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{{#Wiki_filter:5                                                U.se NUCLEAR REGULATORY C       ISSION   DOCKET NUMBER NRC>ORA     1 (2 78)                                                                                                               50-244 FILE NUMBER CIRC DISTRIBUTION FoR PART 50 DOCKET MATERIAL TO:                                                 FROM:                                                   DATE OF DOCUMENT Rochester Gas & Electric Co.                               ~
{{#Wiki_filter:U.se NUCLEAR REGULATORY C ISSION NRC>ORA 1 5 (2 78)
CIRC DISTRIBUTION FoR PART 50 DOCKET MATERIAL DOCKET NUMBER 50-244 FILE NUMBER TO:
-Mr. A. Schwencer FROM:
Rochester Gas
& Electric Co.
Rochester, New York L. D. White Jr.
DATE OF DOCUMENT
~
2/11/77
2/11/77
          -Mr. A. Schwencer                          Rochester, New York                          ~       DATE RECEIVED L. D. White Jr.                                                  2/16/77
~
/(LETTER               '0 NOTOR 2 E DI              PROP                       INPUT FORM                 NUMBER OF COPIES RECEIVED ORIGINAL          -ISUNCLASSIFIED
DATE RECEIVED 2/16/77
  ~QCOPY                                                                                                          . One sz.gned DESCRIPTION                                                              ENCLOSURE Ltr. furnishing     response to our 1/12/77 request for information on fuel rod             bowing'nd on DNBR margins presently available. ~ .
/(LETTER ORIGINAL
                                                                                                        "'    11 I'
~QCOPY DESCRIPTION
PLANT NAME R. E. Ginna No. 1 SAFETY                                   FOR ACTION/INFORMATION                               2 17 77                 RJL ASSXGNED AD!
'0 NOTOR I2 E D
Schwencer R
-ISUNCLASSIFIED PROP INPUT FORM ENCLOSURE NUMBER OF COPIES RECEIVED
hXC EC   .MANA E ASST --- 
. One sz.gned Ltr. furnishing response to our 1/12/77 request for information on fuel rod bowing'nd on DNBR margins presently available.
                        ~ -- =-
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PLANT NAME R. E. Ginna No.
                                  ..-   .,
1 SAFETY ASSXGNED AD!
Wambach She ard..
FOR ACTION/INFORMATION Schwencer 2
PROJECT MANAGER LIC ASST     . ~ .
17 77 RJL R
INTERNAL D IST RI BUTION SYSTEMS SAFETY                    PLANT SYSTEMS                          S TE SAFE
EC
    .NRC- PJ)R                           - HEINEMAN                          TEDESCO X&E                                   SCHROEDER OELD GOSSXCK & STAFF                       ENGXNEERING                        IPPOLITO MXPC                                                                                                             ERNST CASE                                                                                                           BALLARD HANAUER                               SIHWEIL                            OPERATING REACTORS                    SPANGLER HARLESS                               PAWL CK                            STELLO SITE TECH PROJECT. MANAGEMENT                   REACTOR SAFE                      OPERATING        CH                    GAMMILL BOYD                                 ROSS                              EISENHUT                              STEPP P0 COLLINS                           NOVAK                                                                    HULMAN HOUSTON                               ROSZTOCZY PETERSON                             CHECK                              BUTLE                                  SITE ANALYSIS MELTZ                                                                                                           VOLLMER HELTEMES                               AT& I                                                                    BUNCH SKOVHOLT                               SALTZMAN                                                                J    COLLINS RUTBERG                                                                  KREGER LPDR Rochester     N Y             EXTERNAL DISTRIBUTION                                                          QNTROL NUMBER LPDR~                                 NAT LAB                            B 0 TXC:                                 REG V IE                          ULR KSON    OR NSIC:
.MANA E
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Wambach hXC ASST ---
She ard..
PROJECT MANAGER LIC ASST
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.NRC-PJ)R X&E OELD GOSSXCK & STAFF MXPC CASE HANAUER HARLESS PROJECT. MANAGEMENT BOYD P0 COLLINS HOUSTON PETERSON MELTZ HELTEMES SKOVHOLT LPDR Rochester N Y LPDR~
TXC:
NSIC:
ASLB:
ASLB:
LA PDR CONSUL NTS:
ACRS CYS jHRrBXH&/
l&oi ACRS      CYS  jHRrBXH&/
INTERNALD SYSTEMS SAFETY
NRC FORM 196 I2 78I
- HEINEMAN SCHROEDER ENGXNEERING SIHWEIL PAWL CK REACTOR SAFE ROSS NOVAK ROSZTOCZY CHECK AT& I SALTZMAN RUTBERG EXTERNALDISTRIBUTION NAT LAB REG V IE LA PDR CONSUL NTS:
ISTRI BUTION PLANT SYSTEMS TEDESCO IPPOLITO OPERATING REACTORS STELLO OPERATING CH EISENHUT BUTLE B 0 ULR KSON OR S TE SAFE ERNST BALLARD SPANGLER SITE TECH GAMMILL STEPP HULMAN SITE ANALYSIS VOLLMER BUNCH J
COLLINS KREGER QNTROL NUMBER l&oi NRC FORM 196 I2 78I


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ROCHESTER GAS AND ELECTRIC CORPORATION         o 89 EAST AVENUE, ROCHESTER, N.Y. 14649 LEON D. WHITE, JR.                                                             TELEPHONE VICE RRESIOENT                                                     AREA cooE 7ld 546.2700 February       ll, 1977
ROCHESTER GAS AND ELECTRIC CORPORATION o
                                                                                            ~scg~,~
89 EAST AVENUE, ROCHESTER, N.Y. 14649 LEON D. WHITE, JR.
Director of Nuclea'r Reactor Regulation                     cg Attention: Mr. A. Schw'en'cer, Chief Opexating Rea'ctors Branch   0'!
VICE RRESIOENT TELEPHONE AREA cooE 7ld 546.2700 February ll, 1977 Director of Nuclea'r Reactor Regulation Attention:
                                                                                            /g.~
Mr. A. Schw'en'cer, Chief Opexating Rea'ctors Branch 0'!
U.S. Nuclea'r Regulatory Commission                                                     ,co~~  >Ey      I, Washington, D.C.                 20555
U.S. Nuclea'r Regulatory Commission Washington, D.C.
                                                              'o~%r,
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==Dear Mr. Schwencer:==
==Dear Mr. Schwencer:==
                                              >r,O                   1I This     letter is in res'ponse 'to your reques f for information on fuel'od bowing and on D h rh
>r,O 1I This letter is in res'ponse
                                                                      .
'to your reques f
                                                                          ~2,        1977 ns presently available.'e have 'reviewed our fuel design in de supplier, Westingho'use 'Elec'tric Corporation, and have obtained il  with our the DNBR margins which 'are pres'ently available.
. ~2, 1977 for information on fuel'od bowing and on D h rh ns presently available.'e have 'reviewed our fuel design in de il with our
Protection against reaching DNB ratios less than 1.30 is provided in two plant protec'tion setpoints, the 'underfrequency trip set-point. and the'vertemperature aT setpoint. The underfrequency trip provides'rotection for the loss-of-flow design basis accident while the ovex'temperature 5T trip provides protection for other potentially                                 "
: supplier, Westingho'use 'Elec'tric Corporation, and have obtained the DNBR margins which 'are pres'ently available.
limiting DNB rel'ated transients. The''present Technical Specification limit for the underfrequency trip setpoint is 57.5 Hz, however a change 'in the Tec'hn'ic'al Spec'ification limit to 55 Hz was requested by application dated November', 1976. The analysis supporting this application showed a minimum DNBR during the loss of flow accident of 1.615 for a trip setpoint of 55 Hz and a frequency decay rate of 5 Hz/sec , for a margin of 24.2% to a DNBR of 1.30.                         In addition, mar-gins 'are available 'in the'NBR analysis for the thermal diffusion coefficient'f 3'.'0% and for the 'pitch 'reduction of 3.3%. Thus, a total margin of 30.5% is available 'for the'oss of flow design basis accident.
Protection against reaching DNB ratios less than 1.30 is provided in two plant protec'tion setpoints, the 'underfrequency trip set-point. and the'vertemperature aT setpoint.
The analysis supporting sel'ection of the Technical Specification limit on the oVertemperature 'nT trip setpoint was originally performed for Cycle '3 and was submitted to the'RC on February 16, 1973. In this analysis a 9.9% DNBR penalty for densification heat flux spike and a for fuel rod flattening wer'e incorporated. As neither'f penalty 10.0% DNBR the'se 'pen'alties're. required now, they provide for a margin of 19.9%. In addition, the''ther'mal diffusion coefficient and pitch reduction margins are 'availabl'e, yiel'ding a total margin of 26.2%.
The underfrequency trip provides'rotection for the loss-of-flow design basis accident while the ovex'temperature 5T trip provides protection for other potentially limiting DNB rel'ated transients.
Analysis for Cycl'e 5, submitted to the NRC on March 26, 1975, resulted in a slight increa'se in the''ovextemperature 6T trip setpoint, thereby using 4.0%, of the DNBR margin. Inasmuch as the overtemperature bT has not been changed since 'the 'Cycle 5 analysis, a DNBR margin of 22.2%
The''present Technical Specification limit for the underfrequency trip setpoint is 57.5 Hz, however a
change 'in the Tec'hn'ic'al Spec'ification limit to 55 Hz was requested by application dated November',
1976.
The analysis supporting this application showed a minimum DNBR during the loss of flow accident of 1.615 for a trip setpoint of 55 Hz and a frequency decay rate of 5 Hz/sec
, for a margin of 24.2% to a DNBR of 1.30.
In addition, mar-gins 'are available 'in the'NBR analysis for the thermal diffusion coefficient'f 3'.'0% and for the 'pitch 'reduction of 3.3%.
: Thus, a total margin of 30.5% is available 'for the'oss of flow design basis accident.
The analysis supporting sel'ection of the Technical Specification limit on the oVertemperature
'nT trip setpoint was originally performed for Cycle '3 and was submitted to the'RC on February 16, 1973.
In this analysis a 9.9%
DNBR penalty for densification heat flux spike and a
10.0%
DNBR penalty for fuel rod flattening wer'e incorporated.
As neither'f the'se 'pen'alties're.
required now, they provide for a margin of 19.9%.
In addition, the''ther'mal diffusion coefficient and pitch reduction margins are 'availabl'e, yiel'ding a total margin of 26.2%.
Analysis for Cycl'e 5, submitted to the NRC on March 26, 1975, resulted in a slight increa'se in the''ovextemperature 6T trip setpoint, thereby using 4.0%, of the DNBR margin.
Inasmuch as the overtemperature bT has not been changed since 'the 'Cycle 5 analysis, a
DNBR margin of 22.2%
is now available.
is now available.


ROCHESTER GAS AND ELECTR ORP.                               SHEET NO. 2 To February   ll, 1977 Mr. A. Schwencer,     Chief Operating Reactors Branch   41 In addition to reviewing the DNBR margins available, we have reviewed fuel inspection data. As discussed in our letter of August 18, 1976, no fuel rod bowing has be'e'n seen in television examination of fuel assemblies with assembly aver'age burnups in excess of 2S,000 MWD/MTU.
ROCHESTER GAS AND ELECTR ORP.
February ll, 1977 To Mr. A. Schwencer, Chief Operating Reactors Branch 41 SHEET NO.
2 In addition to reviewing the DNBR margins available, we have reviewed fuel inspection data.
As discussed in our letter of August 18,
: 1976, no fuel rod bowing has be'e'n seen in television examination of fuel assemblies with assembly aver'age burnups in excess of 2S,000 MWD/MTU.
Any assessment of potential DNBR penalties should, in our opinion, be consistent with thes'e 'actual measured data.
Any assessment of potential DNBR penalties should, in our opinion, be consistent with thes'e 'actual measured data.
In summary, DNBR margins of at least 22.2% are available. In addition, no fuel rod bowing has bee'n observed in Ginna 9 grid, stainless steel guide tube, 14 x 14 fuel.
In summary, DNBR margins of at least 22.2% are available.
In addition, no fuel rod bowing has bee'n observed in Ginna 9 grid, stainless steel guide tube, 14 x 14 fuel.
Very truly yours, L.D. Whi e, Jr.
Very truly yours, L.D. Whi e, Jr.


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Latest revision as of 20:46, 5 January 2025

Response to Request of 1/12/1977, DNBR Margins of at Least 22.2% Are Available; No Fuel Rod Bowing Has Been Observed in Ginna 9 Grid, Stainless Steel Guide Tube, 14 X 14 Fuel
ML18142A836
Person / Time
Site: Ginna Constellation icon.png
Issue date: 02/11/1977
From: White L
Rochester Gas & Electric Corp
To: Schwencer A
Office of Nuclear Reactor Regulation
References
Download: ML18142A836 (5)


Text

U.se NUCLEAR REGULATORY C ISSION NRC>ORA 1 5 (2 78)

CIRC DISTRIBUTION FoR PART 50 DOCKET MATERIAL DOCKET NUMBER 50-244 FILE NUMBER TO:

-Mr. A. Schwencer FROM:

Rochester Gas

& Electric Co.

Rochester, New York L. D. White Jr.

DATE OF DOCUMENT

~

2/11/77

~

DATE RECEIVED 2/16/77

/(LETTER ORIGINAL

~QCOPY DESCRIPTION

'0 NOTOR I2 E D

-ISUNCLASSIFIED PROP INPUT FORM ENCLOSURE NUMBER OF COPIES RECEIVED

. One sz.gned Ltr. furnishing response to our 1/12/77 request for information on fuel rod bowing'nd on DNBR margins presently available.

~.

11 I'

PLANT NAME R. E. Ginna No.

1 SAFETY ASSXGNED AD!

FOR ACTION/INFORMATION Schwencer 2

17 77 RJL R

EC

.MANA E

~ --

=-.-..

Wambach hXC ASST ---

She ard..

PROJECT MANAGER LIC ASST

. ~

.NRC-PJ)R X&E OELD GOSSXCK & STAFF MXPC CASE HANAUER HARLESS PROJECT. MANAGEMENT BOYD P0 COLLINS HOUSTON PETERSON MELTZ HELTEMES SKOVHOLT LPDR Rochester N Y LPDR~

TXC:

NSIC:

ASLB:

ACRS CYS jHRrBXH&/

INTERNALD SYSTEMS SAFETY

- HEINEMAN SCHROEDER ENGXNEERING SIHWEIL PAWL CK REACTOR SAFE ROSS NOVAK ROSZTOCZY CHECK AT& I SALTZMAN RUTBERG EXTERNALDISTRIBUTION NAT LAB REG V IE LA PDR CONSUL NTS:

ISTRI BUTION PLANT SYSTEMS TEDESCO IPPOLITO OPERATING REACTORS STELLO OPERATING CH EISENHUT BUTLE B 0 ULR KSON OR S TE SAFE ERNST BALLARD SPANGLER SITE TECH GAMMILL STEPP HULMAN SITE ANALYSIS VOLLMER BUNCH J

COLLINS KREGER QNTROL NUMBER l&oi NRC FORM 196 I2 78I

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ROCHESTER GAS AND ELECTRIC CORPORATION o

89 EAST AVENUE, ROCHESTER, N.Y. 14649 LEON D. WHITE, JR.

VICE RRESIOENT TELEPHONE AREA cooE 7ld 546.2700 February ll, 1977 Director of Nuclea'r Reactor Regulation Attention:

Mr. A. Schw'en'cer, Chief Opexating Rea'ctors Branch 0'!

U.S. Nuclea'r Regulatory Commission Washington, D.C.

20555 cg

'o~%r,

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Dear Mr. Schwencer:

>r,O 1I This letter is in res'ponse

'to your reques f

. ~2, 1977 for information on fuel'od bowing and on D h rh ns presently available.'e have 'reviewed our fuel design in de il with our

supplier, Westingho'use 'Elec'tric Corporation, and have obtained the DNBR margins which 'are pres'ently available.

Protection against reaching DNB ratios less than 1.30 is provided in two plant protec'tion setpoints, the 'underfrequency trip set-point. and the'vertemperature aT setpoint.

The underfrequency trip provides'rotection for the loss-of-flow design basis accident while the ovex'temperature 5T trip provides protection for other potentially limiting DNB rel'ated transients.

Thepresent Technical Specification limit for the underfrequency trip setpoint is 57.5 Hz, however a

change 'in the Tec'hn'ic'al Spec'ification limit to 55 Hz was requested by application dated November',

1976.

The analysis supporting this application showed a minimum DNBR during the loss of flow accident of 1.615 for a trip setpoint of 55 Hz and a frequency decay rate of 5 Hz/sec

, for a margin of 24.2% to a DNBR of 1.30.

In addition, mar-gins 'are available 'in the'NBR analysis for the thermal diffusion coefficient'f 3'.'0% and for the 'pitch 'reduction of 3.3%.

Thus, a total margin of 30.5% is available 'for the'oss of flow design basis accident.

The analysis supporting sel'ection of the Technical Specification limit on the oVertemperature

'nT trip setpoint was originally performed for Cycle '3 and was submitted to the'RC on February 16, 1973.

In this analysis a 9.9%

DNBR penalty for densification heat flux spike and a

10.0%

DNBR penalty for fuel rod flattening wer'e incorporated.

As neither'f the'se 'pen'alties're.

required now, they provide for a margin of 19.9%.

In addition, thether'mal diffusion coefficient and pitch reduction margins are 'availabl'e, yiel'ding a total margin of 26.2%.

Analysis for Cycl'e 5, submitted to the NRC on March 26, 1975, resulted in a slight increa'se in theovextemperature 6T trip setpoint, thereby using 4.0%, of the DNBR margin.

Inasmuch as the overtemperature bT has not been changed since 'the 'Cycle 5 analysis, a

DNBR margin of 22.2%

is now available.

ROCHESTER GAS AND ELECTR ORP.

February ll, 1977 To Mr. A. Schwencer, Chief Operating Reactors Branch 41 SHEET NO.

2 In addition to reviewing the DNBR margins available, we have reviewed fuel inspection data.

As discussed in our letter of August 18,

1976, no fuel rod bowing has be'e'n seen in television examination of fuel assemblies with assembly aver'age burnups in excess of 2S,000 MWD/MTU.

Any assessment of potential DNBR penalties should, in our opinion, be consistent with thes'e 'actual measured data.

In summary, DNBR margins of at least 22.2% are available.

In addition, no fuel rod bowing has bee'n observed in Ginna 9 grid, stainless steel guide tube, 14 x 14 fuel.

Very truly yours, L.D. Whi e, Jr.

0

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