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{{#Wiki_filter:NRC ronM 195 I2.7B)V.S.NUCLFAR REGULATOR.IMISSION DOC~+T NUMBER+O-QQ,C)NRC DISTRIBUTION roR PART 50 D+r KFT MATERIAL I ILE NUMBER TO: MR K R GOLLER LETTER+ORIGINAL QCOPV ONOTORIZED g VNC LASS IF I E D FEIDM: NIAGARA MOHAWK POWER CORP SYRACUSE, NY G K RHODE INPUT FORM DATE OF DOCUMENT D*T>R>c>lv.D>1 (NUMBER OF COPIES RECEIVED DESCRIPTION LTR RE OUR 5-6-76 LTR"-TRANS'HE FOLLOWRlo.......
{{#Wiki_filter:NRC ronM 195                                                       V.S. NUCLFAR REGULATOR                 .IMISSION DOC~+T NUMBER I2.7B)                                                                                                                    +O- QQ,C)
F.NCLOSURE RESPONSES TO APRIL 6p 1976 NRC QUEST10NS......
I ILE NUMBER NRC DISTRIBUTION roR PART 50                 D+r KFT MATERIAL TO:                                                         FEIDM: NIAGARA MOHAWK POWER CORP                         DATE OF DOCUMENT MR      K R GOLLER                                            SYRACUSE, NY G K RHODE                                         D*T> R>c>lv .D
l IDONOT RZMPVZ>>~sT~>>>.:kX,~~,~iI>e, v 4.<ACKNOWLZDgZD SAX>>TY ASSIGNED AD: BRANCH CHIEF: PROJECT IMAGER: LIC.ASST.: Q<nii FOR AC1 ION/INFORMATION ASSXGNED AD: BRANCH CHXEF: PRO JECT MANAGER: LIC.ASST.: REG FILE ICE OELD GOSSICK 5 STAFF lHPC CASE EEANAUER Hr,l".s T MANAGEMENT P COLLINS 1iOUSTON PL7HHSON FED'/EEI"LTEMES SKOV HOLT LPDR: DSM~+3)~'1'Tr,'NSIO ASLB>>cns II nor,>>1;>ia s>>>>>>INTERNAL D SYSTEI43 S!~w..EEEX NEIMAN SCHHOEDER ENGINEERING KNIGEIT PAWLXCKX REACTOR SAFETY HOSS NOVAK HOSKTOCKY CHECK AT 6 I SADiZMAN HUTBEHG EXTERNAL DISTR I8UTION HEG.V-IE LA VOre CONSULTAIfl'S IST RI8UTION'LANT SYSTEMS TEDESCO BENAROYA IPPOLITO OPERATING HEACTO S STELIQ OPERATING TECFE EISEMGJT SFEAO BAEre SCHWENC ER GHIIlES SITE SAT>>"PY 8e WVXHO ANALY~>XS Dpi'y~yg'r P>;I'.ULNAE>BleOOKlrAVEN 11ATL LAB ULIniXON (OmrL RVXHO TECEl'ALLAR r SITE TECH GAMMILL STEPP EIULMAN SXTE ANALYSXS VOLLMER BUNCFr J.COLLINS KREGER CONTROL NUMBER
                                                                                                                                    >1 (
~~~~~yf NIAGARA MOHAWK POWER CORPORATION NIAGARA~MOHAWK 300 ERIK 60ULKVARD WEST SYRACUSE, H.Y.13202'8 Kw~June 2, l976 Uo$IPJCISAR RICIMT02T, COhN ISS lOII he/Rdl2T Director of Nuclear Reactor Regulation Attn:Mr.Karl R.Goller, Assistant Director Division of Operating Reactors U.S.Nuclear Regulatory Commission Washington, D.C.20555 Re: Nine Mile Point Unit Docket No.50-220 DPR-63
LETTER                      ONOTORIZED                                          INPUT FORM                      NUMBER OF COPIES RECEIVED
  +ORIGINAL QCOPV g VNC LASS IF I E D DESCRIPTION                                                                 F.NCLOSURE LTR RE OUR             5-6-76 LTR"-TRANS'HE FOLLOWRlo.......               RESPONSES           TO   APRIL 6p 1976       NRC QUEST10NS......
l IDONOT RZMPVZ
  >>~sT ~>>>.:kX, ~                   ~,~iI>e,             v 4.<                         ACKNOWLZDgZD Q  <nii SAX>>TY                                     FOR AC1 ION/INFORMATION ASSIGNED AD:                                                                ASSXGNED AD:
BRANCH CHIEF:                                                                BRANCH CHXEF:
PROJECT IMAGER:                                                            PRO JECT MANAGER:
LIC. ASST.:                                                                 LIC. ASST.:
INTERNAL D IST RI8UTION REG         FILE                           SYSTEI43  S!~w..                        SYSTEMS
                                                                                            'LANT RVXHO EEEX NEIMAN                    TEDESCO                                              TECEl'ALLAR ICE                                         SCHHOEDER                      BENAROYA OELD                                                                                                                         r GOSSICK         5   STAFF                 ENGINEERING                    IPPOLITO lHPC                                                                                                                     SITE TECH CASE                                       KNIGEIT                          OPERATING HEACTO S                          GAMMILL EEANAUER                                                                     STELIQ                                      STEPP Hr,l". s                             PAWLXCKX                                                                    EIULMAN OPERATING            TECFE T MANAGEMENT                 REACTOR SAFETY                  EISEMGJT                                    SXTE ANALYSXS HOSS                              SFEAO                                      VOLLMER P COLLINS                                 NOVAK                            BAEre                                      BUNCFr 1iOUSTON                                   HOSKTOCKY                        SCHWENC ER                                  J. COLLINS PL7HHSON                                   CHECK                            GHIIlES                                    KREGER FED'/
EEI"LTEMES                                 AT 6   I                       SITE     SAT>>"PY       8e   WVXHO SKOVHOLT                                  SADiZMAN                        ANALY~>XS HUTBEHG                        Dpi'y~yg 'r P>;   I'.ULNAE>
EXTERNAL DISTR I8UTION                                                          CONTROL NUMBER LPDR: DSM~+3)              ~              HEG. V-IE BleOOKlrAVEN 11ATL LAB ULIniXON (OmrL
    '1'Tr,'NSIO LA    VOre ASLB                                      CONSULTAIfl'S
    >>cns II        nor,>>1;>ia s>>>>>>


==Dear Sir:==
~ ~ ~ ~ ~
Your April 6, l976 letter requested radioactive methyl iodide decontamination test information for the Emer-gency Ventilation System at Nine Mile Point Unit l.The attached responses address the questions contained in'that letter.Si ncerel y, NIAGARA MOMWK"POWER CORPORATION EMERALD K ODE Vice President-ngineering
yf
/sz Attachment 5888
$~y'lg fcmw<g'I~%4 IL hp I C ll RESPONSES TO APRIL 6I l976 NRC QUESTIONS NINE MILE POINT UNIT l DOCKET NO.50-220 DPR-63 R~euest 1 The date the sample of'harcoal was obtained, and the method under which it was obtained (eg, canister and grain thief').a.l0/29/73-Cartridge, Emergency Ventilation System b.l0/27/75-Cartridge, Emergency Ventilation System R~euesL 2 The time interval the charcoal had been installed in the system, and the approximate number of hours the appropriate ESF syst'm had been in operation with the tested charcoal.Res onse 2 The samples were obtained by removal of cartridges installed at the time of the initial bed loading.The cartridges contained charcoal from that loading.Initial plant criticality was achieved 9/5/69.a.Time interval: '0/29/73 sample: Approximately four calendar years l0/27/75 sample: Approximately six calendar years


b.approximate number of hours: Prior to 10/29/73 sample: 10 hrs/year x 5 years*=50 hours Prior to 10/27/75 sample: 50 hrs (prior to 10/73 sample)+10 hrs/yr x 2 yrs (testing)+20 hrs (purge prior to 1974 outage, est.)+41 hrs (purge prior to 1975 outage, actual)131 hours.s*Includes initial plant startup time plus four calendar years.~Re uesC 3 The laboratory that performed the radioactive test.Nuclear Containment Systems, Inc.P.O.Box 19827 Columbus, Ohio 43129 (614)252-1420 R~euese 4 The test agent (ie, elemental iodine or methyl iodide).Res onse 4 a.10/'29/73-Elemental iodine and methyl iodide'b.10/27/75-Methyl iodide
NIAGARA MOHAWK POWER CORPORATION NIAGARA 300
                                  ~      MOHAWK ERIK 60ULKVARD WEST SYRACUSE, H.Y. 13202                '8 June 2, l976 Kw~                                        Uo$ IPJCISAR RICIMT02T, COhN ISS lOII he/ Rdl2T Director of Nuclear Reactor Regulation Attn: Mr. Karl R. Goller, Assistant Director Division of Operating Reactors U. S. Nuclear Regulatory Commission Washington, D. C. 20555 Re:  Nine Mile Point Unit Docket No. 50-220 DPR-63


R~euest 5 The test conditions (eg, temperature, relative humidity, inlet concentration and duration of test).Test results should indicate whether RDT M16-IT procedures were followed.The test conditions of RDT 816-IT, including temperature, relative'humidity, i nlet concentration and test durati on, were followed using the following options: a.10/29/73 sample: 25 Cg ambient pressure, 70~relative humidi ty b.10/27/75 sample: 190 F, one atmosphere, 958 relative humidity~Re uest 6 The removal efficiency obtained, and the experimental error (if known).a.10/29/73 Emergency Ventilation System Cartridge 8 1" depth 99.96'.iodine removed 92.W'ethyl iodide decontaminated 8 2" depth 100.000 iodine removed 99.0C methyl iodide decontaminated 10/27/75 II11 Emergency Ventilation System Cartridge 8 2" depth 97.82K'ethyl iodide decontaminated The experimental error was not known.
==Dear  Sir:==


R~euest 7 Any unusual operation conditions or other information you may consider useful.None.
Your April 6, l976 letter requested radioactive methyl iodide decontamination      test information for the    Emer-gency  Ventilation System  at  Nine Mile Point Unit      l. The attached responses address the questions contained          in'that letter.
A I'I;0~~}}
Si ncerel y, NIAGARA MOMWK "POWER CORPORATION EMERALD K  ODE Vice President          ngineering
/sz 5888 Attachment
 
                    $~y'lg fcmw<g
'I
  ~%4    hp      I IL      C ll
 
RESPONSES  TO  APRIL 6I l976  NRC QUESTIONS NINE MILE POINT UNIT    l DOCKET NO. 50-220 DPR-63 R~euest  1 date the sample of'harcoal was obtained, and the method under The which it  was obtained (eg, canister and grain thief').
: a. l0/29/73 - Cartridge,    Emergency  Ventilation System
: b. l0/27/75  Cartridge,    Emergency  Ventilation System R~euesL 2 The time interval the charcoal had been installed in the system, and the approximate number of hours the appropriate ESF syst'm had been in operation with the tested charcoal.
Res onse 2 The samples  were obtained by removal of cartridges installed at the time of the initial bed loading. The cartridges contained charcoal from that loading. Initial plant criticality was achieved 9/5/69.
: a. Time  interval:
        '0/29/73 sample:    Approximately four calendar years l0/27/75 sample:    Approximately six calendar years
: b. approximate number of hours:
Prior to 10/29/73 sample:
10 hrs/year x  5 years* = 50 hours Prior to 10/27/75 sample:
50 hrs (prior to 10/73 sample) + 10 hrs/yr x 2 yrs (testing) + 20 hrs (purge prior to 1974 outage, est.)
            + 41 hrs (purge prior to 1975 outage, actual) 131 hours.
            *Includes initial plant startup time plus four s
calendar years.
                                ~Re uesC 3 The laboratory that performed the radioactive test.
Nuclear Containment Systems, Inc.
P. O. Box 19827 Columbus, Ohio      43129 (614) 252-1420 R~euese  4 The  test agent (ie, elemental iodine or methyl iodide).
Res onse 4
: a. 10/'29/73  - Elemental iodine and methyl iodide
'b. 10/27/75    Methyl  iodide
 
R~euest 5 The test conditions (eg, temperature, relative humidity, inlet concentration and duration of test). Test results should indicate whether RDT M16-IT procedures were followed.
The test conditions of RDT 816-IT, including temperature, relative
'humidity, i nlet concentration and test durati on, were followed using the following options:
: a. 10/29/73 sample:    25  Cg  ambient pressure, 70~ relative humidi ty
: b. 10/27/75 sample:    190  F, one atmosphere, 958 relative humidity
                              ~Re  uest 6 The removal  efficiency obtained,    and the experimental error (if known)  .
: a. 10/29/73 Emergency Ventilation System Cartridge 8 1" depth    99.96'. iodine removed
: 92. W'ethyl iodide decontaminated 8 2" depth 100.000 iodine removed 99.0C methyl iodide decontaminated 10/27/75 II11 Emergency Ventilation System Cartridge 8 2" depth 97.82K'ethyl iodide decontaminated The  experimental error was not known.
 
R~euest 7 Any unusual operation conditions or other information you may consider useful.
None.
 
A I
'I; 0 ~
        ~}}

Latest revision as of 09:26, 30 October 2019

Letter Responding to 04/06/1976 Letter Requesting Radioactive Methyl Iodide Decontamination Test Information for the Emergency Ventilation System
ML17037B552
Person / Time
Site: Nine Mile Point Constellation icon.png
Issue date: 06/02/1976
From: Rhode G
Niagara Mohawk Power Corp
To: Goller K
Office of Nuclear Reactor Regulation
References
Download: ML17037B552 (12)
v • d • e


Text

NRC ronM 195 V.S. NUCLFAR REGULATOR .IMISSION DOC~+T NUMBER I2.7B) +O- QQ,C)

I ILE NUMBER NRC DISTRIBUTION roR PART 50 D+r KFT MATERIAL TO: FEIDM: NIAGARA MOHAWK POWER CORP DATE OF DOCUMENT MR K R GOLLER SYRACUSE, NY G K RHODE D*T> R>c>lv .D

>1 (

LETTER ONOTORIZED INPUT FORM NUMBER OF COPIES RECEIVED

+ORIGINAL QCOPV g VNC LASS IF I E D DESCRIPTION F.NCLOSURE LTR RE OUR 5-6-76 LTR"-TRANS'HE FOLLOWRlo....... RESPONSES TO APRIL 6p 1976 NRC QUEST10NS......

l IDONOT RZMPVZ

>>~sT ~>>>.:kX, ~ ~,~iI>e, v 4.< ACKNOWLZDgZD Q <nii SAX>>TY FOR AC1 ION/INFORMATION ASSIGNED AD: ASSXGNED AD:

BRANCH CHIEF: BRANCH CHXEF:

PROJECT IMAGER: PRO JECT MANAGER:

LIC. ASST.: LIC. ASST.:

INTERNAL D IST RI8UTION REG FILE SYSTEI43 S!~w.. SYSTEMS

'LANT RVXHO EEEX NEIMAN TEDESCO TECEl'ALLAR ICE SCHHOEDER BENAROYA OELD r GOSSICK 5 STAFF ENGINEERING IPPOLITO lHPC SITE TECH CASE KNIGEIT OPERATING HEACTO S GAMMILL EEANAUER STELIQ STEPP Hr,l". s PAWLXCKX EIULMAN OPERATING TECFE T MANAGEMENT REACTOR SAFETY EISEMGJT SXTE ANALYSXS HOSS SFEAO VOLLMER P COLLINS NOVAK BAEre BUNCFr 1iOUSTON HOSKTOCKY SCHWENC ER J. COLLINS PL7HHSON CHECK GHIIlES KREGER FED'/

EEI"LTEMES AT 6 I SITE SAT>>"PY 8e WVXHO SKOVHOLT SADiZMAN ANALY~>XS HUTBEHG Dpi'y~yg 'r P>; I'.ULNAE>

EXTERNAL DISTR I8UTION CONTROL NUMBER LPDR: DSM~+3) ~ HEG. V-IE BleOOKlrAVEN 11ATL LAB ULIniXON (OmrL

'1'Tr,'NSIO LA VOre ASLB CONSULTAIfl'S

>>cns II nor,>>1;>ia s>>>>>>

~ ~ ~ ~ ~

yf

NIAGARA MOHAWK POWER CORPORATION NIAGARA 300

~ MOHAWK ERIK 60ULKVARD WEST SYRACUSE, H.Y. 13202 '8 June 2, l976 Kw~ Uo$ IPJCISAR RICIMT02T, COhN ISS lOII he/ Rdl2T Director of Nuclear Reactor Regulation Attn: Mr. Karl R. Goller, Assistant Director Division of Operating Reactors U. S. Nuclear Regulatory Commission Washington, D. C. 20555 Re: Nine Mile Point Unit Docket No. 50-220 DPR-63

Dear Sir:

Your April 6, l976 letter requested radioactive methyl iodide decontamination test information for the Emer-gency Ventilation System at Nine Mile Point Unit l. The attached responses address the questions contained in'that letter.

Si ncerel y, NIAGARA MOMWK "POWER CORPORATION EMERALD K ODE Vice President ngineering

/sz 5888 Attachment

$~y'lg fcmw<g

'I

~%4 hp I IL C ll

RESPONSES TO APRIL 6I l976 NRC QUESTIONS NINE MILE POINT UNIT l DOCKET NO. 50-220 DPR-63 R~euest 1 date the sample of'harcoal was obtained, and the method under The which it was obtained (eg, canister and grain thief').

a. l0/29/73 - Cartridge, Emergency Ventilation System
b. l0/27/75 Cartridge, Emergency Ventilation System R~euesL 2 The time interval the charcoal had been installed in the system, and the approximate number of hours the appropriate ESF syst'm had been in operation with the tested charcoal.

Res onse 2 The samples were obtained by removal of cartridges installed at the time of the initial bed loading. The cartridges contained charcoal from that loading. Initial plant criticality was achieved 9/5/69.

a. Time interval:

'0/29/73 sample: Approximately four calendar years l0/27/75 sample: Approximately six calendar years

b. approximate number of hours:

Prior to 10/29/73 sample:

10 hrs/year x 5 years* = 50 hours5.787037e-4 days <br />0.0139 hours <br />8.267196e-5 weeks <br />1.9025e-5 months <br /> Prior to 10/27/75 sample:

50 hrs (prior to 10/73 sample) + 10 hrs/yr x 2 yrs (testing) + 20 hrs (purge prior to 1974 outage, est.)

+ 41 hrs (purge prior to 1975 outage, actual) 131 hours0.00152 days <br />0.0364 hours <br />2.166005e-4 weeks <br />4.98455e-5 months <br />.

  • Includes initial plant startup time plus four s

calendar years.

~Re uesC 3 The laboratory that performed the radioactive test.

Nuclear Containment Systems, Inc.

P. O. Box 19827 Columbus, Ohio 43129 (614) 252-1420 R~euese 4 The test agent (ie, elemental iodine or methyl iodide).

Res onse 4

a. 10/'29/73 - Elemental iodine and methyl iodide

'b. 10/27/75 Methyl iodide

R~euest 5 The test conditions (eg, temperature, relative humidity, inlet concentration and duration of test). Test results should indicate whether RDT M16-IT procedures were followed.

The test conditions of RDT 816-IT, including temperature, relative

'humidity, i nlet concentration and test durati on, were followed using the following options:

a. 10/29/73 sample: 25 Cg ambient pressure, 70~ relative humidi ty
b. 10/27/75 sample: 190 F, one atmosphere, 958 relative humidity

~Re uest 6 The removal efficiency obtained, and the experimental error (if known) .

a. 10/29/73 Emergency Ventilation System Cartridge 8 1" depth 99.96'. iodine removed
92. W'ethyl iodide decontaminated 8 2" depth 100.000 iodine removed 99.0C methyl iodide decontaminated 10/27/75 II11 Emergency Ventilation System Cartridge 8 2" depth 97.82K'ethyl iodide decontaminated The experimental error was not known.

R~euest 7 Any unusual operation conditions or other information you may consider useful.

None.

A I

'I; 0 ~

~

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