ML20037D014
| ML20037D014 | |
| Person / Time | |
|---|---|
| Site: | Prairie Island  |
| Issue date: | 02/28/1981 |
| From: | Broderick N, Debby Hackett, Radosevic J EG&G, INC. |
| To: | Bender P, Wilson R Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML20003J316 | List: |
| References | |
| CON-FIN-A-0250, CON-FIN-A-250 EGG-1183-4183, IEB-80-06, IEB-80-6, NUDOCS 8105110266 | |
| Download: ML20037D014 (6) | |
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ENERGYMEASUREMENTS GROUP TECHNICAL EVALUATION OF THE LICENSEE'S RESPONSE TO I&E SULLETIN 80-06 CONCERNING ESF RESET CONTROLS FOR THE PRAIRIE ISLAND NUCLEAR GENERATING PLANT, UNITS 1 AND 2 (DOCKET NO S. 50 282 and SC.3C6) s t\\%
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DISCLAIMER This report was prepared as an account of work sponsored by the United States Government.
Neither the United States nor the United Status Department of Energy, nor~ an'y' 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, aoparatus, product or process disclosed, ~or represents that its use would not infringe
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on privately owned rights.-
Reference herein.to' any specific commercial product,, process, or service by trade name, mark, manufacturer, or other-wise, does not necessarily constitute or imply its endorsement, recorrend-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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INTERif.; Rif.7 -.iT h2C:G 1::' n."l * *d'; *.7.'t.*-*
NRC TAC i 42770 and 12771 Report No.
EGG 1183 4183 Contract Program or Froject
Title:
Electrical, Instrumentation, and Control System Support Subject of this Document:
Technical Evaluathn of the Licensee's Response to I&E Bulletin 30-06 Concerning ESF Reset Controls for the Prairie Island Nuclear Generating Plant, Units 1 and 2 Type of Document:
Informal Report A uth o..s):
D. B. Hackett Date of Document:
January 1981 9
Responsible NRC Individual and NRC Of fice or Division:
P. Sender /R. Wilson, ICSB l
This document was prepared pri:narily for preliminary or internal use.
It nas not received full review and approval. Since there may be sucstantive changes, this document should not be considered final.
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EGaG Energy Measurements Gecup l
San Ramon Operations 3an Rainen. CA 94583 i
i Prepared for the U.S. Nuclear Regulatory Connission Washington. 0.C.
Under 00E Contract No.S&R 201904031 NRC FIN No. A0250 I
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$Ud 11*"-*.sa Ener'2y Measurements Group San Ramon Operatiens TECHNICAL EVALUATION OF THE LICENSEE'S RESPONSE TO l&E SULLETIN S0-06 CONCERNING ESF RESET CONTROLS FOR THE PRAIRIE ISLAND NUCLEAR GENERATING PLANT, UNITS 1 AND 2 (OCCKET NCS. 5C.282 and SC-3C6) by D. S. Hackett l
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Approved for Publication
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- J. K. daCOSeV1C Department Manager i
l inis document is UNCLASSIFidu
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' N1Cnolas i( irCCer1CK Department Manager Worn Performed for Lawrence Lavermore National Lacoratory uncer U.S.Cepartment of Ener;;y Contract No. CE-ACOS-76 NVQ 1183.
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1.
INTRUGUCTION On Marcn 13, 1930, ne USNRC Of fice of Inspection and Enforcetaant (13E), issued ISE Bulletin 80-06, entitled "Engiaeered Safety Feature (dSF)
Reset Con rols," to all PWR and BWR f acilities witn operating licenses.
I&E Sulletin 80-06 requested tnat the following ac:f ons se taken my tne licensees:
(1)
Review :ne drawings for all systems serving safety-related functions at :ne scnematic/ elementary diagram level to de.ennine wnetner or no: upon :ne reset of an ESF actuation signal all associated cafety-related equipment re:nains in its emergency mode.
(2)
Verify tnat the actual' installed instrumentation and controls at tne facility are consistent witn tne schematics reviewed in Item 1 aoove by conducting a,
test to de:nonstrate that all equipment remains in its emergency made upon removal of :ne actuating signal and/or manual rese: ting of tne various isolating or actuation signals.
Provide a scnedule for :ne per-formance of :ne testing in your response to tnis bulletin.
(3)
If any safety-related equipment does not remain in its emergency mode upon reset of an ESF signal at your facility, descrice proposed system modification, design change, or other corrective action planned to resolve the problem.
(4)
Report in w-iting,;itnin 90 days ne results of your review, include a list of all devices wnicn respond as discussed in Item 3 above, actions taken or planned to assure adequate equipinent control, and a scnedule for implementation of corrective action.
This tecnnical evaluation addresses tne licensee'siresponse to ISE Bulletin 80-06 and the licensee's proposed system modifica: ion, design In change, and/or other corrective action planned to resolve tne problem.
evaluating tne licensee's response to the four Action Item requirements of tne bulletin, tne following NRC staff guidance is also used:
Upon the rese; of ESF signals, all safety-related equipment snall remain in its emer~gency mode.
Multiple reset sequencing snall not cause :ne affected equipment to deviate from its emergency mode.
Justification snould be pec eided for any exceptions.
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2.
EVALUATION At:0 CUNCLUSIONS In a letter dated June 2,1980 [Ref.1], Nor:nern States Power Ccept.ny (NSP), tne licensee for Prairie Island Nuclear Generating Plants, Units 1 and 2, replied to ISE Bulletin 80-06.
- ortnern States Power reported tna; they ned completed a review of the safety system scnematics for Prairie Island Nuclear Generating Plant.
Tne licensee stated tnat their safety-related equipment remains in its emergency mode upon reset of the safety signals.
We conclude :na: :ne licensee nas complied witn Action Items 1, 3, and 4 of I3E Bulletin 60-06.
ine licensee coanitted to test eacn unit at its nex: refueling outage to demonstrate tnat :ne safety-related equipment remains in its emerger.cy made after reset.
The next seneduled refueling outages were stated to be in Augus:/ September, 1980 for Unit 1 and in February /Marcn, 1981 for Unit 2.
We conclude tnat tne licensee has complied witn Action I:em 2 of I&E Bulletin 80-06 by providing :nis schedule.
3.
F INDINGS Based on our review of the information and documents proviced by tne licensee, we find tnat tne ESF rese: cont.ols for Prairie Island Nuclear Generating Plant, Units 1 and 2 satisfy the requirements of I&E Bulletin 80-06.
RUERENCES 1.
Nortnern States Power Company letter (0.E. Gilberts) to NRC (J.
G.
Keppler), Occkets 50-282 and 50-306, no title, dated June 9, 1960.
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