ML20036B456
| ML20036B456 | |
| Person / Time | |
|---|---|
| Site: | Millstone  |
| Issue date: | 09/12/1991 |
| From: | Fuhrmeister R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | AFFILIATION NOT ASSIGNED |
| Shared Package | |
| ML20036A053 | List:
|
| References | |
| FOIA-92-162 NUDOCS 9305200212 | |
| Download: ML20036B456 (4) | |
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UNITED ST ATES I
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c 475 ALLENDALE ROAD D
KING OF PRUSSIA. PENNSYLVANIA 19406-1415
% '... *,o 11 SEP 1991 Docket No. 50-245 50-336 50-423 File No. RI-91-A-0144
Subject:
Allegation concerning Millstone Nuclear Power Station I
The NRC Regien I office has completed its follow up in response to the concern i
you brought to our attention on June 18, 1991, alleging that the deteriorated l
condition of portable radies and police cruisers could adversely affect the l
ability of the Town of East Lyme to respond to an emergency at the statien.
We referred your concern to the Federal Emergency Management Agency (FEMA), as indicated 11 our letter dated July 1,1991, since they are the agency tasked with eviewing effsite emergency planning.
We found your allegation to be unsubstantiated in that the State of Cennecticut Radiological Emergency Response Plan does not rely on resources provided by the towns.
This conclusien is based upon the FEMA response to our inquiry dated l
August 1, 1991. We plan no further action on this matter.
We appreciate you inferming us of your concerns and feel that our actions in this matter have been responsive to those concerns.
Should you 1. ave any additional questiens, er if I can be of further assistance in this matter, please call me collect at (215) 337-5222.
Sincerel,y,'
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l Roy L. Tuhrmeister Senior Allegation Coordinator t
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s CERTIFIED MAIL RETURN PECEIPT REOUESTED i
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l Dear I
The NRC Region I has completed its followup of the concerns that you brought to our our attention by way of memoranda dated October 7, September 29, and October 9,1990, j
alleging (1) procedural non-compliance with SP-EE-076, (2) a technical specification i
violatic a during instrument and controls troubleshooting, (3) an improper tagout during maintenance, and (4) a failure to comply with procedural requirements during fuel movement.
t With regard to issue (1), we have previously documented our review of this item in an g,l* l inspection report 50-336/89-13 and in a letter to you dated June 13,1990 (attached). We consider this matter both unsubstantiated and closed. The reason this issue is unsubstantiated is that you have not provided documented evidence that compliance with explicit prosisions of SP-EE-076 is recuired in the conduct of activities at Millstone Unit 2.
l With regard to issue (2), you alleged that no diesel generator power source was available during the maintenance. We documented our review of this item in inspection report 50-336/
l 90-22, section 5.1.2 (attached). As documented in our report, emergency power was availabic from a number of sources including manual start of the affected diesel generator.
l Having only one diesel available by manual start is a condition allowed during refueling at legation is therefore unsubstantiated. We consider this matter AECELPT FoR CERTIFIED M AIL
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ou alleged that maintenance was performed on the "A" steam c,e,r ting valve with an improper tagout. We reviewed this allegation in s
e Mee 3-22, section 5.1.1 (attached). We found that all required tations were used in the electrical isolation. Your a!:egation was i
i nd we consider this matter closed.
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Confidentiality:
k'as it requested?
Yes No 7 k'as it initially granted?
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Yes No k'as it finally granted by the allegation panel Yes No Does a confidentiality agreement need to be sent to alleger?
Yes No i
Has a confidentiality agreement been signed?
Yes No
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P.emo documenting why it was granted is attached?
Yes No 2
Alleger's[yggool Empicyer:
Position /Titie:
I Facility: MitcSrafue afvir a Docket No.: 6_.eet I
(A11egatien Summary (brief description of concern (s): fA,curts r w m e.o c.s
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rA Ecse.rnio?t Sovipnswr-i Number of Concerns: _
1 Employee Receiving Allegation:
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(first two initials a'nd last name)
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Type of Regulated Activity (a)A Reactor (d)
Safeguards (b)
Vendor (e) _ Other:
l (c) [ Materials
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(Specify) j Materials License No. (if appitcable): _
i FunctionalAres(s): 4(a) Operations (e) Emergency Preparedness
_ (b) Construction (f) Onsite Health and Safety
_(c) Safeguards (g) Offsite Health and Safety l
_ (d) Transportation (h) Other:
1 (NRC Region I Fom 207 Revised 30/89)
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l This letter refers to concerns that you provided to us on June 17, 1992, alleging: (1) a lupse in control of work en safety-related equipnent; and (2) the centrol wiring diagran for or.c j
safety-related valve noter c; erator does nc,t agree with plant as-built conditicns.
We have initiated action t: have the !;crtheast l'tilities staff I
review the at:ve concerns.
Attached a:e the issues as we intend te characterire the-t: the licensee.
W-wall inf orn you cf tl=ir Icv
'w find.ngs.
She 1d ycu have any further questiens, or if I can be of further j
assistance in the e re:ards, plear ca;l ne collect at (215) 32~-
5225
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Sincerely,
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,<~ Edward Wenzinger, Chief Reacter Frojects Branch 4 i
Attach ents: As stated bec:
A: legation Files (3), F:-31-A-14E, 249. 150 J.
Stewart T.
Shedicsky e
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Raynend l
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Felly a
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i ENCLOSURE Issue On June 14, 1991, while attempting to replace the "SealTite" flexible electrical conduit and the position indicator window for No. 1 Steam Generator Main Steam Isolation Bypass
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Valve motor operator (2-MS-65A), it was found that the work had been done previously under AWO M2-89-01828 on March 13, l
1989.
However, the prints had not been updated.
Request Please discuss the validity of the above assertions.
If l
deficiencies in work control or drawing control are found, please inform us of the corrective actions you have taken to Please provide us with an assessment of 3
prevent recurrence.
the significance with regard to safety of any identified deficiencies.
Issue On June 14, 1991, differences between a control wiring diagran and actual plant conditions was found.
The wiring diagram (Drawing 25203-32020) for the No. 1 Steam Generator Main Steam Bypass Valve (2-MS-65A) Motor Operator indicates the presence of an amber light to signify when the unit has tripped on overload.
This light is not installed.
Also, Contact 49, shown on Drawing 25203-32031, sht. 42 does not exist.
i l
Request Please discuss the validity of the above assertions.
If deficiencies are found in plant drawings,'please notify us I
of the corrective actions taken to prevent recurrence.
Please provide us with an assessment of the significance with regard to safety of any identified deficiencies.
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T L '.1931 This letter refers to concerns that you provided to us on June 17, 1991, alleg:ng: (1) a lapse in control of werk on safety-related equipnent; and (2) the control wiring diagran for one sa fety-related valve motor operatcr does not agree with plant as-built conditions.
We have initiated action to have the Northeast Utilities staff review the above concerns.
Attached are the issues as we intend l
to characterize then to the licensee.
We will inforn you of their review findings.
Shculd you have any further q'.estions, or if I can be of further l
assistanr: in these regards, please call re collect at (215) 337-l 5225 Sincerely, ll,
j _ t.'
l Edward Wenzinger, Chief Reactor Projects Branch 4 l
Attachnents: As stated l
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1 Allegation Files (3), RI-91-A 43, 149, 150 i
J.
Stewart l
i T. Shed1csky f
W.
Paynend E.
Kelly l
I laictma:iri in in reta:d via; c'd'ed in 20;erdante viith the frectom ci inictmation I
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I ENCLOSURE r
Issue On June 14, 1991, while attempting to replace the "SealTite" flexible electrical conduit and the position indicator i
window for No. 1 Steam Generator Main Steam Isolation Bypass Valve motor operetor (2-MS-65A), it was found that the work had been done previously under AWo M2-89-01828 on March 13, 1989.
However, the prints had not been updated.
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Request Please discuss the validity of the above assertions.
If deficiencies in work control or drawing control are found, please inform us of the corrective actions you have taken to prevent recurrence.
Please provide us with an assessment of the significance with regard to safety of any identified deficiencies.
t Issue On June 14, 1991, differences between a control wiring diagram and actual plant conditions was found.
The wiring diagram (Drawing 25203-32020) for the No. 1 Steam Generator Main Steam Bypass Valve (2-MS-65A) Motor Operator indicates the presence of an amber light to signify when the unit has tripped on overload.
This light is not installed.
Also, Contact 49, shown on Drawing 25203-32031, sht. 42 dces not exist.
l Request Please discuss the validity of the above assertions.
If deficiencies are found in plant drawings, please notify us of the corrective actions taken to prevent recurrence.
Please provide us with an assessment of the significance with regard to safety of any identified deficiencies.
i 4T r
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'1 NUCLEAR REGULATORY COMMISSION
,- c R E GION I h\\s 7' '
475 AtttNDALE ROAD o,
c KING OF FRUSStA. PENNSYLV ANIA 1 9 36 1415
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This letter refers to concerns that you provided to us on June of Northeast Utilities alleging a failure on the part supervision to follow procedures which ensure environnental 17, 1991, qualification of electrical equipment.
i initiated action to have the Northeast Utilities staff I
I intend to I
We have Attached is the issues as we review the above concern.
We will infern you of their characterize it to the licensee.
review findings.
or if I can be of further Should you have any further questions, at (215) 337-l assistance in these regards, please call ne collect 5225 I
I Si.ncerely,
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ief c.cwarc 1
Reactcr Frojects anch 4 l
l Attachments: As stated l
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A5egationFile, 3
- 3. Stewart l
T. Shedicsky
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Raymond E.
Kelly l
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ENCLOSURE Issue On June 12, 1991, preventive naintenance action was authorized on an environmentally qualified component without the proper quality controls.
A Non-QA work order (two-page AWO) was used to perform work on the motor operator for the "B" Shutdown Cooling Heat Exchanger to "C" HPSI Pump Suction Valve (2-SI-662) in violation of Administrative Control i
Procedure ACP-QA-2.16.
Specifically, the inspection governed by 2701J-7, 2701J-10, and 2701J-11 may require the addition of grease or other consumables.
The addition of grease or other consumables, if not properly controlled as would be done using QA work orders, disqualifies the equipment qualification.
)
Request Please discuss the validity of the above assertion.
Were the EEQ boundaries affected by this preventive maintenance activity?
If deficiencies are found in work control and/or procedures, please notify us of the corrective actions you have taken to prevent recurrence.
Please provide us with an i
assessment of the significance with regard to safety of any
)
identified deficiencies.
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