ML20009B124

Technical Evaluation of Licensee Response to IE Bulletin 80-06 Re Engineered Safety Features Reset Controls.

ML20009B124
Person / Time
Site:	Crystal River
Issue date:	02/28/1981
From:	Laudenbach D, Radosevic J EG&G, INC.
To:	Bender P, Wilson R Office of Nuclear Reactor Regulation
Shared Package
ML20009B118	List: ML20009B124
References
CON-FIN-A-0250, CON-FIN-A-250 EGG-1183-4189, TAC-42734, NUDOCS 8107140827
Download: ML20009B124 (6)

Text

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EGG 1183-4186

- FEBRU ARY 1981 g,$ EGes ENERGYMEASUREMENTS GROUP v .

TECHNICAL EVALUATION OF THE LICENSEE'S RESPONSE TO I&E BULLETIN 80-06  ;

CONCERNING ESF RESET CONTROLS FOR THE CRYSTAL RIVER NUCLEAR POWER STATION, UNIT 3 i

l (DOCKET 50-302) ,

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l i SAN RAMON OPERATIONS t

2001 CLO CAOW CANYON ADAD 8107140827 810702 SAN RAMON. CALIFOANIA 94583

, PDR ADOCK 05000302 G PDR -

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INTERIM REPORT E l

)4 ;;Gs0 1 T.!". **C.71*.*** l NRC TAC No. 42734 Report No. EGG 1183-4189 Contract Program or Project

Title:

Electrical, Instrumentation,and Control System Support Subject of this Document:

Technical Evaluation of the Licensee's Response to I&E Bulletin 80-06 Corcerning ESF Reset Controls for the Crystal River Nuclear Power Station, Unit 3 Type of Document:

Infonral Report Author (s):

D. P Laudenbach Date of Document:

February 1981 Responsible NRC Individual and NRC Of fice or Division:

P. Bender /R. Wi.lson, ICSB This document was prepared primarily for preliminary or internal use. It has not received full review and approval. Since there may be substantive changes, this document should not be considered final.

EG&G Energy Measurements Group San Ramon Operations San Ramon, CA 94583 Prepared for the U.S. Nuclear Regulatory Commission Washington 0.C.

. Under 00E Contract No.B&R 201904031 NRC FIN No. A-0250 INTERIM REPORT l

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[EGsG

, EGG 1183-4189 Energy Measurements Group February 1981 San Ramon Operations j

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I TECHNICAL EVALUATION OF THE LICENSEE'S RESPONSE TO I&E BULLETIN 80-06 CONCERNING ESF RESET CONTROLS FOR THE l 1

CRYSTAL RIVER NUCLEAR POWER STATION, UNIT 3 (DOCKET 50-302) l by l

0. H. Laudenbach Approved for Publication A/Ls .

'J. R. Radosevic Department Manager This document is UNCLASSIFIE0 f

ss le : t Nicnolds E. $roderick Department Manager l

Work Performed for t.awrence Livermore National Laboratory under U.S. Department of Energy Contract No. DE.ACQ8 76 NVO 1183.

j INTRODUCTION ,

On March 13, 1980, the USNRC Of fice of Inspection and Enforcement (I&E), issued I&E Bulletin 80'-06, entitled " Engineered Safety Feature (ESF) ,

Reset Controls " to all PWR and BWR facilities with operating licenses.

I&E Bulletin 80-06 requested that tne following actions be taken oy 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 safety-related equi;:mcnt remains in its emergency mode.

(2) Verify that the actual installed instrumentation and controls at the facility are consistent with the ,

schematics reviewed in 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 isolating or actuation signals. Provide a schedule for the per- j formance of the testing in your response to tnis i bulletin.

(3) If any safety-related equipment does not remain in its i emergency mode upon reset of an ESF signal at your facility, describe proposed system modification,  !

design ' change, or other corrective action planned to i resolve tne problem.

l (4) Report in writing within 90 days the results of your  !

review, include a list of all devices which respond as  !

discussed in Item 3 above, actions taken or planned to  !

as::ure adequate equipment control, and a schedule for  ;

implementation of corrective action.

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, This technical evaluation addresses the licensee's response to i I&E Bulletin 80-06 and the licensee's proposed system modification, design '

change, and/or other corrective action planned to resolve the problem. In evaluating tne licer.see's response to the four Action item requirements of

, tne bulletin, the following NRC staff guidance is also used: .

Upon the reset of ESF signals, all safety-related equipment shall remaia in its emergency mode. Multiple reset sequencing shell not cause the affected equipment to deviate from its emergency mode. Justification should be provided for any exceptions.

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EVALUATION AND CONCLUSIONS 4

In a letter dated June 12,1980 [Ref.1], Florida Power Corpora- l tion, the licensee for Crystal River Nuclear Power Station, Unit 3, replied 4

to I&E Bulletin 80-06. In a telephone conference call conducted on January )

29,1981 [Ref. 2], the licensee provided additional information and clar- '

ification of their original response [Ref.1].

i Tne licensee reported [Ref. 1] tnat a thorougn review of all equipment actuated by the ESFAS system has been completed at tne scnematic/

elementary diagram level. The ESFAS system includes High Pressure Injec-tion. Low Pressure Injection, Reactor Building Isolation, and Reactor Building Spray. The licensee indicated [Ref. 2] that their response to Action Item 1 cf !&E Bulletin 80-06 (in their June 12, 1980 letter [Ref.

1]) meant that "all systems serving safety-related functions were review-ed." We ennelude that tne licensee has complied with the requirements of

, Action Item 1 of ISE Bulletin 80-06 by completing the drawing review of all systems serving safety-related functions.

, The licensee reported [Ref. 1] that Surveillance Procedure SP-417, entitled " Refueling Interval Integrated Plant Response to Engineered Safeguards Actuation," has been modified to include a test to

. demonstrate that all equipment remains in its emergency-mode upon removal i

of the actuating signal and/or upon manual resetting of the various isola-ting or actuation signals. This test will .be conducted during restart of Unit 3. We conclude that the licensee has complied with the requirements of Action Item 2 of I&E Bulletin 80-06 by providing a scnedule for the per.formance of the testing.

The licensee reported [Ref.1] they nave determined, as a result of the drawing review conducted in response to Action Item 1 of I&E Bulle-tin 80-06, tnat no valve, ventilation damper, motor, etc. , returns to its preactuation condition upon reset of the ESF -4gnal. Based on the findings presented [Refs.1 and 2], we conclude that ie licensee has complied witn the requirements of Action Item 3 of I&E Bulletin 80-06.

The licensee nas complied with the requirements of I&E But letin 80-06, Action Item 4, in their response to Action Items 1 through 3.

FINDINGS Based on our review of the information and documents provided by the licensee, we find that the ESF reset controls for Crystal River Nuclear Power Station, Unit 3, satisfy tne requirements of I&E Bulletin 80-06.

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. . l REFERENCES ,

1. Florida Power Corporation letter (P. Y. Baynard) to NRC/I&E (J. P .

O'Reilly), " Response to I&E Bulletin 80-06", dated June 12, 1980.

2. Telephone conference call, NRC (P. Bender); Florida Power Corporation (W. Lobo, E. Good); EG&G, Inc., San Ramon (D. Hackett, D. Laudenbach),

January 29, 1981.

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