ML20009H207
| ML20009H207 | |
| Person / Time | |
|---|---|
| Site: | Millstone  |
| Issue date: | 05/31/1981 |
| From: | Jacoby K EG&G, INC. |
| To: | Bender P, Wilson R Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML20009H203 | List: |
| References | |
| CON-FIN-A-0250, CON-FIN-A-250 EGG-1183-4219, IEB-80-06, IEB-80-6, NUDOCS 8108070026 | |
| Download: ML20009H207 (6) | |
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3 INTERIM REPORT
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EGsG T,?.!"tCll*".'!.*'"*
NRC TAC Ho.
42755 Report No.
EGG 1183 4219 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 Concerning ESF Reset Controls for the Millstone Nuclear Power Station, Unit 1 Type of Document:
Informal Report Authortsh l
K. D. Jacoby p
\\
Date of Document:
l May 1981 Responsible NRC Individual and NRC Office or Division:
P. Bender /R. Wilson, ICSB This document was prepared primarily for preliminary or internal use.
It nas not received full review and approval. Since there may be substantive changes, this document snauld not be considered firial.
I
~333 Erergy Measurements Group San Ramon Operations San Ramon, CA 9d583 Prepared for the U.S. Nuclear :legulatory Commission
)
.Jashington, 0.C.
{
Uncer 00E Contract No.BaR 201904031 1
NRC FIN No. A-07.50 INTERIM REPORT
0 EQsG EGG 1183-4219 an.rry M.:.ur.m nta creus san nemca operation.
May 1981 TECHNICAL EVALUATION OF THE LICENSEE'S RESPONSE TO I&E BULLETIN 80-06 CONCERNING ESF RESET CONTROLS FOR THE MILLSTONE NUCLEAR POWER STATION, UNIT 1 (DOCKET NO. 50-245) by i
. D. Jacoby Approved for Publication 1
hhhk A i
J. R. Radosevic Department Manager Tnis cocument is UNCLASSIFIED i
_ //et
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a e:
t
" Nicnolas't. Broaericx Department Manager i
I4 Work Performed for Lawrence Livermore National Laboratory under U.S. Department of Energy Contract No. DE-ACO8-76 NVQ 1103.
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i I
t INTRODUCTION On March 13, 1980,-tne USNRC Office of Inspection and Enforcement (I&E), issued I&E Bulletin 80-06, entitled " Engineered Safety Feature (ESF) i Reset Controls," to all PWR and BWR facilities witn operating licenses, j
I&E Bulletin 80-06 requested tnat tne following actions be taken by tne licensees:
I l
(1)
Review the drawings for all systems serving safety -
l related functions at tne scnematic/ elementary diagram level to determi;1e wnetner or not upon tne reset of an ESF actuation signal all associated safety-related equipment remains in its emergenet mode.
(2)
Verify tnat tne actual installed instrumentation and i
i controls at tne facility are consistent with tne senematic" reviewed in Item 1 aoove by conducting a test to demonstrate tnat all equipment remains in its emergency mode upon removal of tne actuating signal and/or manual resetting of tne various isolating or actuation signals.
Provide a schedule for tne per-formance of the testing in your response to this I
bulletin.
(3)
If any safety-related equipaent does not remain in its t
emergency mode upon reset of an ESF signal at your l
l f acility, describe proposed system modification, design cnange, or otner corrective action planned to resolve tne problem.
(4)
Report in writing within 90 days tne results of your l
review, include a list of a?1 devices wnicn respond as l
discussed in Item 3 above, actions taken or planned to l
assure adequate equipment control, and a scnedule for implementation of corrective action.
l This tecnnical evaluation addresses tne licensee's response to I&E Bulletin 80-06 and tne licensee's proposed system modification, design cnange, and/or otner corrective action planned to resolve tne proolem.
In l
evaluating the licensee's response to tne four Action Item requirements of the bulletin, tne 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 sequencing snall not cause tne affected ;quipment to deviate f rom its emergency mode.
Justification snould be provided for any exceptions.
i l
EVALUATION AND CONCLUSIONS In a letter dated June 13, 1980 [Re f.
1], Nortneast Nuclear Energy Company (NNECO), tne licensee for Millstone Nuclear Power Station, Unit 1, replied to I&E Bulletin 80-06.
Following a February 15, 1981 telephone conference call [Ref. 2], a meeting was neld on February 24,19'.d between the licensee and tne NRC Project Manager [Ref. 3] during wnicn additional information was provided.
~
NNECO reported [Re f. 1] tnat a review of tne drawings for all systems serving safety-related functions nad been completed to determine wnetner or not upon tne reset of an ESF actuation signal all associated safety-related equipment remains in its emergency mode.
The licensee identified four iso-condenser valves tnat could move from tneir emergency mode upon ESF reset.
We conclude tnat the licensee nas complied witn tne requirements of Action Item 1 of I&E Bulletin 80-06 by completing tne drawing review of all systems serving safety-related functions.
NNECO nas committed [Ref. 1] to perform a test prior to startup from tne 1980 refueling outage to demonstrate tnat tne installed instru-mentation and controls at tne facility are consistent witn tne scnematics.
We conclude tnat the licensee nas complied witn the requirements of Action Item 2 of I&E Bulletin 80-06 by providing a scnedule for tne performance of testing.
l NNECO nas committed to perform modifications to eacn of tne l
components identified by tne licensee, and nas provided [Ref. 3] botn a narrative description and marked-up drawings of all proposed modifications.
Tnis information was forwarded to EG&G/SRO by the Nfi Tecnnical Contact.
l Tne modifications, as presented in reference 3, will assure tnat each of tne items identified will remain in its emergency mode position upon ESF reset; tnarefore, we conclude tnat tne licensee nas complied witn tne requirements of Action Item 3 of I&E Bulletin 80-06.
NNECO committed to install and test the modifications prior to l
startup from tne current outage [Ref. 2].
We conclude tnat tne licenses has complied with Action Item 4 of I&E Bulletin 80-06 by providing tnis schedule and in their response to Action Items 1 and 3 above.
FINDINGS Based on our review of tne information and documents provided, we find the ESF reset controls for tne Millstone Nuclear Power Station, Unit 1, comply witn tne requirements of I&E Sulletu 80-06.
j I '
REFERENCES 1.
Northeast Utilities letter (W.
G. - Counsil) to NRC (B.
H.
Grier),
" Millstone Nuclear Pnwer Station, Unit No.
1, I&E dulletin 80-06--
Engineered Safety leatures Reset Control," dated June 13, 1980.
r l
' 2.
Telephone conference call, NkC (P. Sender) and EG&G/SRO (K. Jacoby) to NNECO (P. Blasioli), February 19, 1981.
3.
Meeting between NRC and NNECO, Lyme, Connecticut, February 24, 1981.
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