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{{#Wiki_filter:NRC FORM 195                                                   U.S. NUCLEAR REGULATORV C     ISSION DOCKET NUMBER I2-70)                                                                                                    50-244 F <LE NUMBE R NRC DISl RIBUTION FoR PART 50 DOCKET MATERIAL a
{{#Wiki_filter:NRC FORM 195 I2-70)
FROM:                                       DATE OF DOCUMENT Rochester Gas &     Electric   Corp.             1/19/77 Mr. A. Schwencer                                  Rochester, New York                           DATE RECEIVED L. D. White, Jr.                                   1/24/77 jgLETTE R                    CI NOTO R I Z E D           PROP                   INPUT FORM           NUMBER OF COPIES RECEIVED ~
U.S. NUCLEAR REGULATORV C ISSION DOCKET NUMBER 50-244 NRC DISl RIBUTION FoR PART 50 DOCKET MATERIAL a
ORIGINAL                )5VNC LASS I F I E D Qcor v                              I                                                                One signed DESCRIPTION                                                              ENCLOSURE Ltr. w/attached...re           our 12/17/76       ltr...
F <LE NUMBE R Mr. A. Schwencer FROM:
furnishing response to our request for additional'nformation with regard to the Ginna Appendix I evaluation...                                                                   lt PLANT NAME'.
Rochester Gas
E. Ginna       fjl                                                     ACKNOWLEDGED                        ..-
& Electric Corp.
APPENDIX       I DISTRIBUTION AFTER           ISSUANCE OF A LICENSE (3-P)
Rochester, New York L. D. White, Jr.
DO NOT RKMOVI SAFETY                                         FOR ACTION/INFORMATION          1 25 77 BRANCH CHIEF:           (3)               Schwencer PROJECT MANAGER                           Wambach
DATE OF DOCUMENT 1/19/77 DATE RECEIVED 1/24/77 jgLETTER ORIGINAL Qcor v DESCRIPTION CINOTOR IZ E D
      -LIC- ASST.:                               Sheppard INTERNAL D IST RI BUTION REG  FILE I&E         2 OELD GOSSICK & STAFF
)5VNC LASS I F I E D I
    -BUTLER .
PROP INPUT FORM ENCLOSURE NUMBER OF COPIES RECEIVED
    --GRIMES DENTON LTR BALLARD AMMILL HULMAN MARKEE J   COLLINS         2 KREGER VERDERY LPDR:Rochester           N. Y.         EXTERNAL DISTRIBUTION                                           CONTROL NUMBER LPDR:
~
TIC N
One signed Ltr. w/attached...re our 12/17/76 ltr...
ACRS               He&%86               TO  hh 754 4
furnishing response to our request for additional'nformation with regard to the Ginna Appendix I evaluation...
S
PLANT NAME'.
                                                                                                                        ~I NRC FORM 195 I2 78)
E. Ginna fjl APPENDIX I DISTRIBUTION AFTER ISSUANCE OF A LICENSE lt ACKNOWLEDGED..-
(3-P)
DO NOT RKMOVI SAFETY BRANCH CHIEF:
(3)
PROJECT MANAGER
-LIC-ASST.:
FOR ACTION/INFORMATION 1
25 77 Schwencer Wambach Sheppard REG FILE INTERNALDIST RI BUTION I&E 2
OELD GOSSICK & STAFF
-BUTLER.
--GRIMES DENTON LTR BALLARD AMMILL HULMAN MARKEE J
COLLINS 2
KREGER VERDERY LPDR:Rochester N. Y.
LPDR:
TIC EXTERNAL DISTRIBUTION CONTROL NUMBER N
ACRS He&%86 S
NRC FORM 195 I2 78)
TO hh 754 4
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IIIZj~jgZ ZZrZZ IIIIjIIjt I IIIIIIIIII ROCHESTER GAS AND ELECTRIC CORPORATION           o 89 EAST AVENUE, ROCHESTER, N.Y. 74649 LEON D. WHITE, JR,                                                           YCLCPNONC YICC PRCSIDCNT                                                     ARCA CODC 7IC 546-2700 3
> IIIIjIIjt IIIIIIIIIII ROCHESTER GAS AND ELECTRIC CORPORATION o
January 19, 1977                          9EcBvEO
89 EAST AVENUE, ROCHESTER, N.Y. 74649 LEON D. WHITE, JR, YICC PRCSIDCNT YCLCPNONC ARCA CODC 7IC 546-2700 Mr. A. Schwencer, Chief Operating Reactors Branch Il Division of Operating Reactors U.S. Nuclear Regulatory Commission Washington, D.C.
                                                                                      ~q 24        l977 u
20555
Mr. A. Schwencer,                 Chief Operating Reactors Branch Division of Operating Reactors Il                                          @~EM'he U.S. Nuclear Regulatory Commission Washington, D.C.                   20555


==Dear Mr. Schwencer:==
==Dear Mr. Schwencer:==
 
January 19, 1977 3
enclosed material has been prepared in response             to your     letter of           December 17, 1976 requesting   additional       information with regard to the Ginna Appendix j: evaluation. Forty copies are being enclosed for your convenience.
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@~EM'he enclosed material has been prepared in response to your letter of December 17, 1976 requesting additional information with regard to the Ginna Appendix j: evaluation.
Forty copies are being enclosed for your convenience.
Very truly yours, L.D. White, Jr.
Very truly yours, L.D. White, Jr.
Enclosure 6
Enclosure 6
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Response to NRC Additional Information Requests, Appendix I R. E. Ginna Nuclear Power Plant Res onse 'to I'tern 1         Condensate Demineralizer. S stem l.a   Average flow     rate through demineralizers Based upon an expected flow fraction of 0.69 of the total steam flow, the average flow rate through the demineralizers is calculated to be 4.6 x 106 lb/hr.
===Response===
l.b   Demineralizer type D~ee   bed l.c  Number and     size of demineralizers Pour units will be installed, three for simultaneous operation and one for standby. Each unit contains 204 ft3 of 50/50 anion/cation resin.
to NRC Additional Information Requests, Appendix I R. E. Ginna Nuclear Power Plant Res onse 'to I'tern 1 Condensate Demineralizer.
led Regeneration frequency The regeneration frequency for the condensate demineralizer system is assumed to be 3.5 days per demineralizer according to NUREG-0017. This value is then multiplied by the number of de-mineralizer units (4) to obtain a regeneration time of 14 days for the entire system. It is estimated, however, that the actual condensate demineralizer regeneration frequency may be on the order of 10-14 days per demineralizer or a regeneration time of 40-56 days for the entire system.
S stem l.a Average flow rate through demineralizers Based upon an expected flow fraction of 0.69 of the total steam flow, the average flow rate through the demineralizers is calculated to be 4.6 x 106 lb/hr.
1 e  Indication whether ultrasonic resin cleaning is used and the waste     liquid volume associated with its   use.
l.b Demineralizer type l.c D~ee bed Number and size of demineralizers led Pour units will be installed, three for simultaneous operation and one for standby.
No   ultrasonic cleaning is planned for use.
Each unit contains 204 ft3 of 50/50 anion/cation resin.
Regenerant .volume and activity..
Regeneration frequency 1 e The regeneration frequency for the condensate demineralizer system is assumed to be 3.5 days per demineralizer according to NUREG-0017.
NUREG-0017 assumes a regenerant flow rate of 3400 gpd (1.24 x 106 gallons per year). If one assumes a regeneration frequency of 3.5 days per demineralizer according to NUREG-0017, this results in approximately 104   regenerations per year.     The volume calculated for each demineralizer regeneration       is then 1.19 x 104 gallons.     More realistic estimates indicate that
This value is then multiplied by the number of de-mineralizer units (4) to obtain a regeneration time of 14 days for the entire system.
It is estimated, however, that the actual condensate demineralizer regeneration frequency may be on the order of 10-14 days per demineralizer or a regeneration time of 40-56 days for the entire system.
Indication whether ultrasonic resin cleaning is used and the waste liquid volume associated with its use.
No ultrasonic cleaning is planned for use.
Regenerant
.volume and activity..
NUREG-0017 assumes a regenerant flow rate of 3400 gpd (1.24 x 106 gallons per year). If one assumes a regeneration frequency of 3.5 days per demineralizer according to NUREG-0017, this results in approximately 104 regenerations per year.
The volume calculated for each demineralizer regeneration is then 1.19 x 104 gallons.
More realistic estimates indicate that


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each regeneration   will produce 20,.000 gal. of low con-ductivity waste which is retained in a separate storage tank and reused in future regenerations as rinse and sluice water. Each regeneration will also produce from 28,250 gal. to 35,750 gal. of high conductivity waste which must be neutralized and disposed of.
each regeneration will produce 20,.000 gal. of low con-ductivity waste which is retained in a separate storage tank and reused in future regenerations as rinse and sluice water.
These volumes will be generated     every 10 days to 2 weeks under normal operating,   conditions.
Each regeneration will also produce from 28,250 gal. to 35,750 gal. of high conductivity waste which must be neutralized and disposed of.
Using the assumptions of NUREG-OOl7, the total annual release from the plant due to regeneration waste is calculated to be 4.6 curies/yr. However,       it is not expected that operation of the condensate demineralizer system would be maintained during periods of significant primary-to-second leakage in the plant.
These volumes will be generated every 10 days to 2 weeks under normal operating, conditions.
Res onse to Item 2       Neteorolo ical Parameter Ad'ustments Extrapolation of wind speeds measured at the 50 ft.
Using the assumptions of NUREG-OOl7, the total annual release from the plant due to regeneration waste is calculated to be 4.6 curies/yr.
However, it is not expected that operation of the condensate demineralizer system would be maintained during periods of significant primary-to-second leakage in the plant.
Res onse to Item 2
Neteorolo ical Parameter Ad'ustments Extrapolation of wind speeds measured at the 50 ft.
elevation to the 33 ft. level was performed using the mathematical relationship given in Appendix D, Volume 2 of the Ginna Environmental Report (1972).
elevation to the 33 ft. level was performed using the mathematical relationship given in Appendix D, Volume 2 of the Ginna Environmental Report (1972).
Temperature   differential data   were adjusted to represent LT l50 ft-33 ft from actual dT l50 ft lO ft measurements by employing a logarithmic correction factor of 0.56.
Temperature differential data were adjusted to represent LT l50 ft-33 ft from actual dT l50 ft lO ft measurements by employing a logarithmic correction factor of 0.56.
The correction factor, P, was calculated'n the following manner:
The correction factor, P, was calculated'n the following manner:
P =   1n   150 fn    = 0.55 33 fn ln   l50 10
P =
1n
= 0.55 150 fn 33 fn ln l50 10


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Latest revision as of 20:46, 5 January 2025

Forwards Response Letter of 12/17/1976 Requesting Additional Information Regarding Appendix I Evaluation
ML18142A837
Person / Time
Site: Ginna Constellation icon.png
Issue date: 01/19/1977
From: White L
Rochester Gas & Electric Corp
To: Schwencer A
Office of Nuclear Reactor Regulation
References
Download: ML18142A837 (8)


Text

NRC FORM 195 I2-70)

U.S. NUCLEAR REGULATORV C ISSION DOCKET NUMBER 50-244 NRC DISl RIBUTION FoR PART 50 DOCKET MATERIAL a

F <LE NUMBE R Mr. A. Schwencer FROM:

Rochester Gas

& Electric Corp.

Rochester, New York L. D. White, Jr.

DATE OF DOCUMENT 1/19/77 DATE RECEIVED 1/24/77 jgLETTER ORIGINAL Qcor v DESCRIPTION CINOTOR IZ E D

)5VNC LASS I F I E D I

PROP INPUT FORM ENCLOSURE NUMBER OF COPIES RECEIVED

~

One signed Ltr. w/attached...re our 12/17/76 ltr...

furnishing response to our request for additional'nformation with regard to the Ginna Appendix I evaluation...

PLANT NAME'.

E. Ginna fjl APPENDIX I DISTRIBUTION AFTER ISSUANCE OF A LICENSE lt ACKNOWLEDGED..-

(3-P)

DO NOT RKMOVI SAFETY BRANCH CHIEF:

(3)

PROJECT MANAGER

-LIC-ASST.:

FOR ACTION/INFORMATION 1

25 77 Schwencer Wambach Sheppard REG FILE INTERNALDIST RI BUTION I&E 2

OELD GOSSICK & STAFF

-BUTLER.

--GRIMES DENTON LTR BALLARD AMMILL HULMAN MARKEE J

COLLINS 2

KREGER VERDERY LPDR:Rochester N. Y.

LPDR:

TIC EXTERNAL DISTRIBUTION CONTROL NUMBER N

ACRS He&%86 S

NRC FORM 195 I2 78)

TO hh 754 4

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4

+ I, IIIZj~jgZ ZZrZZ IIIEI)7'll>/l/IS/

> IIIIjIIjt IIIIIIIIIII ROCHESTER GAS AND ELECTRIC CORPORATION o

89 EAST AVENUE, ROCHESTER, N.Y. 74649 LEON D. WHITE, JR, YICC PRCSIDCNT YCLCPNONC ARCA CODC 7IC 546-2700 Mr. A. Schwencer, Chief Operating Reactors Branch Il Division of Operating Reactors U.S. Nuclear Regulatory Commission Washington, D.C.

20555

Dear Mr. Schwencer:

January 19, 1977 3

9EcBvEO

~q 24 l977 u

@~EM'he enclosed material has been prepared in response to your letter of December 17, 1976 requesting additional information with regard to the Ginna Appendix j: evaluation.

Forty copies are being enclosed for your convenience.

Very truly yours, L.D. White, Jr.

Enclosure 6

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,p Q5 II

Response

to NRC Additional Information Requests, Appendix I R. E. Ginna Nuclear Power Plant Res onse 'to I'tern 1 Condensate Demineralizer.

S stem l.a Average flow rate through demineralizers Based upon an expected flow fraction of 0.69 of the total steam flow, the average flow rate through the demineralizers is calculated to be 4.6 x 106 lb/hr.

l.b Demineralizer type l.c D~ee bed Number and size of demineralizers led Pour units will be installed, three for simultaneous operation and one for standby.

Each unit contains 204 ft3 of 50/50 anion/cation resin.

Regeneration frequency 1 e The regeneration frequency for the condensate demineralizer system is assumed to be 3.5 days per demineralizer according to NUREG-0017.

This value is then multiplied by the number of de-mineralizer units (4) to obtain a regeneration time of 14 days for the entire system.

It is estimated, however, that the actual condensate demineralizer regeneration frequency may be on the order of 10-14 days per demineralizer or a regeneration time of 40-56 days for the entire system.

Indication whether ultrasonic resin cleaning is used and the waste liquid volume associated with its use.

No ultrasonic cleaning is planned for use.

Regenerant

.volume and activity..

NUREG-0017 assumes a regenerant flow rate of 3400 gpd (1.24 x 106 gallons per year). If one assumes a regeneration frequency of 3.5 days per demineralizer according to NUREG-0017, this results in approximately 104 regenerations per year.

The volume calculated for each demineralizer regeneration is then 1.19 x 104 gallons.

More realistic estimates indicate that

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each regeneration will produce 20,.000 gal. of low con-ductivity waste which is retained in a separate storage tank and reused in future regenerations as rinse and sluice water.

Each regeneration will also produce from 28,250 gal. to 35,750 gal. of high conductivity waste which must be neutralized and disposed of.

These volumes will be generated every 10 days to 2 weeks under normal operating, conditions.

Using the assumptions of NUREG-OOl7, the total annual release from the plant due to regeneration waste is calculated to be 4.6 curies/yr.

However, it is not expected that operation of the condensate demineralizer system would be maintained during periods of significant primary-to-second leakage in the plant.

Res onse to Item 2

Neteorolo ical Parameter Ad'ustments Extrapolation of wind speeds measured at the 50 ft.

elevation to the 33 ft. level was performed using the mathematical relationship given in Appendix D, Volume 2 of the Ginna Environmental Report (1972).

Temperature differential data were adjusted to represent LT l50 ft-33 ft from actual dT l50 ft lO ft measurements by employing a logarithmic correction factor of 0.56.

The correction factor, P, was calculated'n the following manner:

P =

1n

= 0.55 150 fn 33 fn ln l50 10

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