ML20041C868

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Technical Evaluation of Licensee Response to IE Bulletin 80-06 Concerning ESF Reset Controls for Yankee Nuclear Power Plant
ML20041C868
Person / Time
Site: Yankee Rowe
Issue date: 08/30/1981
From: Radosevic J
EG&G, INC.
To:
NRC
Shared Package
ML20041C862 List:
References
IEB-80-06, IEB-80-6, SRO-291, NUDOCS 8203020620
Download: ML20041C868 (6)
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D GSaa SRO-29 ENERGYMEASUREMENTS GROUP avausr,oe f

TECHNICAL EVALUATION 'OF THE LICENSEE'S RESPONSE TO IC:E SULLETIN 80-~06 C'ONCERNING ESF RESET CONTROLS FOR THE YAi4KEE NUCLEAR POWER PLANT, UNIT 1 (DOCKET NO. 50-29)

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SAN RAMON OPERATIONS ~.

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.s DISCLAIMER This report was prepared as an account of work sponsored by the United States Government.

Neither the United States nor the United States Department. of Energy, nor any of their employees, makes any warranty,

, express or implied, or assumes any legal liability or responsibility for the accuracy,' completeness or usefulness of any information, apparatus, product or process disclosed, or represents that its use would not infringe on prive.ely owned rights.

Reference herein to any specific. commercial product, p.rocess, or service by trade name, mark, manufacturer, or other-wise, does not necessarily constitute or imply its endorsement, recommend-ation, or favoring by the United States Government or any agency thereof.

The views and opinions of authors expressed herein do not necessarily state or reflect those of the United States Government or any agency thereof.

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O,2GnG ENERGY MEASUREMENTS GROUP sno-291

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August 1981 e

TECHNICAL EVALUATION OF THE LICENSEE'S RESPONSE TO I&E BULLETIN 80-06 CONCERNING ESF RESET CONTROLS FOR THE YANKEE NUCLEAR POWER PLANT, UNIT 1 (DOCKET NO 50 29) w by B. Kountanis

,$Y funA J. R. Radosevic Department Manager Tnis document is UNCLASSIFIED l

i s f er:

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' Nicholas EfBroderick Department Manager l

Work Performed for Lawrence Livermore Natiortal Laboratory under U S. Department of Energy Contract No. DE-ACOd-76 NVO 1183.

SAN RAMON OPERATIONS,

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s INTRODUCTION On March 13, 1980, the USNRC Office of Inspection and Enforcement (ISE), issued ISE Bulletin 80-06, entitled " Engineered Safety Feature (ESF)

Reset Control s," to all PWR and.BWR facilities.with operating licenses.

18E Bulletin 80-06 requested that the following actions be taken by the licensees:

(1)

Review the drawings for all systems serving safety-related functions at the schematic / elementary diagram level to determine whether or not upon the reset of an ESF actuation signal all associated sa fety-rel ated equipment remains in its emergency mode.

(2)

Verify that the actual installed instrumentation and controls at the facility are consistent with the schematics reviewed ir item 1 above by conducting a test to demonstrate that all equipment remains in its emergency mode upon removal of the actuating signal and/or manual resetting of the various isol ating or actuation signals.

Provide a schedule for the per-formance of the testing in your response to this bulletin.

(3)

If any safety-related equipment does not remain in its emergency mode upon reset of an ESF signal at your facility, describe proposed system modification, design change, or other corrective act. ion planned to resolve the problem.

(4)

Report in writing within 90 days the results of your review, include a list of all devices which respond as

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discussed in Item 3 above, actions taken or p.lar.ned to assure adequate equipment control, and a schedule for implementation of corrective action.

This technical evaluation addresses the licensee's response to 18E Bulletin 80-06 and the licensee's proposed system modification, design change, and/or other. corrective action planned to resolve the problem, in e' valuating the licensee's response to the four Action Item requirements of the bulletin,.the following NRC staff guidance is also used:

Upon the reset of ESF signals, all safety-related equipment-shall remain in its emergency mode.

Multiple reset sequenc-

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ing shall not cause the affected equipment to deviate from its emergency mode.

Justification should be provided for any exceptions.

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s EVALUA, TION AND CONCLUSIONS In a letter' dated June ~ 12,1980'[Ref.II,'YankeeAtomicElectric Company, the licensee for Yankee Nuclear Power Plant,' replied to.I&E Bulletin 80-06.

In telephone ' conference. calls on March 4,1981 [Ref. 2]

and March 18,1981 [Ref. 3], the licensee provided clarification of por-tions of their original response' [Ref. 1].

On March 28, 1981, the NRC requested additional information by letter [Ref. 4].

The reply letter

[Ref. 5] was dated May 7, 1981.

In response to Action Item 1 of I&E Bulletin.80-06, the licensee ~

i reported [Ref. 1] that they have completed the review of all applicable schematic and logic diagrams of all safety-related functions and that the charging pumps and the accumulator N pilot supply valves do not remain in their emergency mode upon reset of $n ESF actuation signal.

We conclude that Action Item 1 of I&E Bulletin 80-06 has been satisfied.

In response to Action Item 3 of 1&E Bulletin 80-06, the licensee indica'ted [Ref. 1] that the control circuits for the charging pump and

  • accumulator 'N., pilot supply vahes will be modified to prevent automatic reset when th'e initiating signal is no longer present.

Additionally, the containment isolation system has been modified and tested previously to satisfy NUREG-0578.

The licensee reported by telephone [Ref. 2] that all the modifications were made and tested during October 1980.

The. licensee was asked during telephone conversations [Refs. 2 and 3] to describe.all the modifications.

This proved to be difficult to accomplish by telephone, and a formal' request for more information [Ref. 4] was made by the NRC.

The licensee responded [Ref. 5] by sending schematic diagrams and a written description of tne modifications to the containment isolation circuit, the charging pump circuit, and accumulator N2 pilot supply valves circuit. Our review of the submitted material indicates that the modifications meet the requirements of Action Item 3 of I&E Bulletin 80-06.

There may, however, be a question concerning the adequacy of the pilot solenoid circuit for the containment isolation system.

This circuit should be looked at by the SEP study for compliance with the fail-safe requirements of GDC-23 because at least one solenoid valve must be energized to keep the isolation valve closed.

In response to Action Item 2 of I&E Bulletin 80-06, the licensee reported [Refs. 1, 2, and 3] th.at tests on all equipment, including the modifications to the containment isolation, have been completed and that no.

equipment deviates from its emergency mode.

We, therefore, conclude that Action Item 2 of I&E Bulletin 80-06 has been satisfied.

The ' licensee has complied with the requirements of Action Item 4 of I&E Bulletin 80-06 in ' heir response to Action Items 1 through 3.

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FINDINGS Based on our review of the documents and information provided and the modification made by the licensee, we conclude that the ESF reset controls for the Yankee Nuclear Power Plant comply with the require-ments of 1&E Bulletin 80-06.

REFERENCES 1.

Yankee Atomic Electric Company letter (0.E. Vandenburgh) to NRC (8.H.

Grier), " Response to I&E Bulletin No. 80-06, Engineered Safety Feature (ESF) Reset Controls," dated June 12, 1980.

2.

Telephone conference call, NRC (R. Caruso and P. Bender), Yankee Atomic Electric Co. (J. Kay, D. January, and A. Miller), and.EG&G, Inc., San Ramon (B. Kountanis and D. Hackett), March 4,1981.

3.

Teiephone conference call, NRC (R. Caruso and P. Bender), Yankee Atomic Ele'ctric Co. (J. Kay and A. Miller), EG&G, Inc., San Ramon (B. Koun-tanis), March 18, 1981.

4.

NRC letter, (O. M. Crutchfield) to Yankee Atomic Electric Co. (J. A.

Kay), dated March 28, 1981.

5.

Yankee Atomic Electric Co. letter (J. A. Kay) to NRC (0.M. Crutch-field), " Additional Information on Engineered Safety Feature Reset Controls (IE Bulletin 80-06)," dated May 7, 1981.

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