ML20116D938
| ML20116D938 | |
| Person / Time | |
|---|---|
| Site: | Calvert Cliffs  |
| Issue date: | 07/14/1987 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20116D885 | List:
|
| References | |
| FOIA-96-237 GL-83-28, NUDOCS 9608050020 | |
| Download: ML20116D938 (4) | |
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ENCLOSURE 1
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I94 UNITED STATES l
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SAFETY EVALUATION REPORT GENERIC LETTER 83-28, ITEM 2.1 (PART 2) l VENDOR INTERFACE PROGRAMS (RTS COMPONENTS)
CALVERT CLIFFS NUCLEAR POWER PLANT, UNITS 182 DOCKET NOS. 50-317/318 l
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1.0 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 i
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 to be related to the sticking of the undervoltage trip attachment. Prior to this incident, on February 22, 1983, at Unit I of the Salem Nuclear Power Plant, an automatic trip signal was j
generated based on steam generator low-low level during plant start-up. In this case, the reactor was tripped manually by the operator almost coincidentally with the automatic trip.
Following these incidents, on February 28, 1983, the NRC Executive Director for Operations (EDO), directed the 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, 1
the Commission (NRC) requested (by Generic Letter 83-28 dated July 8,1983 )
all licensees of operating reactors, applicants for an operating license, and holders of construction permits to respond to generic issues raised by the analyses of these two A1VS events.
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This report is an evaluation of the response submitted by Baltimore Gas &
Electric Company, the licensee for the Calvert Cliffs Nuclear Plant Units 1&2, for Item 2.1 (Part 2) of Generic Letter 83-28. The actual documents reviewed as part of this evaluation are listed in the references at the end of the report.
Item 2.1 (Part 2) requires the licensee to conform that an interface has been established with the NSSS or with the vendors of each of the components of the Reactor Trip System which includes:
periodic communication between the licensee / applicant and the NSSS or the vendors of each of the components of the Reactor Trip System,
- and, a system of positive feedback which confirms receipt by the licensee /
applicant of transmittals: of vendor technical information.
2.0 EVALUATION The licensee for the Calvert Cliffs, Units 1&2 plants responded to the require-2 ments of Item 2.1 (Part 2) with a submittal dated April 6,1987. The licensee stated in this submittal that Combus, tion Engineering is the NSSS vendor for the Calvert Cliffs, Units 1&2 plants and that the RTS is included as part of the Combustion Engineering interface program established for these plants. The response also confirms that this interface program includes both I
periodic communication between Combustion Engineering and the licensee and positive feedback from the licensee in the form of signed receipts for l
technical information transmitted by Combustion Engineering.
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3.0 CONCLUSION
l Based on our review of these responses, we find the licensee's statements
-confirm that a vendor interface program exists with the NSSS vendor for components that are required for performance of the reactor trip function.
This program meets the requirements of Item 2.1 (Part 2) of the Generic Letter 83-28, and is therefore acceptable.
4.0 REFERENCES
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NRC Letter, D. G. Eisenhut to all Licensees of Operating Reactors, Applicants for Operating License, and Holders of Construction Permits, " Required Actions Based on Generic Implications of Salem ATWS Events (Generic Letter 83-28) "
July 8, 1983.
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Baltimore Gas & Electric Company letter to NRC, J. A.
Tiernan to Office of Nuclear Reactor Regulation, " Additional Information Concerning BG&E Responses to Generic Letter 83-28,"
April 6,1987.
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ENCLOSURE 2 ICSB/ DEST SALP INPUT PLANT: Calvert Cliffs Nuclear Power Plant, Units 182 DOCKET NO: 50-317/318 SER
SUBJECT:
Review of Responses to Generic Letter 83-28, Item 2.1 (Part 2)
PERFORMANCE PARAMETERS:
Management Involvement in Assuring Quality Approach to Resolution of Technical Issues From a Safety Standpoint Response to NRC Initiatives
- 4) Staffing (Including Management) 5 Reporting and Analysis of Reportable Events 6
Training and Qualification Effectiveness (7
Any Other SALP Functional Area f
I PERFORMANCE NARRATIVE DESCRIPTION OF CATEGORY /
PARAMETER APPLICANT / LICENSEE'S PERFORMANCE RATING 1
No basis for assessment.
N/A 2
Approach was direct and enabled ready 1
l verification of acceptability of their j
program.
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Licensee described his program which net 1
the requirements of this generic letter item.
4 thru 7 No basis for assessment.
N/A OVERALL APPLICANT / LICENSEE PERFORMANCE RATING 1
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EGG-NTA-7720 June 1987 l
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CONFORMANCE TO ITEM 2.1 (PART 2) 0F GENERIC
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LETTER 83-28, REACTOR TRIP SYSTEM VENDOR Engineer /ng.
9 INTERFACE, CALVERT CLIFFS-1 AND -2, MILLSTONE-2*
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AND PALISADES
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a DISCLAIMER TNs book was prepared as an account of work sponsored by an agency of the United i
States Gowomment. Nether the Uruted States Governtnent nor any agency thereof, nor any of their empiovees, makes any warranty, express or vnphed, or assumes any legal batziety or responsebeisty for the accuracy, completenses, or usefulness of any 1
informenon, apparatus, product or process discioned, or represents that sts use would
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not enfnnge prnrately owned nghts. References hereen to any specific commercel j
product, process, or service by trade name, trademert, rnenufacturer, or othenarise does not necessanly Constitute or empiy sts endorsement, recommendeDon, or fewonng by the Uruted States Govemment or any agency thereof. The wwwe and opiruons of authors espressed herein do not necessardy state or reflect thoes of the Uruled Statee Government or any agency thereof-
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CONFORMANCE TO i
ITEM 2.1 (PART 2) 0F GENERIC LETTER 83-28 REACTOR TRIP SYSTEM VENDOR INTERFACE CALVERT CLIFFS-1 AND -2 l
MILLSTONE-2 PALISADES F. G. Farmer 1
Published June 1987 Idaho National Engineering' Laboratory EG&G Idaho, Inc.
J Prepared for the U.S. Nuclear Regulatory Commission Washington, D.C.
20555 Under 00E Contract No. DE-AC07-761001570 I
FIN Nos. 06001 and 06002 l
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- I ABSTRACT This EG&G Idaho, Inc. report provides a review of the submittals for some of the Combustion Engineering (C-E) nuclear plants for conformance to Generic Letter 83-28 Item 2.1 (Part 2). The report includes the following Combustion Engineering plants, and is in partial fulfillment of the following TAC Nos.:
j Plant Docket Number TAC Number l
Calvert C11ffs-1 50-317 52825 Calvert C11ffs-2
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50-318 52826 M111 stone-2 50-336 52855 i
Palisades 50-255 52864
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FOREMORD This report is provided as part of the program for evaluating j
licensee / applicant conformance to Generic Letter "83-28, " Required Actions Based on Generic Implications of Sales ATWS Events." This work is conducted for the U. S. Nuclear Regulatory Commission, Office of Nuclear Reactor Regulation, Division of Engineering and System Technology by EG&G Idaho, Inc.
4 The U. S. Nuclear Regulatory Commission funded the work under the authorization, B&R 20-19-19-11-3, FIN Nos. 06001 and 06002.
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i CONTENTS ABSTRACT...........................................................,
FOREWORD.................................
gj igt 1.
INTRODUCTION...............................
2.
j RE VIEW REQUIRENENTS......................
2 3.
GROUP RE VIEW RESUL TS.......................
3 4.
REVIEW RESULTS FOR CALVERT CLIFFS-1 AND -2..
4 4.1 Evaluation................................................
4 4.2 Conclusion.................................
5.
4 REVIEW RESULTS FOR NILLSTONE S 5
5.1 Evaluation................................................
5 5.2 Conclusion...................................
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RE VIEW RESUL TS FOR PALISADES.................
6 6.1 Evaluation..........................................
6 6.2 Conclusion.....................................
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6 GROUP CONCLUSION...............................
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REFERENCES.......................................
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e CONFORMANCE TO ITEM 2.1 (PART 2) 0F GENERIC LETTER 83-28 REACTOR TRIP SYSTEM VENDOR INTERFACE CALVERT CLIFFS-1 AND -2 MILLSTONE-2 PALISADES 1.
INTRODUCTION On July 8, 1983, Generic Letter 83-28 was issued by D. G. Eisenhut, Director of the Division of Licensing, Office of Nuclear Reactor Regulation, to all licensees of operating reactors, applicants for operating 11(enses, and holders of construction permits. This letter included required actions based on generic implications of the Sales ATWS events. These requirements have been published in Volume 2 of NUREG-1000,
" Generic Implications of ATWS Events at the Salem Nuclear Power Plant."
This report documents the EG&G Idaho, Inc. review of the submittals of four of the Combustion Engineering plants Calvert C11ffs-1 and -2, j
M111 stone-2 and Palisades, for conformance to Item 2.1 (Part 2) of Generic Letter 83-28. The submittals from the licensees and applicants uttitzed in l
these evaluations are referenced in Section 8 of, this report.
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REVIEW REQUIREMENTS Item 2.1 (Part 2) (Reactor Trip System - Vendor Interface) requires licensees and applicants to establish, implement and maintain a continuing program to ensure that vendor information on Reactor Trip System (RTS) components is complete, current and controlled throughout the life of the plant, and appropriately referenced or incorporated in plant instructions and procedures.
The vendor Interface program is to include periodic connunications with vendors to assure that all applicable information has been received, as well as a system of positive feedback with vendors for mailings containing technical information, e. g.,
licensee / applicant acknowledgement for receipt of technical information.
That part of the vendor interface program which ensures that vendor information on RTS components, once acquired, is appropriately controlled, rcierenced and incorporated in plant instructions and procedures, will be evaluated as part of the review of Item 2.2 of the Generic Letter.
Because the Nuclear Steam System Supplier (NSSS) is ordinarily also i
the supplier of the entire RTS, the NSSS is also the principal source of information on the components of the RTS.
This review of the licensee and applicant submittals will:
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Confirm that the licensee / applicant has identified an interface with either the NSSS or with the vendors of each of the components of the Reactor Trip System.
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Confirm that the interface identified by licensees / applicants includes
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periodic communication with the NSSS or with the vendors of each of the components of the Reactor Trip System.
3.
Confirm that the interface identified by licensees /apolicants includes
' a system of positive feedback to confirm receipt of transmittals of technical information.
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GROUP REVIEW RESULTS 1
The relevant submittals from each of the included reactor plants were j
reviewed to determine compliance with Item 2.1 (Part 2). First, the l
i submittals from each plant were reviewed to establish that Item 2.1 (Part
- 2) was specifically addressed. Second, the submittals were evaluated to determine the extent to which each of the plants complies with the staff guidelines for Item 2.1 (Part 2).
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4 REVIEW RESULTS FOR CALVERT: CLIFFS-1 AND -2 i
5.1 Evalua tion Baltimore Gas and Electric Company, the licensee for Calvert Cliffs, provided their response to' Item 2.1 (Part 2) of the Generic Letter on April j
6, 1987.
In that response, the licensee confirms that the NSSS for Calvert Cliffs is Combustion Engineering and that the RTS for Calvert Citffs is included as a part of the C-E interface program established for the Calvert Cliffs NSSS.
The C-E interface program for the NSSS includes periodic communication between C-E and licensees / applicants such as "INf080LLETINS" containing information and recommendations concerning C-E systems, a system of positive feedback from licensees / applicants in the form of signed receipts for technical information transmitted by C-E, and periodic issuance by C-E of indices of INf08ULLETINS.
5.2 Conclusion
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We find the licensee's statement confirming that Calvert Cliffs.ts a participant in the Combustion Engineering interface program for the RTS, which meets the staff position on Item 2.1 (Part 2) of the Generic Letter, is acceptable.
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REVIEW RESULTS FOR MILLSTONE-2 5.1 Evaluation Northeast Utilities, the licensee for Millstone-2, provided their response to Item 2.1 (Part 2) of the Generic Letter on April 2,1987. In that response, the licensee confirms that the NSSS for Millstone-2 is Combustion Engineering and that the RTS for Millstone-2 is included as a part of the C-E interface program established for the Millstone-2 NSSS.
The C-E interface program for the NSSS includes periodic communication between C-E and licensees / applicants such as "INF0 BULLETINS" containing
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information and recommendations concerning C-E systems, a system of positive feedback from licensees / applicants in the form of signed receipts for technical information transmitted by C-E, and periodic issuance by C-E of indices of INFOSULLETINS.
5.2 Conclusion We find the licensee's statement confirming that Millstone-2 is a participant in the Combustion Engineering interface program for the RTS, which meets the staf f position on Item 2.1 (Part 2) of the Generic Letter, is acceptable.
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REVIEW RESULTS FOR PALISADES i
1 6.1 Evaluation i
Consumers Power, the licensee for Palisades, provided their response i
to item ~2.1 (Part 2) of the Generic Letter on May 8, 1987.
In that j
response, the licensee confirms that the N5SS for Palisades is Combustion i
Engineering and that the RTS for Palisades is included as a part of the C-E interface program established for the Palisades NSSS.
The C-E Interface program for the NSSS includes periodic communication between C-E and licensees / applicants such as "INF08ULLETINS" containtag information and recoassendations concerning C-E systems, a system of positive feedback from licensees / applicants in the form of signed receipts for technical information transmitted by C-E, and periodic issuance by C-E of indices of INF08ULLETINS.
6.2 Conclusion We find the licensee's statement confirming that Palisades is a participant in the Combustion Engineering interface program for the RTS, which meets the staff position on Item 2.1 (Part 2) of the Generic Letter, is acceptable.
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GROUP CONCLUSION We conclude that the licensee / applicant responses for the listed Combustion Engineering plants meet the staff position for Item 2.1 (Part 2) i I
-of Generic Letter 83-28 and are acceptable.
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REFERENCES 1.
NRC Letter, D. G. Eisenhut to all Itcensees of Operating Reactors, Appilcants for Operating License, and Holders of Construction Permits
" Required Actions Based on Generic Impitcations of Salem ATWS Events (Generic Letter 83-28)," July 8, 1983.
2.
Generic Implications of ATWS Events at the Salem Nuclear Power Plant NUREG-1000, Volume 1, April 1983; Volume 2, July 1983.
3.
Baltimore Gas and Electric Company letter to NRC, J. A. Tiernan to I
Office of Nuclear Reactor Regulation, " Additional Information Concerning BG&E Responses to Generic Letter 83-28," April 6,1987.
4.
Northeast Utt11ttes letter to NRC, E. J. Mroczka to Document Control 1
Desk, " Generic Letter 83-28, Salem ATWS," Aprt) 2,1987.
5.
Consumers Power letter to NRC, J. L. Kuemin to Document Control Desk,
" Additional Information - Vendor Interface and Equipment Classification - Generic Letter 83-28," May 8, 1987.
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,m This EG&G Idaho, Inc. report presents the results of cur evaluation of the submittals 1
of some of the Combustion Engineering nuclear plants for conformance to Generic Letter 83-28. Item 2.1 (Part 2).
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