NUREG/CR-4661, Forwards Written Comments & Suggested Changes to Draft NUREG/CR-4661, Closeout of IE Bulletin 85-003: Motor-Operated Valve Common Mode Failures During Plant Transients Due to Improper Switch Settings
| ML19332C058 | |
| Person / Time | |
|---|---|
| Issue date: | 11/08/1989 |
| From: | Berlinger C Office of Nuclear Reactor Regulation |
| To: | Foley W PARAMETER, INC. |
| References | |
| RTR-NUREG-CR-4661 IEB-85-003, IEB-85-3, NUDOCS 8911220258 | |
| Download: ML19332C058 (12) | |
Text
__
November 8 1989 Walter J. Foley, Principal Investigator Parameter, Inc.
13380 Watertown Plank Road Elm Grove, Wisconsin 53122
Dear Mr Foley:
Your letter of August 25, 1989, forwarded the latest draft of NUREG/CR-4661,
" Closeout of IE Bulletin 85-03: Motor-Operated Valve Common Mode Failures During Plant Transients Due to Improper Switch Settings." provides our written comments pertaining to the draft. Enclosure 2 is the marked-up pages showing our suggested editorial changes to the draft.
Once these comments and changes have been incorporated into the NUREG, the final version should be submitted for publication.
Sincerely.
Original SiEned By Carl H. Berlinger Carl H. Berlinger, Chief Generic Communications Branch Division of Operational Events Assessment Office of Nuclear Reactor Regulation
Enclosures:
1.
Generic Communications Branch Comments on Draft NUREG/CR-4661 dated August 25, 1989 2.
Marked Up Pages from Draf t NUREG/CR-4661 dated August 25, 1989 DISTRIBUTION w/ enclosures FJMiraglia, NRR CERossi, NRR CH8erlinger, NRR RJKiessel, NRR CHaughney, NRR JAcalvo, NRR PDR Centd1Til'es.;J.
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Y Novenber 8, 1989 4
Generic Communications Branch Coments on Draft NUREG/CR-4661 Dated August 25, 1989 Abstract, Third Sentence (page iii) - Revise the sentence to read "The 1.
report includes documentation and status of the review of Action Item e of the bulletin completed through the issuance of Generic Letter 89-10 on June 28, 1989. Action Item e requested the bulletin addressees to submit a report identifying the maximum differential pressures to be expected and the program to accomplish the goals of the bulletin."
2.
Introduction. Fifth Paragraph (page 1) - Revise the paragraph to read "In order to provide a consistent basis for reviewing individual utility responses, NRC reviewed and commented on three owners groups reports.
The chronology of these reviews is included in Appendix C."
3.
Scope (page2)-Addanewitem7toread"Preparerequestsforadditional information for facilities which have unfavorable reviews (see Page B-27)." Renumber the subsequent item.
4.
Sumary, Jtem 3 (page 3) - Hope Creek 1 is indicated as not having satis-factcry completion documentation whereas Table B-1 (page B-10) indicates the review status as being " Complete." Please bring the two portions of the report into agreement.
5.
Sumary, Item 3 (page 3) - Provide a description as to why these facili-ties are not considered as having satisfactory completion documentation.
If the description is contained elsewhere, provide reference to where it can be found.
6.
Table B-1, Millstone 3 (page B-13) - Provide a footnote (as was done for the Limerick 1,2 entries on sage B-12) indicating why the facility is considered incomplete even t1ough all table entries appear to be complete.
7.
AppendixA,CoverSheet(unnumberedpage) Provide a table of contents as was done for Appendix C.
l l
8.
Appendix B, Cover Sheet (unnumbered page) Provide a table of contents as was done for Appendix C.
I 9.
Appendix C, BWR Owners Group (page C-1) - Add the August 8, 1988, letter from Charles E. Rossi to Donald N. Grace which accepted the supplement.
- 10. Appendix C, SNilPPS (page C-3) - Add Inspection Report 87-32 which con-tained the approval of the program.
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November 8, 1989 j?f~
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Documentation is e ovi/ed n this repor for the esecut f
RC Bulletin 85-03.
h ees t o develop and i pl[e N'.ctd ;'t purpose was to rg vest 11 e e t programs to ensure thatrsuitch s t ings r
oncertainsafepn-fe ted motor-operated valves are sele i d, set 3 and maintained t'y h reifable valve operation wh n valves are subj ect ed t ok; ximum dif f erent ial pressures expect ed'*HMT the design basisf The report includes (1) documentation of the partially completed review of Action Item e of the bulletin, which is concerned with the selection of critical motor-operated valver, (MOVs)in emergency systems, and the development of the switch setting programs for these valves by the licensees, and (2) the documentation of the complete closecut of the bulletin through the superseding Generic Letter 89-10 Licensee actions for Action Item e were completed satisfactorily for 102 (86*4) of the facilities for which actions were required.
Satisfactory completion of acti:n; for the remaining 17 facilities is ensured by 4he r;;&=arti
' the generic letter.
In the report conclusions, the inter-relationship of the generic letter and the bulletin is presented.
Background information is supplied in the Introduction and Appendix A.
O e
3 i
CLOSEOUT OF IE BULLETIN 85-03:
MOTOR-OPERATED VALVE COMMON MODE FAILURES DURING PLANT TRANSIENTS DUE TO IMPROPER SUITCH SETTINGS 8'gg &
/kmq( cor d, b6M$ y vg4 cW&sj INTRODUCTION Cg:seoutofIEBulletin85-03andSupplement1iscompletej,4ar-t n-h M '
" - Generic Letter (GL) 89-10 (See Page A-33).
The extended program of the GL enables the NRC to cancel the requirement for further reporting to the bulletin and its supplement.
In accordance with the Statement of Work in Task Order 012 under NRC Contract 05-85-157-02, this report pr ovides documentation det oS the review status of Action Item e of IE Bulletin 85-03 Documentation is based on the records obtained from the NRC Document Control System and the NRC/NRR project managers.
This review covers Action Item (a) of_the bulletin andJbe program for description of the scope of this report follows the \\of Mg5 bMM.
through (d)f(see pages A-4 and A-5)
A Q-, action items (b)
O introduction.
IE Bulletin 85-03 was issued n November 15, 1985 because of concern about incidents caus d by the improper switch settings of motor-operated valves (MOVs in feedwater systems at two facilities.
Earlier in 198 complete loss of feedwater had occurred at Davis-Besse lg partial loss had occurred at Sequoyah 2e et4 A lve suitch setting problems had been identified at boJh facilities.
Supplement 1 o f IE Bu l l e t i n 85-03 wa s i s s u e d t o 1Fg e:,
owners of boiling water reactors (BURS) on April 27, 1988.
The purpose of this supplement ukt to clarify which valves were to be included in the BUR program and the meaning of inadvertent equipment operations.
fg g
fedr onpermitforh4 Each holder of an operating license or a con tru
+ive actions to a nuclear power reactor was required to tak in MOVs would [be L
ensure that valve operator switches of c ert
^ " i ~. P2 w checked for operational readiness, - ---
.+ -
For most facilities, the bulletin ar plied to MOVs in dish pressur e coolant injection / core spray ar d emergency feedwater systems (RCIC for BURS).
For older faci {11 ties without the above syst ems, t he bulletin applied to MOVs f rM emergency systems with gf>
/
the highest pressures.
Because the bulletin is cice+d-m sup4 N 6 Generic Letter 89-10. the ec.
action item f <the ei tL
-m letely in thip refort.
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g, n o t b e e n r e v ' eue d c omp$ip P4g v/r19Fe; # /v/
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In order to provide a consistent basis for revleutng utility responses. NRC review comments about owners group reports on affected MOVs were presented to the groups for action.
The NRC revieu comments are identified in Appendix C but are not presented in detail.
l For background information e,W Te w ret n iie w IE Bulletin l
'85-03. Supplement 1 of the bulletin. related IE information notices. NRC Temporary Instruction 2515/73, Generic Letter 1
l
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c due dates are included in Appendix A.pand a record of changes in.
89-10, a1 summary of required actions e
Review of utility responses and NRC/ Region approval letters or inspection reports i
is documented in Appendix B,0; 15: betd fui..eisetin; t..
!!r-aree re-f:r :re: cf Sel',etin Action ite,; e; The chronology of review of owners group reports is included in Appendix Cp 4+r ard;r ta d:ce :-t-t5: 50:!: ef-th,sec;r raded iyrirei ae=ase+++
te Art t em p.
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mo i"etie-i; th: N"0.
An example request for ad utional information (RAI) is presented in Appe.wdix D in ceneral form,ir Ord:r te d:::r!E: 15: ' i r,e l d*+weiteta;n e r r a mz i r :d 2: t i:n a-Abbreviations used in this report and associated documents are presented in Appendix E.
Favorable rewieus of utility respor.ses to the bulletin and to requests for additional information are brought to the attention of the NRC regions by means of feeder reports from NRC Headquarters (see Table B-3).
Satisfactory completion of Action p# p' i
ltem e is documented by-means of regional letters or inspection reports to the utilities wh.;h are be;;
eri -t h e Tev er eb ri e-; v a -u; L; N^C Hvedyuait:r:-t-d the r eii e-n :1 ev ioeti;r.r (see Table B.1).
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- 1. Close IE ulletin 85-03 and Supplement 1 completely on the basis +f Generic Letter 89-10 (see Page A-33).
- 2. Document the review of Action Item e of the bulletin and the supplement prior to issuance of the generic letter.
Mid
- 3. Exclude :: r!-tm revieu ofdfinal results of the bulletin (action items b,c,d and f)X except program items related to Action Item e.
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- 4. Include the following itemst a) study of piping and instrumentation drawings (PLIDs) or FSAR flow diagrams by reducing them to manageable sketches, including only the subject MOVs (similar to those in the owners group reports) b) selection of affected valves c) comparison of differential pressures, and d) evaluation of programs and schedules.
- 5. Evaluate the following typical characteristics:
a) conformity to owners group reports b) similarity of comparable systems, and c) agreement with bulletin requirements.
Ipde$s'&ionof valves other then ihe MCV+ into consideration in
- 6. T k eva. 9 ting the systems (when necessary).
- 7. Prepare feeder reports for facilities which have favorable
' e "v i e s t-i u ine o i !-e n t i c ri ei-reviews (see Page B-31),tiv v
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SUMMARY
- 2. IE Bulletin 85-03 and Supplement 1 ar e closed for all 119 P
nuclear power f acilities on the basis -e+ Generic Letter 89-10
+
L (see Page A-33).
- 2. Satisfactory completion of Bulletin' Action Item e has been dccumented for the following 102 facilities for which NRC/ Region letters or inspection reports sent to the utilities indicat dcompli,ance with required actions:
Beaver Valley 1,2 Fort Calhoun 1 Robinson 2 Bellefonte 1.2 Fort St. Vrain.
Salem 1,2 Big Rock Point 1 Ginna San Onofre 1,2,3 Braiduood 1,2 Grand Gulf 1 Seabrook 1 Browns Ferry 1,2,3 Harris 1 Sequoyah 1,2 Brunswick 1.2 Hatch-1,2 Shoreham Byron 1.2 Indian Point 2,3 South Texas 1,2 Cellaway 1
.Kevaunee St. Lucie 1.2 Calvert Cliffs 1,2 Moine Yankee Summer 1 Catauba 1,2 McGuira 1,2 Surry 1,2 Clinton 1 Millstone 1.2 Susquehanna 1,2 Comanche Peak 1.2 Monticello TMI 1 Cock 1,2 Nine Mile Point 1,2 Trojan Cooper Station' North Anna 1,2 Turkey Point 3,4 Crystal River 3 Oconee 1,2,3 Vermont Yankee i Davis-Besse 1 Palisades Vogtle 1.2 Diablo Canyon 1.2 Palo Verde 1,2,3 UNP 2 Dresden 2,3 Peach Bottom 2,3 Wolf Creek 1 Duane Arnold Perry 1 Yankee-Roue 1 Farley 1,2 Point Beach 1,2 Zion 1,2 Fermi 2-Prairie Island 1,2 i
FitzPatrick Rancho Seco 1 1
- 3. Satisfactory completion of Bulletin Action Item e hes not been facumented ;cti;4ec4er;', for the following 17 l
_1acili'ies:
l l
Arkansas 1,2 Limerick 1,2
- Quad Cities 1,2 Haddam Neck Millstone 3
- River Bend 1
-Hspe Creek 1
- 0yster Creek 1 Uaterford 3
- LaSalle 1.2 Pilgrim 1
- Uatts Bar 1,2 l
- Issuance of feeder reports has not been approved.
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' 4. Because responses to the' bulletin or responses to RAls are satisfactory, issuance of feeder reports (see Page B-31) has ofthe119 facilities!['
been approved for the following ill (93')
4 k at%ede.
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' Arkansas l',2.
Fort St. Vrain Rancho Seco 1 Beaver Valley 1,2-Ginna Robinson 2 Bellefonte 1,2 Grand Gulf 1 Salem 1,2 Big Rock Point 1 Haddam Neck San Onofre'1,2,3 Braidwood 1,2 Harris 1 Seabrook 1 Brouns Ferry 1,2,3 Hatch 1,2 Sequoyah 1,2 Brunswick 1,2-Hope Creek 1 Shoreham Byron 1,2 Indian Point 2,3 South Texas 1,2 Callaway 1 Keuaunee St. Lucie 1.2 Calvert Cliffs 1,2 Limerick 1,2 Summer 1 Catauba 1.2 Maine Yankee Surry 1,2 i
Clinton 1 McGeire 1.2 Susquehanna 1,2 Comanche Peak 1.2 H111 stone 1,2,3 THI 1 Cook 1,2 Honticello Trojan Cooper. Station Nine Mile Point 1,2 Turkey Point 3.4 Crystal River 3 North Anna 1.2 Vermont Yankee 1 Davis-Besse 1 Oconee 1,2,3 Vogtle 1,2 Diablo Canyon 1,2 Palisades UNP 2 Dresden 2,3 Palo Verde 1,2,3 Waterford 3 Duane Arnold Peach Bottom 2,3 Uolf Creek 1 Farley.1,2 Perry 1 Yankee-Rowe 1 s
Fermi 2 Pilgrim 1 Zion 1,2 FitzPatrick Point Beach 1,2 Fort Calhoun 1 Prairie Island 1,2 5.htssuanceoffeederreportshas sjteen approved fo the following eight (8) facilitiest explained belouj ]
LaSalle 1.2 Quad Cities 1.2 Uatts Bar 1,2 Oyster Creek 1 River Bend 1 LaSalle_142_ IGE 11 The responses of 05-02-88 and 05-18-88 to the RAI-and the response of 06-03-88 to Supplement 1 of-the bulletin l
do not reflect the BUROG position expressed in NEDC-31322 Supplement 1 dated July-1988 A later response predating issuance of the GL on 06-20-89 has not been found.
LaSalle is listed as a BUROG member on Page A-1 of NEDC-31322 dated September 1986'.
DX512c_Cteek_1_1GE11 A response to the RAI of 12-08-86 predating issuance of the GL on 06-28-89 has not been received.
The response of 01-13-89 is a request for extension.
Quad _Cliies_122_1GE11 The responses of 05-02-88 and 05-18-88 to the RAI and the response of 06-03-88 to Supplement 1 of the bulletin do not reflect the BUROG position expressed in NEDC-31322 Supplement 1 of July 1988 A later response predating issuance of the GL on 06-28-89 has not been found.
Quad Cities is listed as a BUROG member on Page A-1 of NEDC-31322 dated September 1986.
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Bivec_ Bend _1.1GE11 The response of 08-18-88 o the RAI and to Supplement 1 of the bulletin is not complete A iater response-y predating-issuance of-the GL on 06-28-89 4:.::JeJe River Bend C
is listed as a BUROG member on Page A-1 of NEDC-31322 dated September 1986 m
Walis_ Bat _142_1W11 A response to the RAI of 02-02-88 Predating issuance of the GL on 06-28-89 has not been found.
6.LThe fo11owing facilities which have been shut down indefinitely or permanently (SDI) or.have had construction halted indefinite)y (CHI) are not included in-T M : 0.1 Tur JN54 review statusy ef TA A/s g,/,
. Dresden 1_________SDI Perry 2____________ CHI Humboldt Bay 3____SDI Seabrook 2________.. CHI' Indian Point 1____SDI THI 2_____________ SDI Lacrosse __________SDI.
UNP 1.3____________ CHI CONCLUSIONS
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-1.
The extended scope of GL 89-10
'- f P C6t 4 9
-* "-the need for further reporting on IE Bulletin 85-03 and Supplement-1.
yark A 2.TheinformationgatheredfromIEBulletin85-03formeddthe basis 44-Generic Lett er 89-1 St
- l#905H4 5
- 3. Satisfactory completion of Bulletin 85-03 Action Item e for the-17 facilities listed in Summary Item 3 (see'Page 3) is ensured by-the issuance of GL 89-10.
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CRITERION FOR REVIEU OF BULLETIN ACTION ITEM e-i Bulletin Action Item e is complete.for facilities to which'the H
followingicriterion applies:
An.NRC/ Region inspection report or letter to the facility s
Lindicates that the ut.dlity response to/the bulletin and (in most cases) the response to an NRC request for additional information (RAI) comply with actions required by Action Item e.
j Notes:
- 1. Refer to-Page A-41 for a " Summary of Bulletin Actions per Item e".
to pages A-4 through A-6 for the complete actions ~and to pages A-11 and A-12 for the clarified actions required for BURS.
1
- 2. RAIs [ Gulf 1. Millstone-1 Wolf Creek 1 and Yankee-Rowe 1.
ere not required for four (4) facilities, namely, Grand
- 3. A second RAI was required for eight (8)-facilities.
- namely, Callaway 1. Kewaunee San Onofre 1. Seabrook 1.
South Texas 1,2 and Susquehanna 1.2.
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- 4. For a list of the nine-(9) MOVs to be considered for inadvertent operations at BUR facilities, see Table B.4 on Page B-36 l
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SUMMARY
OF BULLETIN ACTIONS PER ITEN e u
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a.
Revieu and' document the design basis and the maximum differential pressure for opening and closing each MOV in high pressure coolant injection / core spray and emergency feedwater systems (or reactor core isolation cooling systems for BURS).
-For facilities without-the'above systems, review the I
emergency systems with the highest pressures.
Refer to Table B.4 (see Page B-36) for the list 1of affected valves for BUR facilities.-
<tJlnd lMlUd/#
Prepare a [rogram;.for selecting and establishing switch b.
settingsy und ed! ; the results of Item a and considering w
factors such as friction, margin of safety, degradation and.
wear.
c-Prepare a program for changingTsettings of-individual valves to those established in Item b (as appropriate), and for j
demonstrating operability by at least stroke testing each vs1ve.
,,qpg.
-d.
Prepare a program for preparing or revising pr cedures to ensure that correct suitch settings are deter ined and maintained throughout the life of the plant eer.;'4eiluv=
recommendations and in:'"]>!nc moni oring of valve industry Irlku S6 periormance.
v>hich inclos6co e.
Submit a written report to the NRCg ir. :u....v the results of
- Item a and the program and schedule for completing items b through d.
Action 44e w lb C, V N
.26'M b
Notes: 1. The purpose of the prograMrequired is to ensure-proper selection, setting 3and maintenance of switches for MOVs in certain high pressure emergency cooling systems.
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- 2. Only rograms is included in this l
partial review of action items b, e and d,Fer Item-r, j
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- 3. Review of the responses to ction Item f is et included in the scope of is report; houe er, partial ll evaluation of this item er performed e7.neieinec irr l-ti; third centener under Oc;p:-(see Page 2).
For/c mplete!
11etin actions, see pages A-4 th ough 4.
A-6; for revised actions required for BURS-pee /
l Supplement 1, see pages A-11 and A-12 l
A-41 o
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REVISION OF REQUIRED DATES OF PROGRAM COMPLETION AND REPORTING
'ecliDD_liam_a (Reporting Results of Item a and Programs and ff q
Schedule for Items b, c and d) h' L
Initially, the due date for-reporting results of Action Item
- a. describing the programjand providing a schedule _uas May I
15, 1986 For plants with an OL, action items b through d were to be completed by November 15, 1987.
For plants with
[/p{ ~
a CP, these action items were to be completed by the later t
of November 15, 1987 or the
- hedulet date fo,r OL issuance.
dier fdkeletterofJune3,1986toJ.M.Fulton(Chairman
~
f t he BUR Ouners' Group) from J. M. Taylor (Director..IE), the SMR due date for initial responses ~- ^^ '
--*^^"
- E e ^ ^ > 4 4 4 a '= 1 1 u from May 15, 1986 to October 1, 1986 the writ ten requesta( of individual utilities within the owners' group.
Further, the end date of November 15, 1987 for completion of action items b through d b uld be extended only if requested and thoroughly Justified in the response due by October 1, 1986.
actioD_liam_f (Final Response)
Initially, the final response was due by January 15, 1988 for plants uith OLs and by the later of January 15, 1988 or the ; h-delci date of OL issuance for plants ujth cps.
M k/<wdsf.<
fv?-(keletteridentifiedabove,[theduedateofJanuary15, 1988 f or t he final wri t t en report s ""' ++ '^ ^"> - '
- onl y if requested and thoroughly Justified in the initial
"##g response due by October 1, 1986 Note that review of these final r esponses -Es not included in the scope of this report, except Scr it.; d nir-d et-:d i.
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Note:
A revised date for submittal of written reports for BUR facilities is specified in Supplement 1 of the bulletin (see Page A-12) 8 A-42
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f BUR OWNERS' GROUP (BUROG) k 1
September 2, 1986 (BUROG-8645)
Letter to J. M. Taylor (NRC/IE) from T. A. Pickens (BUROG), transmittal of BUROG Report NEDC-31322 dated September 1986.
fen )n sst o n.%ty
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2.
October 10, 1986 Letter to T. A.
ickens (BUROG) from E. L. Jordan (NRC/IE), 4 1" request for additional information about BUROG Report NEDC-31322.
3.
January 20, 1987 (BUROG-8707)
Letter t o E. L. Jordan (NRC/IE) from T. A. Pickens (BUROG), response to Item 2 above.
4.
January 30.1987 Letter (with enclosed review comments), to T. A. Pickens (BUROG) from E. L. Jordan (NRC/IE), formal request for i
additional information about BUROG Report NEDC-31322 5.
March 13, 1987 Letter to T. A. Pickens (BUROG) from E. L. Jordan (NRC/IE), review of Item 3 above.
- 6. - August 5, 1987 (BUROG-8742)
Letter to C. E. Rossi (NRC) from R. F. Janecek (BUROG),
response to Item 4 above.
7.
- July, I 1988 Letter to C.E. Rossi (NRC) from D.N. Grace (BUROG),
transmittal of BUROG Report NEDC-31322 Supplement 1.
July, 1988.
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