ML19262B135
| ML19262B135 | |
| Person / Time | |
|---|---|
| Issue date: | 09/27/1979 |
| From: | Vaughn Thomas NRC OFFICE OF INSPECTION & ENFORCEMENT (IE) |
| To: | Jordan E NRC OFFICE OF INSPECTION & ENFORCEMENT (IE) |
| Shared Package | |
| ML19252A551 | List: |
| References | |
| FOIA-81-97, REF-SSINS-6820 NUDOCS 7912120402 | |
| Download: ML19262B135 (17) | |
Text
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$gp 2 ? 1979 MEMORANDUM FOR:
E. L. Jordan, Assistant Director for Technical Programs, Office of Inspection and Enforcement FROM:
IE Bulletin 79-01 Response Task Group Members
SUBJECT:
SUMMARY
OF SCREENING REVIEW 0F WRITTEN RESPONSE FROM LICENSEES OF OPERATING FACILITIES TO IE BULLETIN NO. 79-01 and 79-01A The initial screening review of the enclosed summary of written responses from licensees of operating reactor plants to IE Bulletins 79-01 and 79-01A is forwarded for your information.
The screening review is now complete for equipment inside primary containment.
Other than components previously identified in IE bulletins, circular, etc.,
no additional types of unqualified Class IE electrical components have been identified.
However, the screening review did reveal many cases where qualifi-cation documentation, component identification, service, and function, were not included in the initial licensee response to the Bulletins.
Followup action will be accomplished on these issues during the interim review which is the next work p.se to be undertaken by this Task Group.
Form letters and qualification data form sheets have been developed by the Task Group to issue to licensees in order to facilitate the interim review effort.
Acceptable qualification tes' methods and test reports and quidelines developed by NRR will also be used oy the Task Group during the interim review.
Any questions which you may have concerning the enclosed summary please contact me.
Vincent D. Thomas Technical Programs Division of Reactor Operations Inspection Office of Inspection and Enforcement
Enclosure:
As stated cc: (See next page) 2! % 225 CONTACT:
V. D. Thomas, IE g 9121 o 0 N /)A 49-28180
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E. L. Jordan cc:
V. Stello, IE N. C. Moseley, IE H. D. Thornburg, IE
- 5. E. Bryan, IE G. W. Rei.imuth, IE D. Eisenhut, NRR G. Lainas, NRR D. Tondi, NRR E. Butcher, NRR Regional Branch Chiefs Distribution:
IE Files IE Reading ROI Reading ADTP Reading V. D. Thomas, IE 2130 226
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UNITED STATES
{ B,. r [,g NUCLEAR REGULATORY COMMISSION SSINS 6820
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WASHINGTON, D. C. 20555
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%..~ - f SEP 2 71979 MEMORANDUM FOR:
E.
L.' Jordan, Assistant Director for Technical Programs, Office of Inspection and Enforcement FROM:
IE Bulletin 79-01 Response Task Grcup Members
SUBJECT:
SUMMARY
OF SCREENING REVIEW OF WRITTEN RESPONSE FROM LICENSEES OF OPERATING FACILITIES TO IE BULLETIN NO. 79-01 and 79-01A
~
The initial screening review of the enclosed sumniary of written responses frsm licensees of operating reactor plants to IE Bulletins 79-01 and 79-01A is forwarced for your information.
The screening review is now complete for equipment inside primary containment.
Other than components previously idenified in IE bulletins, circular. etc.,
no additional types of unqualified Class IE electrical components have been identi fied.
However, the screening review did reveal many cases where qualifi-cation documentation, component identification, service, and function, were not included in the initial licensee response to the Bulletins.
Followup action will be accomplished on these issues during the interim review which is tne next work phase to be undertaken by this Task Group.
- orm letters and qualification data form sheets have been developed by the Task Group to issue to licensees in order to facilitate the irterim review effort.
Acceptable qualification tes; methods and test reports and quidelines developJd by NRR will also be used by the Task Group during the interim review.
Any questions wnicn you may have concerning the enclosea summary please contact me.
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Vincent D. incmas Technical Programs Division of Reactor Operations Inspection Office of Inspection ano Enforcement Encicsure:
As stated cc: (See next page)
CONTACT:
V. D Thomas, IE 49-2S180 2130 a,, t
E. L. Jordan cc:
V. Stello, IE N. C. Moseley, IE H. D. Thornburg, IE
-0.
Eisenhut, NRR G. Lainas, NRR D. Tondi, NRR E. Butcher, NRR Regional Branch Chiefs 4
SUMMARY
OF SCREENING REVIEW 0F RESPONSE TO IE SULLETIN NO. 79-01 Written responses to IE Bulletins No. 79-01 and 79-01A have been received from fi f ty-six (56) operating reactors.
Indian Point Unit 1 and Humboldt Bay reactors were not required to respond to these Bulletins because both plants have been in shut-down status for an extended period of time with little possibility of going operational in the foreseeable future.
Fort St. Vrain, a gas cooled reactor, was not part of the review effort because it had been earlier determined that the information requested of licensees in IE Bulletin 79-01, related only to LCCA environments postulated to occur in both BWR and PWR types of power plants. Additionally, eleven SEP plants are not part of this review.
This screening review involved only the equipment reported by the licensees to be insice the containment.
A review of the data contain d in the licensees' responses (presented in the format provided by RII) indicate that three casic methods were used for reviewing and providing written evidence of equipment qualification.
These methocs were:
(a) Generic Comoonent Methoc This generic component method provided a listing of components by generic-types such as pressure transmitters, differential cressure t ansmitters, electrical penetrations, etc., with their environmental qualification cata.
Crystal River, and Oconee responses are examples of this type of su:mittal.
(:)
^ ferral Method e
Tne referral method listed otner documents such as tne FSAR, Topical
'; encor Test Reports, or letter to NRC as containing tne written evidence of e t ironmental qualification or acceDtance.
<asocnses rrom rarley 1 and 9atch 2 are examoles at tais tyce submittal.
E st m Analysis MetDoc c) f s
~ne system analys s metnod utili:ec :ne fcilowing e.aluation logic:
si The reactor plant systems recuired to function uncer postulatec accidents were icentified.
(2)
Tne safety-related electrical compcnents within each reactor plant system were icentified.
(3)
Each safety-related electrical comconent icentified oy system, functicn, etc., was lis*.ed along with its environmental cualifica-tion data.
Responses from Brunswick 1 anc 2, and Calvert Cliffs '.
and 2 are examples of this tyce suomittal.
nn n Of the fifty-six operating plants responding to IE Bulletin No. 79-01 and 79-01A, forty-three licensees have provided information in accordance with the Bulletin requirements while thirteen licensees have submitted responses which required further contact from the NRC in the form of meetings, telephone calls, and letters to obtain sufficient data to complete the screening review.
A review of the 56 operating plants identified the following generic items as not being qualified for service in a LOCA environment.
These items are:
Item Manufacturer Solenoid Valves Automatic Switch Co.
Control Cable Continental Wire & Cable Terminal Blocks Meter Device, Inc.
Valve Stem Limit Switches NAMCO Transmitters.
~
Foxboro, Bart:n, and F. & P.
In each case, where unqualified equipment was identified at an operating plant, that licensee has committed to replace the equipment in question with ecuioment known to be qualified for service in a LCCA environment, and has orovided both a schedule for replacing the equipment and a justification for continued operation.
All 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> reports on unqualified equipment will ce reviewed by NRR.
To date, there nave been 35 separata licensee. reports involving 32 plants of equipment which the licensees uelieve may not be qualified for service in a LOCA environment.
With respect to the licensees mentioned above which dic not respond in accord-ance to requirements in IE Bulletin No. 79-01, the following action taken by the Task Group is summarized:
Telephone calls 13 Folicw-co letters to licensees 3
Follow-up meetings with licensees 2
e ex actior to te taken oy tne Task Group is the interi-eview.
'ne
'rteH m review action involves an evaiuation as to tre sufficiency of tne
- uCi'icaticn metnocs and results for each class I~ comocnent anicn couic be 5;;jectec to a LCCA environment.
The information compile: in the screening
's.'ea onase will be verified for applicability and tne cualification of ea 4: ment to tne LCCA environments will be compared with tne 5AR soecifiec ar- ^ ments and related staff tecnnical positions.
Cualificat on documenta-i
.4 r. -111 be reviewed and an evaluation mada as to its suitacility.
As was the :ase in the screening review, tnis phase sill be limitec to components insice containment.
As a result of the screening review of licensees' resoonses, the Task Group members, propose the following acticns to be taken prior to recuesting acdi-tional information from licensees and performing tne detailed interim review.
213C) 230 1.
A preliminary copy of the DOR staff acceptance guidelines be issued to the Task Group members.
This would be used as a preliminary guide during the interim review and should minimize the numcer of additional informa-tion requests to the licensees.
2.
The licensee be informed that the systems analysis method (identified above) is the preferred method for reviewing and providing written evidence required by paragraph 3 of the Bulletin.
Also, the task group members from RII are presently developing a set of form data sheets which will be provided as a guideline to the licensees to furtner indicate the specific information required for each safety-related electrical component.
3.
A determination should be made as to how Task Group members are to deal with the safety-related components for wnich no cualification documenta-tion is presently available per tne licensee's response.
4.
A determination should be mace as to whether the Task Group members can accept minor deviations from parameter specifications values or refer this Droblem to NRR.
Enclosed for information is a detailed summary for each coerating reactor responding to IE Bulletin No. 79-01.
The summary identifies deficiencies found curing tne screening review of each plant and provides the follow up action planned cy the Task Group to resolve the issues.
D
RECAP SHEET
SUMMARY
OF SCREENING REVIEW FOR IE BULLETINS NO. 79-01 and 79-01A The Task Group has completed the screening review phase of data submitted by utilities having an operating license in response to IE Bulletins No. 79-01 and 79-01A.
The data from this screening review phase are identified in the following pages.
1.
Licensee: Boston Edison Co. 50-293 Pilgrim 1 Findings:
1.
Junction Box Qualification - Raciation level qualified to less than SAR reauirement.
2.
Namco Limit Switches - Not qualified.
Action Taken:
1.
Item 1 above will be reviewed during the interim review pnase.
2.
Item 2 above will be replaced with a qualified comconent in accordance with schedule approvec by NRR.
2.
Licensee:
Northern Nuclear Energy Co. 50-336 Millstone II Findincs:
1.
Flow and pressure transmitter connectors not qualified to the same recuirements as the trans-mitters.
Action Taken:
1.
Item 1 acove will be reviewec during the interim review pnase.
Licensee:
Yankee Atomic 50-309 Maine Yankee
- iccings
1.
The penetrations were not tested to SAR Scecifica-tions.
Radiation was cerformed by analysis.
2.
Radiation analysis was :erformec on T.otors. ca:les.
terminal OlocKs anc mctor coerators.
a tion Taken 1.
During the screening phase o' ne Orogram ne c
qualificaticn reports associstec oitn the ecui mert in items 1 anc 2 acove will Oe reviewec.
3.
Licensee:
Power Authority of the State of New 'f o r k, Inc. 50-2c7 Indian Point 2, 50-256 Indian Point 3
- incings:
1.
Skimmer Electric Valve cualification net estaclished.
2.
Terminal Blocks r,ualification not estaclished.
3.
Transmitters qu.lihcation not established.
4 Limit Switch or MOV's nct cualified.
5.
ASCO solencia salves not cualified.
9 n,,
n.
4 Action Taken:
The items listed above will be reviewed during the interim review phase.
The unqualified items will be replaced with qualified items in accordance with schedule determined by NRR.
4.
Licensee:
Vermont Yankee Nuclear Power Co. 50-271 Vermont Yankee Findinas:
1.
Power Cable 600V& 1000V Rome XLP/PVC/PVC radiation qualified by analysis.
2.
Power Cable, Kerite HTK, qualification document not identified.
3.
Solenoid valve not qualified to radiation level.
4.
Thermocouple Thermo Electric Co. not qualified.
Action Taken:
1.
On items 1-2 above, the data will be reviewed during the screening review phase.
2.
On item 3 above, the licensee will replace with a qualified component in accordance with schedule aporoved by NRR.
3.
On item 4 above, the licensee is gathering data.
5.
Licensee:
Philadelphia Electric Co. 50-277 Peach Bottom 2, 50-273 Peach Bottom 3.
Cindincs:
1.
Limit Switenes not qualified.
Action Taken:
1.
The licensee clans to replace limit switcnes witn qualified components in accordance witn scnecule approved by NRR.
6.
Licensee:
Public Service Electric & Gas Co. 50-272 Salem 1, 50-206 Salem 2 Ci9cincs:
1.
Barten T ansmitte s for ; nit i net cu214'iec.
2.
- isner ;crte-Transmitters 1C32c63 1505.01 c; nct qualifiec.
a tion Taken:
1.
Licensee to reciace _ransmitters 3, Unit ; oith c
Earton 754 2.
Licensee to rec' ace risrer orter transmitte s witn Rosemor.: 1153?'s.
7 Licensee:
.Vetropolitan Ecison Co. 50-235 TMI-1 rindincs:
1.
As a general s atement, from the a tc suomitted it a;; ears tnat cnemical anc raciatic : testing was not performec on all comconents.
2.
The containment fan motors were tested in secue ce of temoerature, pressure, relative humicity, anc t9e-spray cnemical.
Radiation testing is nct mentlenec.
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Action Taken:
1.
Review the data and method to establish the testing requirements 2.
To review the test data determine acceptable method.
8.
Licensee:
Niagara Mohawk Power Co. 50-220 Nine Mile Point 1 Findincs:
No deficient items identified.
9.
Licensee:
Power Authority of the State of New York 50-333 Fitzpatrick Findings:
1.
Response to IE Bulletin No. 79-01 is not adequate.
Action Taken:
1.
The licensee was called and recuested compliance with requirements outlined in IE Bulletin No. 79-01.
Response to call was still not adequate and a letter was issued to Licensee.
Licensee excected to respond in about two weeks, early October-10.
Licensee:
Duquesne Lignt Co. 50-334 Beaver Valley 1 F i r.di ncs :
1.
ASCO Solenoid Pilot valves not cualified.
2.
Meter terminal blocks not qualified.
3.
Low voltage continental cable data for qualification was not available.
Action Taken:
1.
Meeting in HQ with NRR, IE and licensee in wnich the licensee committec to testing of terminal blocks, replace solenoid valves and cable with qualified comoonent curing the next refueling outage scheduled for mic Octccer,1979.
NRR conclucec tr.at tneir bases for continued operation (5-7 *eeks) are acceotable.
11.
Licer.=
Virginia Electric 1 Dower Co. 50-333 'icrth Anna 1
" r :i nc s :
1.
ASCO sciencic valves not cualifisc.
2.
Electrical pressure seals to occy of transm tters i
cuali fication cata cuestionable.
3.
ASCO.aives not cualifiec.
a.
NAMCO Limit switches not cualifisc.
a ticr Taken-1.
Licensee has statec tnat tney ili replace items 1.
c 3, & 4 aDove.
2.
Item 2 acove will te reviewec curing tne interim review onase.
12.
Licensee:
Baltimore Gas & Electric Co. 50-317 Calvert Cliffs 1, 50-313 Calvert Cliffs 2 n -,
Findinos:
1.
ASCO solenoid valves not qualified.
2.
Thomas Belt: 53000 series terminal lugs missing qualification data.
3.
Junction boxes field built, and no qualification data available.
Action Taken:
1.
Licensee has an on going replacement program estimated to be completed during next refueling outage.
2.
Items 2 and 3 above to be reviewed during the interim program phase.
13.
Licensee:
Arkansas Power & Light Co. 50-313 Unit, 1 50-368 Unit 2 Findincs:
1.
The licensee stated that "
.No general environment qualification standard r<isted."
2.
The test which the licensee performed accears to be acceptable in the temperature pressure, RH, and chemical spray area.
The radiation exposure levels for the equipment appears to be below requirements for some components.
Action Taken:
1.
The above cata will be reviewed during the interim review phase of tne program and an analysis of the radiation levels will be examined.
~
14 Licensee:
Indiana & Michigan Power Co. 50-315 and 50-316 0. C. Cook Units 1 & 2.
Findincs-1 The respcnse did not address limit switches that provide position indication of valves ahich are used for primary containment isolation.
2.
Region III has not received a formal response to IE Eulietin No.79-01A. (Tnis licensee has since submi tted resconse to 79-01A. )
Action Taken:
1.
A letter nas been sent to tne license requesting adcitional information.
~5.
_icensee:
- ommonwealtn E:ison 50-295 50-3C4, Zion ~ L 2 Fi-cincs:
1.
Fisher and Porter transmitters were not suojected to chemical scray-The transmitter macei nunters are Nos. EP104 CECA-NS, 1302195KEEAABES-N5, ICE 2a96VC.ES-N, 10S2496PSSASSB-NS anc 5CEP1031BCXA-NS.
We uncerstand a Westingnouse letter (HS-CE-719) cated July 25, 1975, discusses the omission of the enemical spray.
Region III dces not have a copy of :nis letter.
2.
The licensee cid not address limit swit nes tnat provice cosition indicatio of valves which are used for primary containment isolation.
This matter 4as discussec on August 29, 1979 with CECO's Nuclear n - c e
Engineering Department (by telephone).
The licensee stated that they would evaluate this item for all of CECO's plants.
3.
Kerite cgble splices do not meet FSAR requirements of 1.5 X 10 rads, howevgr, they do meet design speci-fications of 1.2 X 10 rads.
4.
D. G. O'Brien electrical penetrations were not subjected to chemical spray.
The A/E and penetration manufacturer have evaluated the corrosion effects of the chemical spray and have concluded that no delete-ricus effects would be experienced during a short duration during accident.
5.
Reactor containment fan ualeg motor does not meet FSAR requirements of 1.5 X 10 racs.
Qualification g
test was 1.4 X 10 rads. Licensee's statement "that radiation level is close enough to expected accident radiation level to be acceptable."
6.
Licensee is replacing unqualifiec ASCO solenoic valves curing the next refueling outage for Unit 1, October,1979 and Unit 2, February,1980.
7.
ASCO solenoid valves are used to control the position of reactor containment fan cooler campers.
In regarc to this the licensee stated "In tne c. vent of an accident, the solenoid valve vents anc the damcer shifts to the accident mode" Action Taken:
1.
The licensee was contacted by phone for additicac1 information on items 2, 6. and 7.
2.
Item 1, 3, 4, and 5 wili be reviewed during the interim review chase.
16.
Licensee:
Nebraska Puclic Power District 50-298, Cooper Findincs:
1.
Licensee states that no ASCC solenoid valves are subjected to LCCA environment.
"cwever. a creventive maintenance program is ceing estaolisnec sucn :na.
carts Y the sciencic valves will De replaced in accorcance witn :ne time period recommenced oy the manufacturer to maintain the cualifiec life of tne assemc:ec componen..
Initial ins;ection of eacn solenoic valve on safety-relatec systems will ::e comaleted by tne enc of :ne station's 1930 refueling outage.
Action Taken:
1.
The licensee was contacted by chone for additional information.
17.
Licensee:
Northern States Power Co. 50-263, Yont. cello Findincs:
1.
Solenoid valve for :ne reactor water sample isolation valve will be replaced witn a cualifisc solenoic valve during :ne next reft.eling outage scneduiec for Feb rua ry, 1960.
2 i30 C6 2.
Recirc pump discharge valve actuator motors have Class B insulation which test revealed are acceptable up to 210 F. However, to provide increased assurance that these valves will function in the LOCA environment, the actuators wi',1 be replaced with class "H" insulation models during the next refueling ou age scheduled for February, 1980.
3.
MSIV solenoid valves and motor operated "alve actuators have not been tested under actual radiation conditions.
The licensee believes that such testing is unnecessary since these components perform their tunction immediately upon detection of an accident and are not required to function thereafter.
Region III does not agree with this position since these components will see radiation during normal plant cperations.
4.
Monticello has stem-mounted limit switches of a type similar to those described in the bulletin (Namco Model SL3B2W) which are used on safety-related valves inside containment.
the licensee states that these switches are not required to perform their safety function for events that would result in a LOCA environment.
Therefore the licensee plans no action with respect to the bulletin.
However, Region III feels that the licensee did not address position indication for primary containment isolation valves.
Action Taken-1.
The licensee was contactec by phone for additional information on items 1 and 2.
2.
A letter has been sent to the licensee recuesting additional information on Item 4.
3.
Item 3 will ce revie ed curing the interim review pnase.
13.
Licensee:
Wisconsin Public Service Coro. 50-305. Kesaunee Findincs:
1.
Region III nas not recei.<ec a formal res;crse to IE Sulletin No.79-01A.
2.
The licensee nas mccified cxboro Yocel E110M trans-mitters sita Y:A moci'ication f-cm Foxcoro.
Regier III believes tnat tnis mocification is unde a generic review by NRR cue to the chemical spray analysis.
3.
D. G. O' Brian electrical penetrations were not suc-fected to chemical scrsy.
The A/E anc penetration manufacture have evaluated the corrosion effects of the chemical spray anc have concludec that no celete-ricus effects would be experiencec curing a short duration during an accident.
. Action Taken:
1.
A letter has been sent to the lic?nsee ecuesting additional information on items 1, 2 anc 3.
19.
Licensee:
Omaha Public Power District 50-285 Fort Calhoun Findinos:
1.
Unqualified solenoid valves will be replaced with Valcor Engineering Corporation or ASCO NP-1 nuclear grade solonoid valves during refueling outage, first quarter of 1980.
2.
Unqualified limit switches will be replaced with qualified switches during refueling outage, first quarter of 1980 and second quarter of 1981.
3.
Foxboro Model EllGM transmitters are equiped with the MGA modification.
Region III believes that these transmitters are under a generic review by NRR due to the chemical analysis.
Action Taken:
1.
The licensee was contacted by phone for additional information on items 1 and 2.
2.
Item 3 will be reviewed curing the interim review phase.
20.
Licensee:
Commonwealth Edison Co. 50-249, Dresden Unit 3 Findines-1 licensee is replacing the unqualified ASCO solenoid valve for the primary sample isolation line during the next refueling outage scheduled for March, 1980.
2.
The licensee did not address limit switches that provide position indication of valves wnich are used for primary containment isolation.
This matter was discussed with the site Tech Staff Engineer (by telepnone) on August 30, 1979.
The licensee statec that they would researcn tnis matter.
3.
Air oceratec valve for M5IV's is Automatic Valve Ccmpany Mocel No. C5512 anicn has nct been cualifiec to radiation requirements.
1::icn Taken:
1.
The licensee was contacted by phone or items ; anc :.
2.
Item 3 will be reviewec curing the ite-im review pnase.
21.
_ :ensee:
- cmmonwealth Edison Co. 50-25 50-255, Quad Cities Units ;
12
'rdincs:
1.
The licensee is unab'e to determine tne qua'ification of the primary saccle isolation solenoid valve (Iarget Rock Corp.). Mocel numcer not kno n at tnis time.
o This information will be obtainec curing a shcrt outage in Cctober, 1979.
2.
Air operated valve for MSIV's is Autcmatic Valve Company Model No. C5512 which has not Deen cualifiec to radiation recuirements.
2 i 23C) 238
. 3.
The licensee did not address limit switches that provide position indication of valves which are used for primary contaicment isolation.
This matter was discussed on August 29, 1979 with CECO's Nuclear Engineering Department (by telephone).
The licensee stated that they would evaluate this matter.
Action Taken:
The licerdee was contacted by phone on items 1 and 2.
Items 1 & 3 will be reviewed during interim review phase.
22.
Licensee:
Northern States Power Co. 50-232 50-306, Prairie Island Units 1 & 2 Findincs:
1.
Foxboro Mcdel E11GM transmitters having (MCA) environ-mental qualification mocification are installed inside containment. Region III believes tnat tnis modification is under a generic review by NRR due to chemical soray analysis.
Similar transmitters are being replacec at D. C. Cook 1 & 2.
2.
In regarc to Barton Model 385 transmitters, Region III believes that this tyoe of transmitter is clso under a generic review cy NRR.
3.
Region III has not received a formal response to IE Bulletin No.79-01A.
4.
D. G. O' Brian electrical penetrations were not suojected to chemical s; ray.
The A/E anc peretration manufacture nave evaluated the corrosion effects of tne c9emical spray anc nave conciuce: :nat not delete-ricus effects would be experience: curing a short curation of the accicent.
- ti:n Taken-1.
The licensee was contacted ;y : c e en item 3 sita a lette-fol'cw uc.
u 2.
Items 1. 2, and C.o
' :e rcie.sc cu-i g tne nter i-review anase.
_ ersee:
- avis-Eesse ri-dincs:
1.
Tne licensee :!ans :: reciace ncm-:Lalifiec limit s ni tcnes (Nr.C: EA170-21300:) on : ntai cent is: stion ia'.ves for indication ;_rpcses curing tne refueling outace Marcn, 1950.
2.
Sciencia valves insice contairment (ASCO v del e
HTXS316C25V anc HTXE210) nave nct been cual'fi ed y test.
The licensee perforT.ec an engineering analysis and states va'ves will perform sa#ety f_ncticr A
^~D 11.V LJl
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Action Taken-1.
The licensee was contacted by phone on item 1 and 2 above.
These items will be evaluated duri ' the interim review phase.
24.
Licensee:
Wisconsin Electric Power Co. 50-266 50-301, Point Beach Units 1 & 2 Findincs:
1.
Foxboro transmitters, Models 611 and 613 series have been modified to meet maximum credible accident (MCA) conditions. Region III oclie es that these transmitters are under a generic review by NRO Similar transmitters are being replaced at O. C. Cook 1 & 2.
2.
The licensee states that since the solenoid valves perform their safety function at the beginning of an accident transient and are not required to operate in the accident environment, the solenoid valves do not neec to be cualified for the accident environment.
However, the licensee does agree to replace tne Acetal clasic parts and Buna "N" gasket.
Replacements will be made througn the normal meintenance program.
Action Taken:
1.
Item 1 will be reviewed during the interim review phase.
2.
A letter has been sent to the licensee requesting additional information on item 2.
25.
Licensee:
Iowa Electric Light and Power 50-331 Duane Arnold Fincinas:
1.
Air cperated valve for MSIV's Autcmatic Valve Ccncany Model No. C5512 whicn nas not been cualified to radiation requirements.
2.
The licensee plans to reclace ncn qualifiec crim2 ry containment isolation valve cosition indication limit switcnes with qualifiec limit swi cnes cu-ing re"ueling cutage, :ecruary 1930.
3.
Recion III has not receivec a formal resocnse to IE Sulleti-No.73-01A.
ASCO sciencid valves were discussed ai n tne licensee on Sec;emcer c. 1979 (03 taleoncne).
ancuali'iec scleroic calves a l' ce recisce: curing next refueling cu age. Fecruary 1930.
Action Iaken.'
l.
The licsnsee was ContacteC Dy OnCne on item 3.
2.
Items 1 and 2 will De reviewec during interim review pnase.
26.
Licensee:
Sacramento to Municical Utility District 50-312, Rancho Seco Findinos:
1.
ASCO solenoid valves not qualified.
2.
Cerro cable deviated from SAR requirements during pressure testing.
Action Taken:
1.
Items 1 and 2 will be reviewed during the interim review phase.
27.
Licensee:
Portland General Electric 50-344, Trojan Findinos:
1.
Items listed in the IE Bulletin response 79-01 dppears to be qualified.
Action Taken:
1.
A review of the qualification data will be performed during interim review phase of the program.
23.
Licensee:
Virginia Electric & Power Co. 50-280 Surry 1 50-231 Surry 2 Findinos:
1.
ASCO solenoid pilot valves not qualified.
2.
Insufficient qualification data to complete interim review of most class IE equipment.
Action Taken:
1.
The ASCO valves identified have been or will be replaced in near future.
Licensee submitted 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> report on this issue.
~
2.
The licensee will be contacted by telephone with a letter follow up specifying deficiencies mentioned in Item 2 above.
29.
Licensee:
Tennessee Vally Authority 50-259 Browns Ferry 1 50-260 Browns Ferry 2 50-296 Browns Ferry 3 Cindincs:
1.
ASCO scienoid ;ilot valves nct cualified.
2.
Ste mounted limit switches not ;uali'iec.
3.
Ins;fficient qualification cata submi :ec tc com iete interim review of all class IE equipmen..
a tion Taken:
1.
The licensee nas committed to replace uncualifiec c
e;uipment in Items 1 anc 2 above.
2.
The licensee will ce centacted by pnene witn a letter follow up wnicn speci'ies deficiencies mentioned in Item 2.
3C.
Licensee:
Carolina Power & Light Co. 50-325 Brunswick 1 50-324 Brunswick 2 Cindincs:
1.
Stem mounted limit switches not qualified.
2.
Insufficient data sunmitted on majority of components reviewec.
,, 30., -at ct
Action Taken:
1.
The licensee was contacted by phone concerning item 1 above and requested to submit a 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> report on the unqualified limit switches.
2.
During interim review the licensee will be contacted by phone with a letter follow up to resolve concerns mentioned in item 2 above.
31.
Licensee:
Florida Power Corporation 50-302, Crystal Power 3 Findincs:
Insufficient data submitted on all class IE components identified in this licensee's response to IE Bulletin No. 79-01.
Action Taken:
The licensee will be contacted by phone with a letter follow up to resolve the deficiencies.
32.
Licensee:
Alabama Power Co. 50-348 Farley 1 Fincinas:
Insufficient data submitted to complete interim review phase.
Action Taken:
Licensee will be contacted by chone and witn a letter follow up icentifying ceficiencies.
33.
Licensee:
Georgia Power Co. 50-321 Hatch 1 50-366 Hatcn 2 Cindings:
1.
Insufficient data suomitted by tnis licensee.
2.
ASCO valves were icentified as unqualified.
3.
Licensee submitted LER's on the ASCO,alves.
Action Taken:
1.
Item 1:
Licensee will te recuested by letter to provide adecuate data to cmplete interim rev ew.
i 2.
Licensee plans tc replace uncualified devices witn cevices consicerec cuali'iec for service in a LCCA environment.
31
_icensee:
Du<e Power Cc. 50-259 Oconee 1 50-270 Oconee 2 50-237 Occnee 3 Ci cincs:
More qualification cata neecec on sil ccmconents identified in resconse tc ccmclete in*erim review.
Action Taken:
Ine licensee will be recuestec ey letter to provice sufficient qualification cata on comoonents mentioned in resconse.
35.
Licensee:
Carolina Power & Lignt Co. 50-251 H. 3. Rcbinscn rincings:
Insufficient data submitted on all cocconents listed in response.
O *, )
r.
/ $.-
Lrc t_
. Action Taken:
Licensee will be requested by letter to provide additional data to complete the interim phase.
36.
Licensee:
Florida Power & Light Co. 50-335, St. Lucie Findinas:
Insufficient data submitted with response to bulletin.
Action Taken:
Licensee will be requested by letter to provide additional qualification data to complete the interim review.
37.
Licensee:
Florida Power & Light Co. 50-250 Turkey Point 3 50-251 Turkey Point 4 Findinas:
Insufficient data submitted with response to bulletin.
Action Taken:
Licensee will be requested by letter to provice additional qualification cata to complete interim review.
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