A09962, Discusses Review of RI-91-A-0260 Re Various Activities at Millstone Unit 2.W/related Matl

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Discusses Review of RI-91-A-0260 Re Various Activities at Millstone Unit 2.W/related Matl
ML20080K776
Person / Time
Site: Millstone Dominion icon.png
Issue date: 12/19/1991
From: Opeka J
NORTHEAST NUCLEAR ENERGY CO., NORTHEAST UTILITIES
To: Hehl C
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
Shared Package
ML20079Q807 List:
References
FOIA-92-162 A09962, A9962, NUDOCS 9503010278
Download: ML20080K776 (10)


Text

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'O' ES General Offices

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H ARTFORD. CONNECTICUT 061414>270 (203) 665-5000 December 19, 1991 Docket No. 50-336 A09962 Re: EmployeeConcerns/

Mr. Charles W. Hehl, Director Division of Reactor Projects U.S.. Nuclear Regulatory Commission Region I 475 Allendale Road King of Prussia, PA 19406

Dear Mr. Hehl:

Millstone Nuclear Power Station, Unit No. 2 RI-91-A-0260 We have completed our review of an identified issue concerning activities at Millstone Unit No. 2. As requested in your transmittal letter of October 29, 1991, our response does not contain any personal privacy, proprietary, or safeguards information. The material contained in this response may be released to the public and placed in the NRC Public Document Room at your discretion. The NRC transmittal letter and our response have received con-trolled and limited distribution on a "need to know" basis during the prepara-tion of this response. This response was originally due to the NRC Staff by December 4, 1991. An additional two weeks in which to respond were granted in a telephone conversation with the Region I Staff on December 2, 1991.

ISSUE:

"there has been a recurring Unit 2 problem, at Millstone Unit 2 [ sic), with a 10 volt reference power supply for the channel 'C' Reactor Protection System (RPS). The issue does not appear to have been properly addressed by I&C

[ Instrumentation and Controls] Department management. The surveillance calibration specification for this power supply is 10 volt +/- 0.003 volt d.c.

It is used as an on line reference for the RPS digital voltmeter and has frequently been found to have a low out of specification output voltage.

Additionally, the power supply in question is said to be modified by drilling holes to allow internal adjustments to be made. This was accomplished without appropriate design change controls."

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9503o1o278 940eo, PDR FOIA PDR N

__ _HUBBARD92-162 j

3 Mr. Charles W. Hehl A09962/Page 2 December 19, 1991 1

I REQUEST:

"Please discuss the validity of these assertions. If they are valid, please notify us of the safety significance of the error, trending of data on drift, whether or not the power supply had been modified and how that was controlled, and the corrective actions you have taken to prevent recurrence. Also, l provide us with an assessment of the safety significance of any idemtified l deficiencies, including any generic considerations." l

RESPONSE

l l

The assertion is partially valid. The power supply at issue is located in l the RPS cabinet in Core Protection Calculator No. 2. It is a modular design l consisting of a circuit board in a plastic case. The plastic case performs no  !

function other than to provide support for the circuit board. The hole which l was drilled in this plastic case allows access to the only adjustment on the -

l power supply, without requiring disassembly of the core protection calculator.

Since the hole in the plastic case could affect the strength of its support function, an inspection of all power supply modules was completed. It was determined that the size of the hole, which is limited to the width of the blade of a small screwdriver, is not detrimental to the strength of the case. A nonconformance report, NCR (291-272), has been initiated to document the satisfactory evaluation of the modification.

The vendor stated tolerance on the +/-10-volt power supply is +/-0.0025 volts.

Since the RPS calibration instrument panel (RPSCIP) digital voltmeter can only display three significant digits, the useful tolerance value was established as +/-0.003 volts. The power supply at issue is checked daily using procedure OP 2601D to determine that the voltage output is within tolerance for the range from -10 volts to +10 volts as read by the RPS digital voltmeter. The procedure requires that any out-of-tolerance readings are to be reported to -

I&C by means of a Priority No. 1 Trouble Report for calibration of the 3 voltmeter. l This power supply voltage is monitored by the RPSCIP digital voltmeter and is 3 not used as a reference during calibrations. The voltmeter is calibrated '

using a calibrated voltage standard and Procedure IC 2417K.

I&C Procedure IC 2417K is also used to calibrate the RPS digital voltmeter quarterly. This calibration does not use the +/-10-volt power supply as a reference. Since the power supply is monitored daily by procedure and adjusted as needed, this concern is considered to be of no safety signifi-cance.

i Mr. Charles W. Hehl A09962/Page 3 December 19, 1991 After our review and evaluation of this issue, we find that this issue did not present any indication of a compromise of nuclear safety. We were not aware of this issue prior to the receipt of the NRC letter. We appreciate the opportunity to respond a'nd explain the basis of our actions. Please contact my staff if there are further questions on any of these matters.

l Very truly yours, NORTHEAST NUCLEAR ENERGY COMPANY A . F.Qi J. F. Opeka O Executive Vice President cc: W. J. Raymond, Senior Resident Inspector, Millstone Unit Nos.1, 2, and 3 E. C. Wenzinger, Chief Projects Branch No. 4, Division of Reactor ,

Projects ,

E. M. Kelly, Chief, Reactor Projects Section 4A J. T. Shedlosky, U.S. Nuclear Regulatory Commission, Millstone

0 64 '91 07:55 NRC MILLSTONE OFFICE P02 /83

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ALLEGATION RECEIPT REPORT Ost+. Tis +

Re,eited: October 1, 1991 1135 Allegation lic. 2".I.-91-4-07.,40 Nese: Address:

!'htne : City /St./ Zip:

Conf.d Wss it requested? Nc Alleger's Empicyer: NUECO t Pcsition/

Title:

instrumentati:n and Ccnte:;

Department Technicisn

?scility: Millstone Unit 2 Lseket No.: 50-336 -

Allegn.cn Sum =ary: Reactor Protection Channel "C" 10 volt reference power supply found out of specification - low. This is a recurring problem.

Additionally, a modification, to allow internal adjustment of the power supply.

  • had been made without appropriate design change controls.

Number :i C:.n= erns: 2 i,

Emp;;yee receiving allegaticn: J. T. 5hedios'ref Tyre .i r+ge.lu ed activit/: P.ehetcr Functicna'. Area;s): Operations a niled :escripti:r. :f Allegation: Tlere has been a recurring problem with a 10 volt reference power supply for the channel "C" Reactor Protection System I (RPS). The issue has not been properly addressed by I&C Department management.

  • i The surveillance calibration specification for this power supply is 10 volt +/-

0.003 volt d.c. It, is used as an on line reference for the RPS digital voltmeter and has frequer,tly been foucM to have a low out of specification output voltage.

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h RECORD OF ALLEGATION PANEL DECISIONS SITE: k5 4 PANEL ATTENDEES:

ALLEGATION NO.: b4 "Ob Chairman - Wahrh 5 DATE: 40C7d (PanelNo.@2345) Dranch Chief -

PRIORITY: High Low Section Chief fAOC) - r_ N SAFETY SIGNIFICANCE: Y,e s No Sr. A11ecation Coord fSAC)[u rw 6t r CONCURRENCE TO CLOSEOUT DD SC OI Representative -

CONFIDENTIALITY GRANTED: Yes N fOther) ft"$4h !A bW cfk (See Allegation Receipt Report) 3/c}f3/c,h) e IS THERE A HARASSHENT/DISCRIHINATION IF YES, ISSUE: Yes @

1) has the individual been informed of the DOL process and the need to file a complaint within 30 days Yes No
2) has the individual filed a complaint with DOL Yes No
3) has a letter been sent to the complainant seeking Yes No any safety concerns IS A CHILLING EFFECT LETTER WARRANTED:

IF YES, HAS IT BEEN SENT Yes Yes hNo HAS THE LICENSEE RESPONDED TO THE CHILLING EFFECT LETTER: Yes No ACTION: RESP ECD

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NOTES:

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B FO PUB DISC W '

t ENCLOSURE Issue 91-260: ,

There has been a recurring Unit 2 problem, at Millstone Unit 2, with a 10 volt reference power supply for the channel "C" Reactor Protection System (RPS). The issue does not appear to have been properly addressed by I&C Department management. The surveillance calibration specification for this power supply is 10 volt +/- 0.003 volt d.c. It is used as an on line reference for the RPS digital voltmeter and has frequently been found to have a low >

out of specification output voltage.

Additionally, the power supply in question is said to be modified by drilling holes to allow internal adjustments to be made. This was accomplished without appropriate design change -

controls. ,

Request: ,

Please discuss the validity of these assertions. If they are valid, please notify us of the  :

safety significance of the error, trending of data on drift, whether or not the power supply .

had been modified and how that was controlled, and the corrective actions you have taken to prevent recurrence. Also, provide us with an assessment of the safety significance of any identified deficiencies, including any generic considerations.

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.AtMITED@fS RIBUTIO FOR P LIC DIS

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fof RECORD OF ALLEGATION PANEL DECISIONS SITE: , 5 Ch 4 2 PANEL ATTENDEES:

ALLEGATION NO. SM ~ ~Ol Chairman - (Akh h 9 DATE: SOCTO (Panel No. 1 2 3 4 5) Branch Chief -

PRIORITY: High Medium Section Chief (AOC) - r f SAFETY SIGNIFICANCE: ,Yes Unkn Sr. A11ecation Coord (SAC) Ful-iti,_

CONCURRENCE TO CLOSEOUT: DD @ SC OI Reoresentative -

CONFIDENTIALITY GRANTED: Yes (Other) r1 M ah b 44 (on4k (See Allegation Receipt Report) g (7) {MM-IS THERE A HARASSMENT / DISCRIMINATION ISSUE: Yes No IF YES,

1) has the individual been informed of the DOL process and the need to file a complaint within 30 days Yes No
2) has the individual filed a complaint with DOL Yes No
3) has a letter been sent to the complainant seeking Yes No any safety concerns IS A CHILLING EFFECT LETTER WARRANTED:

IF YES, RAS IT BEEN SENT Yes Yes O

No HAS THE LICENSEE RESPONDED TO THE CHILLING EFFECT LETTER: Yes No ACTION: RESP ECD

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1 NOTES:

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RECORD OF ALLEGATION PANEL DECISIONS SITE: i 6 PANEL' ATTENDEES:

ALLEGATION NO.: k7-9I ~O2d chairman - b DAT*: Z$ M (Panel No. 1 2 3 4 5) Branch Chief -

PRIORITY: High h Low Section Chief (AOC) - 4 SAFETY SIGNIFICANCE: Pos @ Unkn Sr. Allocation Coord iSAC)

CONCURRENCE TO CLOSEOUT: DD g SC OI Reoresentative -

CONFIDENTIALITY GRANTED: Yes @ (Other) DAN:  !

(See Allegation Receipt Report) V IS THERE A HARASSMENT / DISCRIMINATION IF YES, ISSUE: Yes @

1) has the individual been informed of the DOL process and the need to file a complaint within 30 days Yes No
2) has the individual filed a complaint with DOL Yes No
3) has a letter been sent to the complainant seeking Yes No any safety concerns IS A CHILLING EFFECT LETTER WARRANTED:

IF YES, HAS IT BEEN SENT Yes Yes

@ No HAS THE LICENSEE RESPONDED TO THE CHILLING EFFECT LETTER: Yes No ACTION: RESP ECD

1) C]ow Mf zomo9d 2) 3)

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b li W Mf RECORD OF ALLEGATION PANEL DECISIONS SITE: /! C PANEL ATTENDEES:

k7-9 ~ ~O2d Chairman - N(M4[6d ALLEGATION NO.

(Panel No. 1 2 3 4 5) Branch Chief -

DATE: ZM

- [o f. y PRIORITY: High h Low Section chief fAOC)

Sr. Alleaation Coord iSAC)bw r w eX b SAFETY SIGNIFICANCE: Yes @ Unkn CONCURRENCE TO CLOSE0UT DD g SC OI Reoresentative -

CONFIDENTIALITY GRANTED: Yes @ fOther) dun b m/ "

7 (See Allegation Receipt Report)

IS THERE A HARASSMENT / DISCRIMINATION ISSUE: Yes @ l IF YES,

1) has the individual been informed of the DOL Yes No process and the need to file a complaint within 30 days Yes No
2) hac the individual filed a complaint with DOL Yes No J
3) has a letter been sent to the complainant seeking -

any safety concerns IS A CHILLING EFFECT LETTER WARRANTED:

Yes Yes

@ No IF YES, RAS IT BEEN SENT Yes No l HAS THE LICENSEE RESPONDED TO THE CHILLING EFFECT LETTER:

RESP ECD ACTION: \

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4) 5)

NOTES:

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[ '*g UNITED STATES b- [

M j NUCt. EAR REQULATORY COMMISSION REQlON 1 475 ALLENDALE MOAD

          • loNG OF PRUSSIA. PENNSYLVANIA 1s406 Docket Number: 50-336 0CT 2 s a File Number: RI-91-A-0262 Northeast Nuclear EnergyCompany ATTN: 'Mr. John F. Opeka Executive Vice President - Nuclear P.O. Box 270 Hartford, Connecticut 06141-0270

Dear Mr. Opeka:

The U.S. Nuclear Regulatory Commission recently received information concerning activities at Milistone Unit 2. Enclosed are the details for your review and followup.

We request that the results of your review and disposition of these matters be submitted to Region I within 30 days of the date of receipt of this letter. We request that your response contain no personal privacy, proprietary, or safeguards information so it can be released to the public and placed in the NRC Public Document Room. If necessary, such information shall be contained in a separate attachment which will be withheld from public disclosure. The affidavit required by 10 CFR 2.790(b) must accompany your response if proprietary information is included. Please refer to file number RI-91-A-0262 when providing your response.

The enclosure to this letter should be controlled and distribution limited to personnel with a "need to know" until your investigation of the concern has been completed and reviewed by NRC Region I. The enclosure to this letter is considered Exempt from Public Disclosure in accordance with Title 10, Code of Federal Regulations, Part 2.790(a). However, a copy of this letter excluding the enclosure will be placed in the NRC Public Document room.

'Ihe response requested by this letter and the amompanying enclosure are not subject to the clearance procedures of the Office of Manage rent and Budget as required by the Paperwork Reduction Act of 1980, PL 96-511.

Your cooperation in this matter is appreciated. We will gladly discuss any questions you have concerning this information.

Sincerely,

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' /w H C es W. Ibbl, Directbr

. Division of Reactor Projects w e

e Northeast Nuclear Energy Company 2 OCT 2 91991

Enclosure:

10 CFR 2.790(a) Information Issues and Requests cc w/o encl:

Public Document Room (PDR) local Public Document Room (LPDR)

State of Connecticut bec wiencl:

Allegation File, RI-91-A-0262 E. Conner files E. Kelly (Section Chief)

W. Raymond T. Shediosky Contractor's office files (REAGAN)

RI:DRP .

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concurrences:

RI:DRP RI:DRP R6QRP 7

hi Wenzinger -

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