ML20215L854
| ML20215L854 | |
| Person / Time | |
|---|---|
| Site: | Wolf Creek  |
| Issue date: | 04/30/1987 |
| From: | Udy A EG&G IDAHO, INC., IDAHO NATIONAL ENGINEERING & ENVIRONMENTAL LABORATORY |
| To: | NRC |
| Shared Package | |
| ML20215L832 | List: |
| References | |
| CON-FIN-D-6001 EGG-NTA-7415, GL-83-28, TAC-57385, NUDOCS 8706260194 | |
| Download: ML20215L854 (18) | |
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CONFORfMNCE TO GENERIC LETTER 83-28, ITEM 2.2.1--
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DISCLAIMER i
This book was prepared as an account of work sponsored by an agency of the United 1
States Government. Neither the United States Government nor any agercy thereof, j
nor any of their employees, makes any warranty, express or implied, or assumes any j
legal liability or responsibility for the accuracy, completeness, or usefulness of any 1
information, apparatus, product or process disclosed, or represents that its use would not infringe pnvately owned nghts. References herein to any specific commercial product, proriss, or service by trade name, trademark, manufacturer, or otherwise, does not necessarily constitute or imply its endorsement, recommendation, or favonng by the United States Government or any agency thereof. The views and opinions of authors expressed herein do not necessanly state or reflect those of the United States Government or any agency thereof.
4
EGG-NTA-7415 TECHNICAL EVALUATION REPORT CONFORMANCE TO GENERIC LETTER 83-28, ITEM 2.2.1--
EQUIPMENT CLASSIFICATION FOR ALL OTHER SAFETY-RELATED COMPONENTS-WOLF CREEK l
Docket No. 50-482 Alan C. Udy I
1 Published April 1987 Idaho National Engineering Laboratory EG&G Idaho, Inc.
Idaho Falls, Idaho 83415 Prepared for the U.S. Nuclear Regulatory Commission Washington, D.C.
20555 Under 00E Contract No. DE-AC07-76ID01570 FIN No. D6001
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I ABSTRACT This EG&G Idaho, Inc., report provides a review of the submittals from the Wolf Creek Generating Station regarding conformance to Generic Letter 83-28, Item 2.2.1.
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Docket No. 50-482
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FOREWORD This report is supplied as part of the program for evaluating licensee / applicant conformance to Generic' Letter 83-28, " Required Actions Based on Generic Implications.of Salem ATWS Events.".This work is being-conducted for the U.S. Nuclear Regulatory Commission,10ffice of Nuclear Reactor Regulation,- Division of PWR Licensing-A, by EG&G Idaho, Inc., NRR and-I&E Support Branch.
The U.S. Nuclear Regulatory Commission funded this work under the authorization B&R No. 20-19-10-11-3, FIN No. D6001.
Docket No. 50-482 TAC No. 57385 iii
CONTENTS ABSTRACT..............................................................
ii FOREWORD.............................................................
iii 1.
INTRODUCTION......................................................
1 2.
REVIEW CONTENT AND FORMAT........................................
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3.
ITEM 2.2.1 - PROGRAM.............................................
3 J
l 3.1 Guideline..................................................
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3.2 Evaluation................................................
3 J
3.3 Conclusion................................................
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l 4.
ITEM 2.2.1.1 - IDENTIFICATION CRITERIA...........................
4 i
4.1 Guideline..................................................
4 4.2 Evaluation.................................................
4 4.3 Conclusion.................................................
4 1
5.
ITEM 2.2.1.2 - INFORMATION HANDLING SYSTEM.......................
5 5.1 Guideline..................................................
5 5.2 Evaluation.................................................
5 5.3 Conclusion.................................................
5 6.
ITEM 2.2.1.3 - USE OF EQUIPMENT CLASSIFICATION LISTING...........
6 6.1 Guideline..................................................
6 6.2 Evaluation.................................................
6 6.3 Conclusion.................................................
6 7.
ITEM 2.2.1.4 - MANAGEMENT CONTROLS...............................
7 7.1 Guideline..................................................
7 7.2 Evaluation...............................................
7
- 7. 3 Conclusion.................................................
7 8.
ITEM 2.2.1.5 - DESIGN VERIFICATION AND PROCUREMENT...............
8 8.1 Guideline...........
8 8.2 Evaluation.................................................
8 8.3 Conclusion.................................................
8 9.
ITEM 2.2.1.6 "IMPORTANT TO SAFETY" COMPONENTS..................
9 9.1 Guideline..................................................
9 10.
CONCLUSION.......................................................
10 11.
REFERENCES........................................................
11 iv
CONFORMANCE TO GENERIC LETTER 83-28, ITEM 2.2.1--
EQUIPMENT CLASSIFICATION FOR ALL OTHER SAFETY-RELATED COMPONENTS:
WOLF CREEK 1.
INTRODUCTION On February 25, 1983, both of the scram circuit breakers at Unit 1 of the Salem Nuclear Power Plant failed to open upon an automatic reactor trip signal from the reactor protection system.
This incident was terminated manually by the operator about 30 seconds after the initiation of the automatic trip signal.
The failure of the circuit breakers was determined te be related to the sticking of the undervoltage trip attachment.
Prior to this incident, on February 22, 1983, at Unit 1 of the Salem Nuclear Power Plant, an automatic trip signal was generated based on steam generator low-low level during plant startup.
In this case, the reactor was tripped manually by the operator almost coincidentally with the automatic trip.
Following these incider.ts, on February 28, 1983, the NRC Executive Director for Operations (EDO), directed the NRC staff to investigate and report on the generic implications of these occurrences at Unit 1 of the Salem Nuclear Power Plant.
The results of the staff's inquiry into the generic implications of the Salem unit incidents are reported in NUREG-1000, " Generic Implications of the ATWS Events at the Salem Nuclear Power Plant." As a result of this investigation, the Commission (NRC) 1 requested (by Generic Letter 83-28 dated July 8, 1983 ) all licensees of opercting reactors, applicants for an operating license, and holders of construction permits to respond to the generic issues raised by the analyses of these two ATWS events.
This report is an evaluation of the responses submitted by the Kansas Gas and Electric Company, the licensee for the Wolf Creek Generating Station, for Item 2.2.1 of Generic Letter 83-28. The documents reviewed as a part of this evaluation are listed in the references at the end of this report.
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REVIES CONTENT AND' FORMAT i
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Item 2,2.1 ofzGeneric Letter 83-28 requests the licensee or applicant l
to submit, for the. staff review, a. description of their programs for safety-related equipment classification including supporting information,.
in considerable detail, as indicated in the guideline section for each sub-item within this report.
As previously indicated, each of the six sub-items of Item 2.2.1 is evaluated in a separate section in which the guideline is presented; an
- evaluation of the licensee's/ applicant's response is made; and conclusions about:the programs'of the licensee or applicant for safety-related equipment classification are drawn.
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ITEM 2.2.1 - PROGRAM 3.1 Guideline Licensees and applicants should confirm that an equipment classification program exists which provides assurance that all safety-related components are designated as safety-related on all plant documents, drawings and procedures and in the information handling system that is used in accomplishing safety-related activities, such as work orders for repair, maintenance and surveillance testing and orders for replacement parts.
Licensee and applicant responses which address the features of this program are evaluated in the remainder of this report.
3.2 Evaluation The licensee for the Wolf Creek Generating Station responded to these requirements with submittals dated November 15, 1983 and February 29, 1984.3 2
The licensee also referred to a previous submittal dated March 10, 1983.4 These' submittals include information that describes their safety-related equipment classification program.
In the review of the licensees response to this item, it was assumed that the information and documentation supporting this program is available for audit upon request.
The licensee states that administrative procedures require the use of the computerized Q-list to determine the safety-related status of components and procedures.
The licensee states that all work requests are performed in accordance with the operations quality program with identification of whether the equipment is safety-related or not, and identify the proper work restraints.
3.3 Conclusion We have reviewed the licensee's information and, in general, find that the licensee's response is adequate.
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ITEM 2.2.1.1 - IDENTIFICATION CRITERIA l
4.1 Guidel'ine j
The applicant or licensee should confirm that their program used for equipment classification includes criteria used for identifying components as safety-related.
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4.2 Evaluation
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The licensee's response gives the criteria used for identifying safety-related equipment and components.
A component is considered safety-related if it is required to assure:
(a) the integrity of the reactor coolant system pressure boundary, (b) the capability to achieve and maintain a safe shutdown or (c) the capability to prevent or to mitigate the consequences of an accident which would result in potential offsite exposures.
1 4.3 Conclusion We find that the criteria used in the identification of safety-related i
components meets the requirements of Item 2.2.1.1 and are acceptable.
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5.
ITEM 2.2.1-.2 - INFORMATION HANDLING SYSTEM 5.1 Guideline-I The licensee or applicant should confirm that the program for equipment classification includes an information handling system that is used to identify safety-related components.
The response should confirm that this information handling. system includes a list of safety-related equipment and that procedures exist which govern its develcpment and-validation.
5.2 Evaluation I
The 1(censee's submittals identify the "Q-List" as the computerized 1
index that -identifies safety-related components. The description included the methods used for its development, verification and validation.
5.3 Conclusion l
We find that the information contained in the licensee's submittals is sufficient for us to conclude that the licensee's information handling system for equipment classification meets the guideline requirements.
Therefore, the information provided by the licensee for this item is j
acceptable.
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6.
ITEM 2.2.1.3 - USE OF EQUIPMENT CLASSIFICATION LISTIWG l
6.1 Guideline The licensee's or applicant's description should confirm that their f
1 program for equipment classification includes criteria and procedures which l
govern how station personnel use the equipment classification information
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handling system to determine that an activity is safety-related and what procedures for maintenance, surveillance, parts replacement and other activities defined in the introduction to 10 CFR 50, Appendix B, apply to safety-related components.
6.2 Eyvaluation The licensee states that the computerized Q-list is available and is used by the appropriate station and office personnel to identify the safety-related status of equipment and components.
The licensee states that safety-related activities are identified using the Q-list and are done in accordance with approved procedures governed by the operations quality program. The licensee also states that the activities listed above are performed in accordance with approved procedures.
6.3 Conclusion We find that the licensee's description of plant administrative controls and procedures meets the requirements of this item and is, therefore, acceptable.
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ITEM 2.2.1.4 - MANAGEMENT CONTROLS i
l 7.1 Guideline 1
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The applicant or licensee should confirm that the management controls 1
used to verify that the procedures for preparation, validation and routine l
utilizationoftheinformationhandlingsystemhavebeenfollowed.
7.2 Evaluation
.The' licensee states that the Q-list will be controlled, maintained and i
updated in accordance with written procedures of the Nuclear Plant i
Engineering Division.
The licensee also states.that a s'upplemental Q-list, indicating the safety-related status.of subcomponents and parts of those items identified in 'the Q-list,- will be prepared and. maintained separately from the Q-list by the Plant Manager and his staff. The licensee-also identifies quality assurance surveillance and audits as management controls that address this item.
7.3. Conclusion i
We find that the licensee's description meets the requirements of this 1
item and is, therefore, acceptable.
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ITEM 2.2.1.5 - DESIGN VERIFICATION AND PROCOREMENT 8.1 Guideline The applicant's or licensee's submittal should. document that past usage demonstrates that appropriate design verification and qualification testing is specified for the procurement of safety related components and parts. The specifications should include qualification testing for expected safety service conditions and provide support for the applicant's/ licensee's receipt of testing documentation to support the limits of life recommended by the supplier.
If such documentation'is not available, confirmation that the present program meets these requirements should be provided.
8.2 Evaluation The licensee's submittals state thct specifications for safety-related components include design verification'and qualification testing and analysis for environmental conditions.
These tests and analyses are documented in a historical file. The licensee states that specifications imposed by administrative procedures on safety-related items specify the appropriate technical and quality requirements, including environmental and i
seismic testing.
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8.3 Conclusion The licensee's response for this item is considered to be complete.
The information provided addresses the concerns of this item and is acceptable.
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ITEM 2.2.1.6 "IMPORTANT TO SAFETY" COMPONENTS 9.1 Guideline Generic Letter 83-28 states that the licensee's equipment classification program should include (in addition to the safety-related components) a broader class of components designated as "Important to Safety." However, since the generic letter does not require the licensee to furnish this information as part of their response, review of this item will not be performed.
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CONCLUSION Based on our review of the licensee's response to the specific requirements of Item 2.2.1, we find that the information provided by the licensee to resolve the concerns of Items 2.2.1.1, 2.2.1.2, 2.2.1.3, l
i' 2.2.1.4 and 2.2.1.5 meet the requirements of Generic Letter 83-28 and is acceptable.
Item 2.2.1.6 was not reviewed as noted in Section 9.1.
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REFERENCES 1.
NRC Letter, D. G. Eisenhut to all Licensees of Operating Reactors, Applicants for Operatino License, and Holders of Construction Permits,
" Required Actions 0:sca on Generic Implications of Salem ATWS Events (Generic Letter 83-28)," July 8,1983.
2.
Letter, Kansas Gas and Electric Company (G. L. Koester) to NRC (H. R. Denton), " Response to Generic Letter 83-28," November 15, 1983.
3.
Letter, Kansas Gas and Electric Company (G. L. Koester) to NRC (H. R. Denton), " Response to Generic Letter 83-28," February 29, 1984.
4.
Letter, Standardized Nuclear Unit Power Plant System (N. A. Petrick) to NRC (H. R. Denton), " Environmental Qualification of Safety-related Electrical Equipment," March 10, 1983, File: 0278.
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m iN TaucricNe oN r E..vos 3 LEAVE SLANK 2 TITLE ANO S68 TITLE CONFORMANCE TO GENERIC LETTER 83-28, ITEit'2.2.1--
I i EQUIPMENT CLASSIFICATION FOR ALL OTHER SEFETY-RELATED A oari a** oar co**'uso -
COMPONENTS: WOLF CREEK l
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April 1987
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i-1987 April a emoJ6C7' TASK /Wong yNIT NvMetM 7 $$A7epMtNQ ORGAN 12ATloN NAME AND MasLING ADOntSS uwsese te Coen
'EG&G Idaho, Inc.
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P. O. Box 1625 Idaho Falls, ID 83415 D6002 ila T798ofAE,oMT 1o 3PoNacRING QRGANIZATioN NAME ANO MAlbsNG ADC,A453 i>=ratWe l<a Cose, Division of PWR Licensing - A Office of Nuclear Reactor Regulation 1
U. S. Nuclear Regulatory Commission
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liashington, DC 20555 L ?y.
Il luPwLEMENTan y notes s
53 Assi AACT f200 wores er esas This EG&G Idaho, Inc., report provides a retatew of.the submittal from the KN sas Gas and Electric Company regarding conformance to Generic Letter 83-28. Item 2.2.1 for 4
the Wolf Creek Generating Station'.
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