A09961, Discusses Review of RI-91-A-0249,0253,& 0254 Re Various Activities at Millstone Unit 2.W/related Matl
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O O fh i NORTHEAST UTILITIES o.n.r. ome.. . s.io.n su..t. 8.mn. Crw,cui
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HARTFORD CONNECTICUT '4141-0270 L L J 7."*CL5',"co, ~,, (203) 665-5000 December 19, 1991
. Docket No. 50-336
.A09961 Re: Employee Concerns 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 Neclear Power Station, Unit No. 2 RI-91-A-0249. 0253. and 0254 We have completed our review of identified issues concerning activities at Millstone Unit No. 2. As requested in your transmittal letter of October 29, 1991, our responses do not contain any personal privacy, proprietary, or safegua*ds information. The material contained in these responses may be released to the public and placed in the NRC Public Document Room at your discretion. The NRC transmittal letter and our responses have received controlled and limited distribution on a "need-to-know" basis during the preparation of these responses. These responses were originally due on 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.
IS$UE 91-0249:
" Electrical hand switches are located on Main Control Board section C03F which are no. labeled in the same manner in which they are referenced in surveil-lance procedure SP-24021, ' Low Temperature /0ver-Pressure Circuitry Functional Test.' The switches (i.e. 2-HS-Ill & 2-HS-121 associated with reactor Th and Tc loop selection and 2-HS-1402 & 2-HS-1404 associated with Power Operated Relief Valve (PORV) high/ low pressure setpoints) are not labeled with alpha-numeric labels."
REQUEST:
"Please provide your review of the above concerns. If the above conditions are valid, please notify us of the corrective actions you have taken to prevent recurrence. Also, provide us with an assessment of the safety signi-
/
9503010236 940809 !
PDR FDIA HUBBARD92-162 PDH
Mr. Charles W. Hehl A09961/Page 2 December 19, 1991 ficance of any identified deficiencies, including any potentially generic concerns."
RESPONSE
The assertion that the switch labels are not in an alpha- numeric format is not valid.
The assertion that the procedure suitch identification did not match the label nomenclature is valid for the period beginning approximately November 1990 and ending September 1991.
Procedure SP24021, " Low Temperature /0verpressure Circuitry Functional Test,"
was upgraded in January of 19G9 to writer's guide standards. This revision reflected switch labels (by ID number) as they were engraved at the time.
During the 1990 refueling outage, portions of the Control Room Design Review (CROR) project were implemented resulting in a label change to these switches.
The procedure's description of the switches, while not consistent with the control room labels following the CRDR work, was adequate for the experienced technician 'and operator (who actually positions the switches) to perform the procedure safely.
On September 13, 1991, an instrument specialist expressed similar concerns to his supervisor during the performance of SP2402I. The supervisor, after discussion with the control room operator and a second instrument specialist, directed the second specialist to process a change to the procedure before continuing. Change 4 to Revision 7 of SP2402I was subsequently approved September 18, 1991. To ensure a complete switch description, both the switch ID number and the description were included. The procedure change vas imple-mented within 4 working days of being requested by the technician and prior to the procedure being completed.
We find no nuclear safety significance or generic concerns associated with this issue. Applicable procedures were followed. We were aware of this issue prior to receiving your letter.
ISSUE 253-02:
" Main Control Board concentrated boric acid flow control recorder (FR-210Y) is being improperly calibrated in that the output of the calibration voltage source is not measured with a digital volt meter, as required by procedure, to properly set the device output voltage and compensate for the circuit load. A second example of this issue concerned calibration af process radiation monitor multipoint recorder RJR9373."
d Mr. Charles W. Hehl A09961/Page 3 December 19, 1991 REQUEST:
"Please provide your review of the above concern. If the above conditions are valid, please notify us of 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 potentially generic concerns."
RESPONSE
The concern is not valid. A review of IC 2428B and IC 2427A, which are the two Instrumentation and Controls (I&C) procedures used to calibrate recorders FR-210Y and RJR-9373, did not reveal any provision to use a digital voltmeter in calibrating the flow recorder as alleged.
We were not aware of this issue prior to the receipt of the NRC letter. This is not a safety-related instrument loop; there is no nuclear safety signifi-cance to this issue.
ISSUE 91-254:
" Pressurizer pressure instrument calibration procedure, IC-2418C, does not direct the individual performing the calibration to isolate pressure trans-mitters PT-100X and PT100Y and then restore them to service. The lack of isolation valve control from within the procedure could possibly allow the instruments to be left isolated following the completion of the procedure.
Such an event occurred on November 2, 1990 with PT-100Y as noted during the completion of work order M2-90-13275."
REQUEST:
"Please provide your review of the above concerns. If the above conditions are valid, please notify us of the corrective actions you have taken to prevent recurrence. Also, provide us with an assessment of the safety signi-ficance of any identified deficiencies, including any potentially generic concerns."
RESPONSE
This concern is valid as stated. We were informed of this concern via memo-randum on November 3,1991, and a procedure change was processed to add the isolation valves to the I&C valve line up procedure. This action was taken to prevent recurrence of the referenced event. Long term plans include upgrading the calibration procedure to contain the same level of detail as the safety-related calibration instrument procedure.
There was no safety significance to this issue as it affected only control grade instrumentation.
Q.
9 Mr. Charles W. Hehl A09961/Page 4 December 19, 1991 After our review and evaluation of these issues, we find that these issues did not present any indication of a compromise of nuclear safety. We appreciate the opportunity to respond and explain the basis of' our actions. Please contact my staff if there are further questions on any of these matters.
Very truly yours, '
NORTHEAST NUCLEAR ENERGY COMPANY J. F. Op4ka
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Executive Vice President 4
cc: W. J. Raymond, Senior Resident Inspector, Millstone Unit Nos.1, 2, and 3 E. C. Wenzinger, Chief, Project Branch No.
4, Division of Reactor Projects E. M. Kelly, Chief, Reactor Projects Section 4A i J. T. Shedlosky, U.S. Nuclear Regulatory Commission, Millstone 1
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RECORD OF ALLEGATION PANEL DECISIONS 7
SITE: M *' -(' *e T PANEL ATTENDEES:
ALLEGATION NO.: k -9 " O 2. 9 Dr+ pt%S Chairman -
DATE: E#C~I (Panel No. h2 3 4 5) Branch Chief - (A) e u 2the te PRIORITY: High Hedium h Section Chief (AOC) -
SAFETY SIGNIFICANCE: Yes Unkn Sr. Alleaation Coord ISAC) e m f.h tr-CONCURRENCE TO CLOSEOUT DD h SC OI Peoresentative - CW b kte, hh C.
Yes g (Otherib ( 3 og CONFIDENTIALITY GRANTED:
(See Allegation Receipt Report)
IS THERE A HARASSMENT / DISCRIMINATION ISSUE: Yes IF YES, I) has the individual been informed of the DOL Yes No process and the need to file a complaint within 30Yes days No
- 2) has the individual filed a complaint with DOL No
- 3) has a letter been sent to the complainant seeking Yes any safety concerns IS A CHILLING EFFECT LETTER WARRANTED:
IF YES, 3AS IT BEEN SENT Yes Yes h
No Yes No HAS THE LICENSEE RESPONDED TO THE CHILLING EFFECT LETTER:
RESP ECD ACTION:
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t RECORD OF ALLEGATION PANEL DECISIONS SITE: Ma fMe ui PANEL ATTENDEES:
ALLEGATION NO.: $7-9 f 4- o273 /V/4 Chairman - Oh+q Mi DATE: 16 0C,7 (Panel No, lh345) Branch Chief -
PRIORITY: High Low Section Chief fAOC) - e.I SAFETY SIGNIFICANCE: Yes @ Unkn Sr. Allecation Coord (SAC) k men CONCURRENCE TO CLOSEOUT DD h SC QI Reoresentative -
CONFIDENTIALITY GRANTED: Yes JOther) bete byh Net, t r~
(See Allegation Receipt Report)
IS THERE A HARASSMENT /DISCRIHINATION IF YES, ISSUE: Yes h
- 1) has the individual been informed of the DOL process and the need to file a complaint within 30 days Yes !!c
- 2) has the individual filed a complaint with DOL Yes No
- 3) has a letter been sent to the complainant seeking Yes tio any safety concerns ,
IS A CHILLING EFFECT LETTER WARRANTED: Yes No IF YES, HAS IT BEEN SENT Yes No HAS THE LICENSEE RESPONDED TO THE CHILLING EFFECT LETTER: Yes No ACTION: RESP ECD
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PRIORITY: High h Low Section Chief fAOC) -
SAFETY SIGNIFICANCE: Ves No h Sr. Allecation Coord fSAC) b. v&vt4d 'tr-1 CONCURRENCE TO CLOSEOUT DD SC OI Reoresentative - b.Ek[R CONFIDENTIALITY GRANTED: Yes @ (Other) kO4_ b het
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IS THERE A HARASSMENT /DISCRIHINATION ISSUE: No IF YES,
- 1) has the individual been informed of the DOL 2) process and the need to file a complaint within 30 days 1, _s the individual filed a complain.; with DOL Yes @ h No
- 3) has a letter been sent to the complainant seexing Yes No any safety concerns IS A CHILLING EFFECT LETTER WARRANTED:
IF YES, HAS IT BEEN SENT Yes hN Yes No HAS THE LICENSEE RESPONDED TO THE CHILLING EFFECT LETTER: Yes No ACTION: RESP ECD 1)
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RECORD OF ALLEGATION PANEL DECISIONS SITE: $A .* 5 f- PANEL ATTENDEES:
ALLEGATION No.: D-9I-N'024h Chairman - (A)fcL euh5 s =
DATE: 20C,79d (Panel No. h2 3 4 5) Branch Chief - lifemhal t/~
PRIORITY: High Low Section chief !AOC) -
SAFETY SIGNIFICANCE: 2es
@ Unkn Sr. Allecation Coord fSAC) m e'Ih CONCURRENCE TO CLOSEOUT DD SC OI Reeresentative - b 6 /
CONFIDENTIALITY GRANTED:
(See Allegation Receipt Report)
Yes h f_Otheri Faoe, c,...e. & 4 Me#=( e l j
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 DCL Yes No
- 3) has a letter been sent to the complainant seeking Yes No any safety concerns IS A CHILLING EFFECT LETTER WARRANTED: Yes No IF YES, HAS IT BEEN SENT Yes No i
HAS THE LICENSEE RESPONDED TO THE CHILLING EFFECT LETTER: Yes No ACTION: RESP ECD
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1 ENCLOSURE I
- l Issue 91-249:
Electrical hand switches are located on Main Control Board section CO3F which are not labeled in the same manner in which they are referenced in surveillance procedure SP-24021, %w Temperature /Over-Pressure Circuitry Functional Test." The switches (i.e. 2-HS-111 & 2-HS-121 associated with reactor Th and Tc loop selection and 2-HS-1402 & 2-HS-1404 associated with Power Operated Relief Valve (PORV) high/ low pressure setpoints) are not labeled with alpha-numeric labels.
Issue 91-253-02: l Main Control Board concentrated boric acid flow control recorder (FR-210Y) is being improperly calibrated in that the output of the calibration voltage source is not measured with a digital volt meter, as required by procedure, to properly set the device output voltage and compensate for the circuit load. A second example of this issue concerned calibration of process radiation monitor multipoint recorder RIR-9373.
Issue 91-254:
Pressurizer pressure instrument calibration procedure, IC-2418C, does not direct the individual performing the calibration to isolate pressure transmirxrs PT-100X and PT-100Y and then restore them to service. The lack of isolation valve control from within the procedure could possibly allow the instruments to be left isolated following the completion of the procedure. Such an event occurred on November 2,1990 with PT-100Y as noted curing the completion of work order M2-90-13275.
Request:
Please provide your review of tne above concerns. If the above conditions are valid, please notify us of 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 potentially generic concerns.
LIMI RIBUT - NOT F UBLIC t
. i ION - NO R LIC DISCL LIJWITED'D@
I l
ENCLOSURE i
- l Issue 91-249: !
I Electrical hand switches are located on Main Control Board section CO3F which are not labeled in the same manner in which they are referenced in surveillance procedure SP-24021, " Low Temperature /Over-Pressure Circuitry Functional Test." The switches (i.e. 2-HS-111 & 2-HS-121 associated with reactor Th and Tc loop selection and 2-HS-1402 & 2-HS-1404 associated with Power Operated Relief Valve (PORV) high/ low pressure setpoints) are not labeled with alpha-numaic labels.
Issue 91-253-02:
Main Control Board concentrated boric acid flow control recorder (FR-210Y) is being improperly calibrated in that the output of the calibration voltage source is not measured with a digital volt meter, as required by procedure, to properly set the device output voltage and compensate for the circuit load. A second example of this issue concerned calibration of process radiation monitor multipoint recorder RJR-9373.
Issue 91-254:
Pressurizer pressure instrument calibration procedure, IC-2418C, does not direct the individual performing the calibration to isolate pressure transmitters FT-100X and PT-100Y and then restore them to service. 'Ihe lack of isolation valve control from within the procedure could possibly allow the instruments to be left isolated following the completion of the procedure. Such an event occurred on November 2,1990 with PT-100Y as noted during the completion of work order M2-90-13275.
Request:
Please provide your review of the above concerns. If the above conditions are valid, please notify us of 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 potentially generic concerns.
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1 AIMATI(M REGIPf RDORT l Date/ Time I Received: Nove ber 7, 1991 0830 Allegation No. RI-91-A-253-2 l A9W En9erecs Name:
, Address Phone: City /St./ Zip:
Confidentiality:
Was it requested? No Alleger's Employer: NNE00 Foaition/
Title:
Instrumentation and Control Department Technician l Facility: Millstone Unit 2 Locket No.: 50-336 i Allegation Summary: A noe example of innaequate recorder calibration was ,'
provided.
Number of Concerns: 1 T
Employee receiving allegation: J. T. Shediosky Type of regulated activity: Reactor' f
Functional Areats2: Operations :
Detailed Description of Allegation: An additional examqple of a previously presented issue was pewidad. It concerna the practice of recorder calibration without using a calibrated voltmeter to monitor the test supply voltase. h !
instrument involved. UR-4501, is associated with monitoring the turbine ;
perfor--; it records turbine speed, eccentricity, and control valve position.
h alleger noted that for calibrations perfossed on September 15,1990, March 5, 1989 and March 1,1988 a calibrated voltmeter was not used to back-up the desired output of the voltage source used for the rooorder calibration. The alleger's evidence in the missing Q& serial number for a voltanter when examining the recorder instrument record card. He also alleges that 1&C Department supervision has failed to adequately rwise +h- record cards prior to signing the revise block. -
j A calibration of this recorder perforwed on March 9,1991 used both devices.
Attached are "Instriment Calibration Data Sheets" for this recorder and also e Departmental " Technical Bulletin" which is the basis for the allegation. ;
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Reverse Test OA#: Date: OA#: Date: Equipment OA#: Date: OA#: Date: OA#: Date: QA#: Date: - Crt Date: Technicians: Supervisor: Ar proved: - (l&C Supervisor) Date: [/ l&C Dept Form 3.02-I A (Rev 0)
/[ (Formerly Form 21003)
H I 7 RECORD OF ALLEGATION PANEL DECISIONS SITE: . 5 % 2 PANEL ATTENDEEe: ALLEGATION NO.: N- "N ~O Z N Chairman - (31! DATE: M (Panel No. 1234 5) Branch Chief - 3M PRIORITY: High Low Section Chief fAOC) - SW L 01 SAFETY SIGNIFICANCE: tes No Unkn Sr. Allecation Coord (SAC) . v meAlee. CONCURRENCE TO CLOSEOUT DD BC SC OI Reoresentative - CONFIDENTIALITY GRANTED: (See Allegation Receipt Report) Yes No (Otheri er (D '
$ tc 1L [N '
IS THERE A HARASSMENT /DISCRIHINATION ISSUE: Yes No IF YES, I) 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: Yes No IF YES, HAS IT BEEN SENT Yes No HAS THE LICENSEE RESPONDED TO THE CHILLING EFFECT LETTER: Yes No ACTION: RESP ECD
- 1) h GDei- o'</ (A FW 5 D 58 e v~ e, Nf &AA2.
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- 3) ' kthe c- P_ t'R. e 'A 0 f3 - F E-Nw vdes ad Ca nd... .<
4) 5) NOTES: l I l r l
.( LIC D 'tOStHE - LI TED DI I OT FOR ENCLOSURE Issue 91-249: Electrical hand switches are located on Main Control Board section CO3F which ar not labeled in the same manner in which they are referenced in surveillance procedure , SP-24021, "Irw Temperature /Over-Pressure Circuitry Functional Test." The switches (i.e. 2-HS-111 & 2-HS-121 associated with reactor Th and Tc loop selection and 2-HS-1402 & 2-HS-1404 associated with Power Operated Relief Valve (PORV) high/ low pressure setpoints) are not labeled with alpha-numeric labels. Issue 91-253-02: Main Control Board concentrated boric acid flow control recorder (FR-210Y) is being l improperly calibrated in that the output of the calibration voltage source is not measured with a digital volt meter, as required by procedure, to properly set the device output voltage and compensate for the circuit load. A second example of this issue concerned calibration of process radiation monitor multipoint recorder RJR-9373. Issue 91-254: Pressurizer pressure instrument calibration procedure, IC-2418C, does not direct the individual performing the calibration to isolate pressure transmitters Irr-100X and PT-100Y and then restore them to service. The lack of isolation valve control from within the procedure could possibly allow the instruments to be left isolated following the completion of the procedure. Such an event occurred on November 2,1990 with PT-100Y as noted during the completion of work order M2-90-13275. Request: Please provide your review of the above concerns. If the above conditions are valid, please notify us of 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 potentially generic concerns. t
- - - - - _ _ - _ _ - - - - - - - - - - - - - - - - - - - _ _ - - , - - - - +
J/02r4 , NON-RADIOLOGICAL HAZARDS DATA SHEET PART I - ISSUE , NRC Licensee: Northeast Nuclear Energy Company Millstone Nuclear Power Station Waterford, CT Description of Issue: The Millstone Unit 2 "A" & "B" Emergency Diesel Generators are separated by a double set of doors. One is a water tight door the second is a security door; both are back to back on either side of a wall. The manipulation o,f the water tight door is ackward and danger-ous when the ventilation system creates a differential pressure between the two diesel rooms. How information was obtained: Employee allegation. Other persons informed: NRC Region 1 OSHA Liaison Off.icer, DRSS NRC Region I Allegation Panel Signature - NRC Inspector Date PART II - NRC Licensee Acknowledgement ' An NRC Inspector has identified the above-stated non-radiological issue. b Signature - NRC Licensee Representative Title Date NRC Licensee Comments: : Part III - Followup Description of Corrective Actions: Signature - NRC Inspector Date
/
CC: Regional Office NMSS:IMNS NRR:ILPB 1007 A-1 Issue Date: 11/30/88
/ /Y RECORD OF ALLEGATION PANEL DECISIONS SITE:
- 5 6 PANEL ATTENDEES:
PLLEGATION No.: b-N'O"O2 b chairman - [Mt'h tMS DATE: S OM (PanelNo.@2345) Branch Chief - PRIORITY: High Low Section Chief (AOC) - el (SAC,Fdmasb SAFETY SIGNIFICANCE: Yes h Unkn Sr. A11ecation Coord CONCURRENCE TO CLOSEOUT: DD h SC OI Reoresentative - (o MW CONFIDENTIALITY GRANTED: Yes (See Allegation Receipt Report) h (Other) gd[4 O h hQc-gQQq 4 IS THERE A HARASSMENT / DISCRIMINATION ISSUE: Yes , 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) has the individual filed a complaint with DOL Yes No
- 3) has a letter been sent to the complainant seeking any safety concerns IS A CHILLING EFFECT LETTER WARRANTED: Yes Yes hN To IF YES, HAS IT BEEN SENT Yes No HAS THE LICENSEE RESPONDED TO THE CHILLING EFFECT LETTER:
ACTION: RESP ECD
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- 2) Irnou t#- Qu) w/2 2,u 2te y &ok l\C h4. kw er OSLIN DM N IT 3) 4)
5) NOTES:
1 RECORD OF ALLEGATION PANEL DECISIONS SITE: bs' 5Wf PANEL ATTENDEES: ALLEGATION NO.: N' 01 Chairman - beso t MS DATE: 10C79 (Panel No.h 3 4 5) Branch Chief - lA) e t 'Itf PRIORITY: High Low Section Chief fAOC) - (- SAFETY SIGNIFICANCE: Yes h Unkn Sr. Alleaation Coord iSAC) meti CONCURRENCE TO CLOSEOUT: DD @ SC OI Reoresentative - CONFIDENTIALITY GRANTED: Yes (See Allegation Receipt Report)
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' 3loLQ IS THERE A HARA3SMENT/DISCRIHINATION IF YES, ISSUE: Yes @
- 1) 'has the individual been informed of tie DOL Yes process and the need to file a complaint within 30 days No has the individual filed a complaint with DOL Yes No 2)
- 3) has a letter been sent to the complainant seeking Yes No any safety concerns IS A CHILLING EFFECT LETTER WARRANTED: Yes Yes No IF YES, HAS IT BEEN SENT HAS THE LICENSEE RESPONDED TO THE CHILLING EFFECT LETTER: Yes No ACTION: RESP ECU
- 1) h mc o R beP focal 2) 3)
- 4) . .c 5)
NOTES:
> / 7/
E{pa%ke UNITED STATES NUCLEAR REGULATORY COMMISSION
, REGK)N I
/ 475 ALLENDALE ROAD p,g .....g KING OF PRUSSIA. PENNSYLVANIA 19406 1415 OCT 2 91991 Docket Number: 50-336 File Numbers: RI-91-A-249,253 & 254 Northeast Nuclear Energy ' Company NITN: Mr. John F. Opeka Executive Vice President - Nuclear P.O. Box 270 i Hartford, Connecticut 06141-0270
Dear Mr. Opeka:
The U.S. Nuclear Regulatory Commission recently received information concerning activities at the Millstone Nuclear Power Facility, Unit 2. He details are enclosed 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 t public and placed in the NRC Public Document Room. If necessary, such information s contained in a separate attachment which will be withheld from public disclosure. The affida required by 10 CFR 2.790(b) must accompany your response if proprietary information is included. Please refer to file number RI-91-A-249,250, 253 & 254 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 J. 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. The response requested by this letter and the accompanying enclosure are not subject to the clearance procedures of the Office of Management and Budget as required by the Paperw Reduction Act of 1980, PL %-511. Your cooperation in this matter is appreciated. We will gladly discuss any questions you have concerning this information. Sincerely,
}
Chasles W. H tor Division of Reactor Projects
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j [ .. ., . k. i 007 2 9 1991 o Encl < rare: 10 CFR 2.790(a) Information Issues and Requests cc w/o encl: Public Document Room (PDR) local Public Document Jtoom (LPDR) State of Connecticut bec w/ encl: Allegation File, RI-91-A-0249, 0250, 0253, & 0254 E. Conner files E. Kelly (Section Chief) W. Raymond T. Shediosky Contractor's office files (REAGAN) RI:DRP e
+
I-concunences: n RI:DRP RI RJ elly Wenzin ,er Conner I i /'I go_JR) L V [0 (.
- _ _ ____-______-___.___m _____________________.______________._..__..____________.___.______.____.:.__._______J}}