR GENERATING PLANT July 29, 1983 Page 3-1 3.0 GENERAL REFERENCES 1.

Technical Evaluation Report, " Review of Licensees' Resolution of Out-standing Issues from NRC Equipment Environmental Qualification Safety Evaluation Reports (F-ll and B-60)", March 29,1983, Franklin Research Center.

2.

D. E. G1bberts (NSP) letter to J.G. Keppler (NRC), March 13, 1980,

" Response to IE Bulletin 79-01B"; FRC TER Reference [1].

3.

D. E. Gibberts and L. O. Mayer (NSP) letter to J. G. Keppler (NRC),

October 31, 1980, " Final Response to IE Bulletin 79-01B, Prairie Island Nuclear Generating Plant"; FRC TER Reference [3].

4.

D. E. Gibberts and L. O. Mayer (NSP) letter to J. G. Keppler (NRC),

January 22, 1980, " Response to IE Bulletin 79-01B, Supplement 3"; FRC TERReference[13].

5.

U.S. NRC Office of Nuclear Reactor Regulation Safety Evaluation Report for Prairie Island Units 1 and 2, May 12, 1981; FRC TER Reference

[14].

6.

L. O. Mayer (NSP) Letter to NRC, August 26, 1981, " Prairie Island Nuclear Generating Plant - Response to IE Bulletin 79-018 Safety Evaluation Report"; FRC TER Reference [15].

7.

L. O. Mayer (NSP) Letter to NRC, April 30, 1982, " Prairie Island Nuclear Generating Plant - Response to IE Bulletin 79-01B Safety i

Evaluation Report"; FRC TER Reference [59].

8.

D. Musolf (NSP) letter to NRC, May 19, 1983, " Prairie Island Nuclear Generating Plant - Response to 10 CFR-50.49, Environmental Qualifica-tion of Electrical Equipment Important to Safety for Nuclear Power Plants."

l

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