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{{#Wiki_filter:V.S.NUCLLAB flEGULATOB V COMMISSION fIIIC r:o>>M 195 17 76I w" r r~>In~NRC DISTRIBUTION FOB,P, T GO DOCICET MATERIAL DOCKET NUMBER 50-220 FI'NVMOEB'l Mr.George'Lear FROM: Niagara Mohawk Power Corp.Syracuse, New York Mr, Rudolph R.Schneider DATE OF DOCUMENT 8/3/76 DATL=RECEIVE D 8/6/76 ABETTER PjjjDB IOINAL Q COP V DESCRIPTION ONOTOB IZED PKVNCLASSIF I ED PROP INPUT FORM ENCLOSU RE NUMBER OF COPIES RECEIVED One signed Ltr, w/attached,;,re their 5/1'9/76 ltr, and our 6/9/76 ltr.~~.furnishing additional in information concerning Assembly Averaged'ower-Void Relationship.Tech Spec,-~ACKNOWLEDGED PLANT NAME: Nine Mile Point gi (5-P)'O NOT RziMOVZ.SAFETY.ASSXGNED AD: BRANCH CHIEF: PROJECT MI ANAGER: LXC~ASSTo: Lear Parrish FOR ACTION/INFORMATION ASSI NED DE PRO i NA~L S RE'C'X F'NTERNAL D SYSTE'IS SAFETY IS1 Rl BUTION SITE SA~NRC PDR X&E OEI.D GOSSXCIC&STAFF MIPC CASE IIANAUER JIARLES PROJECT HAVAGFtIEN BOYD P COLLINS HOUSTON PETERSON MELTZ 11ELTEMES S KOVIIOLT LPDR: Oswe o N Y.TXC:.NS,I ASLB: ACI<S CYS He&BBKI NBC Fof1M 166 (2 76)HE XNEI IAN SCHROEDER ENGXNEERING ifIACCARRY
{{#Wiki_filter:V.S. NUCLLAB flEGULATOBV COMMISSION   DOCKET NUMBER fIIIC r:o>>M   195                           w" r r   ~
.KNIGHT SIHIPEIL PAMLICKI REACTOR SAFETZ ROSS NOVAK ROSZTOCZY CHECK AT&X SALTZMAN RUTBERG EXTERNAL DISTRIBUTION Nl lT LAB REGS VIE LA PDR CONSULTANTS
17 76I                                      >In   ~
~~?r BENAROYA IPPOLXTO~KIRKICOOD OPERATItIG REACTORS OPERATXN r CI EISENHUT SHAO BAER BUTLI R GRIMES W UL'RIKSON ORNL ENV?.'RO AMASS~??i.NZm~~lf,aa ENV S E CONTROL NUMiBER 7F/B~
50-220 FI'  NVMOEB NRC DISTRIBUTION FOB,P,                   T GO DOCICET MATERIAL FROM:                                                  DATE OF DOCUMENT
N y tY~N I~~4~N t~~~
                'l                                                                                                     8/3/76 Mr. George 'Lear                                     Niagara Mohawk Power Corp.
NIAGARA MOHAWK POWER CORPORATION NIAGARA~MOHAWK 300 ERIE BOULEVARD WEST SYRACUSE, H.Y.l3202 August 3, 1976 Director of Nuclear Reactor Regulation Attn: Mr.George Lear, Chief Operating Reactors Branch III3 U.S.Nuclear Regulatory Commission Washington, D.C.20555 Re: Nine Mile Point Unit 1 Docket No.50-220 DPR-63
Syracuse, New York                                   DATL= RECEIVE D ABETTER                                                    Mr, Rudolph R. Schneider                                   8/6/76 ONOTOB IZED                   PROP                               INPUT FORM         NUMBER OF COPIES RECEIVED PjjjDB IOINAL            PKVNCLASSIF I ED Q COP V                                                                                                            One   signed DESCRIPTION                                                                          ENCLOSU RE Ltr, w/attached,;,re their               5/1'9/76     ltr,   and our 6/9/76       ltr. ~ ~ .furnishing additional in information concerning Assembly Averaged Relationship .Tech Spec,-                     'ower-Void ACKNOWLEDGED (5-P)'O
                                                                                          ~
PLANT NAME:
Nine Mile Point         gi                                                                       NOT RziMOVZ             .
SAFETY.                                     FOR ACTION/INFORMATION ASSXGNED AD:                                                                               ASSI  NED    DE BRANCH     CHIEF:                         Lear i
PROJECT MIANAGER:
LXC ~ ASSTo:                               Parrish                                 ~L     PRO S
NA RE'C'X F'NTERNAL                 SYSTE 'IS SAFETY D IS1 Rl BUTION SITE SA   ~
NRC PDR                               HE XNEIIAN                                                                  ENV?.'RO  AMASS~
X&E                                   SCHROEDER                                ?r BENAROYA                  ??i.NZm~~lf,aa OEI.D GOSSXCIC & STAFF                     ENGXNEERING                                      IPPOLXTO                  ENV MIPC                                 ifIACCARRY                                      ~ KIRKICOOD CASE                               . KNIGHT IIANAUER                             SIHIPEIL                                          OPERATItIG REACTORS JIARLES                               PAMLICKI PROJECT HAVAGFtIEN                   REACTOR SAFETZ                                    OPERATXN r    CI BOYD                                 ROSS                                              EISENHUT P   COLLINS                         NOVAK                                            SHAO HOUSTON                               ROSZTOCZY                                        BAER PETERSON                             CHECK                                            BUTLI R                    S  E MELTZ                                                                                   GRIMES 11ELTEMES                             AT&X S KOVIIOLT                           SALTZMAN RUTBERG EXTERNAL DISTRIBUTION                                                            CONTROL NUMiBER LPDR:     Oswe o       N Y.         Nl lT LAB                                                            W TXC:                                 REGS        VIE                                  UL'RIKSON ORNL
    .NS,I ASLB:
LA PDR CONSULTANTS 7F/B~
ACI<S     CYS   He&BBKI         ~  ~
NBC Fof1M 166 (2 76)


==Dear Mr.Lear:==
N y
Our letter of'ay 19, 1976 transmitted proposed changes to the Assembly Averaged Power-Void Relationship Technical Specification for Nine Mile Point Unit 1.1'our letter of June 9, 1976 requested additional information regarding that'roposed change.The attached responses address the questions contained in your letter.Sincerely, NIAGARA MOHAWK POWER CORPORATION pe g(P~o po S.gang P Rudolph.Schnei der, Vice President-Electric Operations Attachment
tY ~
'~<5 il't K'i c RESPOND.S TO JUNE 9, l976 NRC QUESTION NINE HILE POINT UNIT 1 Docket No.50-220 DPR-63 RecCuest Provide a quanti tative explanation of'ow exposure dependent"B" values are calculated.
N I
Include examples which show how different values of"B" were calculated for two different exposures of the same fuel.The examples should show (1)the relationships (equations) assumed, and (2)the source and numerical values of all terms in the relationship for: 1.maximum Average Planar Linear Heat=Generation Rate (EQPLHGR)and Average Heat Generation Rate (q)(i.e., assumed peaking factors).2.Dryout Time.(i.e., h, h.,flow, average density, q).g'n'" 3."B" values (i.e., void fraction, peaking factor, power).R~es ense The duration of nucleate boiling for non-jet pump plant ECCS analyses has been determined using the correlation (Equation 1, below)described in"General Electric Compliance with 10CFR50 Appendix K-Acceptance Criteria I.C.4." That correlation shows the time to boiling transition (dryout time)is a function exclusively of liquid volume fraction and power input to the bundle.Converged HAPLHGR limits and conservative axial power distributions were assumed for the dryout time determinations.
            ~ ~ 4 ~
Both HAPLHGR limits and dryout times are exposure dependent.
N t        ~
The following development shows how"B" values are calculated.
        ~  ~
(0~31)(Pf)(hf)gt I I Equation 1 ht=time to transition boiling, hr.3 p=saturated liquid density, ibm/ft h enthalpy of'aporization, BTU/ibm fg gist V (1--a)


(~/q=Powor generation in bundle, BTU/hr=(PF)(FCP)(ABTU)PF=bundle radial power factor FCP~fractional core power relative to 1850 Hh'BTU=average bundle output at 1850 Hft, BTU/hr 3 V=active coolant volume, ft a.=void fraction Therefore ht='0.31)(P)(hf)(V)(1-a.)(ABTU)(PF)(FCP)Equation 2"B" Factor=(1-a.)i (PF)(FCP)Equation 3~t Limiting this"B" factor relatioriship will assure that local power void values will not result in dr@out times shorter than those used.in the ECCS Analysis.Using Equation 2: "B" Factor=(ABTU)Qt)(0.31)(P f)(hf)(V)fg Equation 4 Assumed nominal values are: ABTU=1.1869 x 10 BTU/hr 7 pf~45.977 ibm/ft 3 hf=641.36 BTU/1 bm fg V~1.2696 ft, Znitial Core V=1.2948 ft , Reloads 1, 2, 3 3 r~~
NIAGARA MOHAWK POWER CORPORATION NIAGARA 300
V=1.2936 ft , Reloads 4, 5 3 Substituting the above values in Equation 4 yields the"B" factor relatiori-ships for the different reloads: "B" Factor=(1022.688)(ht)"B" Factor=(1002.784)(ht)"B" Factor=(1003.714)(b t)2'ni tial Core Reloads 1, 2, 3 Reloads 4, 5 Equation 5 Equa,tion 6 Equation 7 The folloving examples shov hov different values of"B" vere calculated for tvo different exposures of the same fuel (Reload 3):~Ex osure ECCS Anal sis Dr out Times HAPLHGR 5000 7fVD/T 25000 HVD/T 1.48 sec 1.59 sec 10.68 9.92 Sunsti tuting the above dryout times in Equation 6 yields: For 5000 IWD/T: "B" Factor=(1002.784)(ht)"B" Factor=1002.784lhr)
                                    ~       MOHAWK ERIE BOULEVARD WEST SYRACUSE, H.Y. l3202 August 3, 1976 Director of Nuclear Reactor Regulation Attn: Mr. George Lear, Chief Operating Reactors Branch III3 U. S. Nuclear Regulatory Commission Washington, D. C. 20555 Re:   Nine Mile Point Unit 1 Docket No. 50-220 DPR-63
(1.48 sec)3600 sec/hr"B" Factor=0.412 For 25000 IWD/T: "B" Factor=(1002.784) gt)"B" Factor=(1002.784/hr)
(1.59 sec)3600 sec/hr"B" Factor=0.443


e~eeest: Demonstrate how"B" values are calculated to assure conservatism when using the dryout times assumed in the ECCS analysis.R~es see As indicated in the above response, nominal values were.used to calculate, the"B" factors.Converged HApLHGR limits and conservative axial power distributions were assumed for t'e dryout time, determinations.
==Dear Mr. Lear:==
'In addition, a conservative c4rrelation (G.E.compliance with 10CFR50, Appendix K criteria I.C.4:)was used which was previously approved by the Commission.
 
A"B" Factor Limiting Condition for Operation is not necessary to assure that actual dryout times are conservative.
Our letter of'ay    19, 1976 transmitted proposed changes to the Assembly Averaged Power-Void Relationship Technical Specification for Nine Mile Point Unit 1. 1'our letter of June 9, 1976 requested additional information regarding that'roposed change. The attached responses address the questions contained in your letter.
Dryout time is only one of many conservative inputs used to determine HAPL/EGR limits, the ultimate restriction of interest.Sensitivity analyses performed by our fuel supplier have determined that the parameters used to calculate dryout time (void fraction, axial power distributions) are conservative when compared to normal plant operation.  
Sincerely, NIAGARA MOHAWK POWER CORPORATION Rudolph        . Schnei der, peg(P~o    po          Vice President        Electric  Operations S. gang P Attachment
~r~w y~}}
 
              ' ~
<5 il
      't K 'i
 
c RESPOND. S TO JUNE    9, l976 NRC QUESTION NINE  HILE  POINT    UNIT 1 Docket  No. 50-220 DPR-63 RecCuest Provide a quanti tative explanation of'ow exposure dependent "B" values are calculated. Include examples which show how different values of "B" were calculated for two different exposures of the same fuel. The examples should show (1) the relationships (equations) assumed, and (2) the source and numerical values of all terms in the relationship for:
: 1. maximum Average      Planar Linear      Heat=  Generation Rate    (EQPLHGR) and Average Heat Generation Rate (q)                (i.e.,  assumed peaking factors)      .
: 2. Dryout Time.      (i.e., h,g'n'"h., flow,      average density,    q).
: 3.  "B" values      (i.e., void fraction,        peaking  factor, power).
R~es ense The  duration of nucleate boiling for non-jet              pump  plant  ECCS  analyses has been determined using the correlation (Equation 1, below) described in "General Electric Compliance with 10CFR50 Appendix K-Acceptance Criteria I.C.4." That correlation shows the time to boiling transition (dryout time)  is  a function exclusively of liquid volume fraction and power input to the bundle. Converged HAPLHGR limits and conservative axial power distributions were assumed for the dryout time determinations.
Both HAPLHGR limits and dryout times are exposure dependent.                    The following development shows how "B" values are calculated.
(0 ~ 31) (Pf)  (hf  )        Equation  1 gt II ht    =  time to transition        boiling, hr.
3 p    =  saturated liquid density, ibm/ft h
enthalpy  of'aporization,        BTU/ibm fg gist V  (1--a)
 
(~
                            /
q        =    Powor generation        in bundle, BTU/hr = (PF)      (FCP) (ABTU)
PF        =    bundle    radial    power  factor FCP      ~    fractional core        power relative to  1850 Hh'BTU
                          =    average bundle output        at 1850 Hft, BTU/hr V        =    active coolant volume,        ft3
: a.        =    void fraction Therefore ht ='0.31)      (P  ) (hf  ) (V) (1  - a.)
Equation  2 (ABTU)            (PF) (FCP)
          "B" Factor = (1 i
a.)
Equation 3  ~
(PF) (FCP) t Limiting this "B" factor relatioriship will assure that local power void values will not result in dr@out times shorter than those used.
in  the    ECCS  Analysis.
Using Equation 2:
          "B" Factor =              (ABTU)    Qt)              Equation  4 (0.31)  (P f) (hffg) (V)
Assumed nominal        values are:
7 ABTU =      1.1869 x 10 BTU/hr pf    ~    45.977      ibm/ft3 hffg  =    641 . 36    BTU/1 bm V      ~    1.2696    ft, Znitial        Core V      =    1.2948    ft3  , Reloads 1, 2, 3
 
r
~~
 
V    =  1.2936  ft3  , Reloads 4, 5 Substituting the    above values  in  Equation    4 yields the "B" factor relatiori-ships  for the different reloads:
"B" Factor    =    (1022.688) (ht)          2'ni tial  Core          Equation 5 "B" Factor    =    (1002.784) (ht)          Reloads 1, 2, 3          Equa,tion 6 "B" Factor    =    (1003.714) (b t)        Reloads 4, 5              Equation  7 The  folloving examples shov hov different values of "B" vere calculated for tvo different exposures of the same fuel (Reload 3):
      ~Ex osure                  ECCS  Anal sis Dr out Times          HAPLHGR 5000 7fVD/T                          1.48 sec                    10.68 25000 HVD/T                          1.59 sec                    9.92 Sunsti tuting the above dryout times        in  Equation  6 yields:
For 5000 IWD/T:
            "B" Factor    =  (1002.784) (ht)
            "B" Factor    =    1002.784lhr) (1.48 sec) 3600  sec/hr "B" Factor    =  0.412 For 25000 IWD/T:
            "B" Factor    =  (1002.784)    gt)
            "B" Factor    =  (1002.784/hr)      (1.59 sec) 3600  sec/hr "B" Factor    =  0.443
 
e~eeest:
Demonstrate how "B" values are calculated to assure conservatism when using the dryout times assumed in the ECCS analysis.
R~es   see As   indicated in the above response, nominal values were .used to calculate, the "B" factors. Converged HApLHGR limits and conservative axial power distributions were assumed for t'e dryout time, determinations. 'In addition, a conservative c4rrelation (G.E. compliance with 10CFR50, Appendix K criteria I.C.4:) was used which was previously approved by the Commission.
A "B" Factor Limiting Condition for Operation is not necessary to assure that actual dryout times are conservative. Dryout time is only one of many conservative inputs used to determine HAPL/EGR limits, the ultimate restriction of interest. Sensitivity analyses performed by our fuel supplier have determined that the parameters used to calculate dryout time (void fraction, axial power distributions) are conservative when compared to normal plant operation.
 
~ r~w y ~}}

Latest revision as of 09:26, 30 October 2019

Letter Regarding Responses to June 9, 1976 NRC Question
ML17037B543
Person / Time
Site: Nine Mile Point Constellation icon.png
Issue date: 08/03/1976
From: Schneider R
Niagara Mohawk Power Corp
To: Lear G
Office of Nuclear Reactor Regulation
References
Download: ML17037B543 (12)
v • d • e


Text

V.S. NUCLLAB flEGULATOBV COMMISSION DOCKET NUMBER fIIIC r:o>>M 195 w" r r ~

17 76I >In ~

50-220 FI' NVMOEB NRC DISTRIBUTION FOB,P, T GO DOCICET MATERIAL FROM: DATE OF DOCUMENT

'l 8/3/76 Mr. George 'Lear Niagara Mohawk Power Corp.

Syracuse, New York DATL= RECEIVE D ABETTER Mr, Rudolph R. Schneider 8/6/76 ONOTOB IZED PROP INPUT FORM NUMBER OF COPIES RECEIVED PjjjDB IOINAL PKVNCLASSIF I ED Q COP V One signed DESCRIPTION ENCLOSU RE Ltr, w/attached,;,re their 5/1'9/76 ltr, and our 6/9/76 ltr. ~ ~ .furnishing additional in information concerning Assembly Averaged Relationship .Tech Spec,- 'ower-Void ACKNOWLEDGED (5-P)'O

~

PLANT NAME:

Nine Mile Point gi NOT RziMOVZ .

SAFETY. FOR ACTION/INFORMATION ASSXGNED AD: ASSI NED DE BRANCH CHIEF: Lear i

PROJECT MIANAGER:

LXC ~ ASSTo: Parrish ~L PRO S

NA RE'C'X F'NTERNAL SYSTE 'IS SAFETY D IS1 Rl BUTION SITE SA ~

NRC PDR HE XNEIIAN ENV?.'RO AMASS~

X&E SCHROEDER ?r BENAROYA  ??i.NZm~~lf,aa OEI.D GOSSXCIC & STAFF ENGXNEERING IPPOLXTO ENV MIPC ifIACCARRY ~ KIRKICOOD CASE . KNIGHT IIANAUER SIHIPEIL OPERATItIG REACTORS JIARLES PAMLICKI PROJECT HAVAGFtIEN REACTOR SAFETZ OPERATXN r CI BOYD ROSS EISENHUT P COLLINS NOVAK SHAO HOUSTON ROSZTOCZY BAER PETERSON CHECK BUTLI R S E MELTZ GRIMES 11ELTEMES AT&X S KOVIIOLT SALTZMAN RUTBERG EXTERNAL DISTRIBUTION CONTROL NUMiBER LPDR: Oswe o N Y. Nl lT LAB W TXC: REGS VIE UL'RIKSON ORNL

.NS,I ASLB:

LA PDR CONSULTANTS 7F/B~

ACI<S CYS He&BBKI ~ ~

NBC Fof1M 166 (2 76)

N y

tY ~

N I

~ ~ 4 ~

N t ~

~ ~

NIAGARA MOHAWK POWER CORPORATION NIAGARA 300

~ MOHAWK ERIE BOULEVARD WEST SYRACUSE, H.Y. l3202 August 3, 1976 Director of Nuclear Reactor Regulation Attn: Mr. George Lear, Chief Operating Reactors Branch III3 U. S. Nuclear Regulatory Commission Washington, D. C. 20555 Re: Nine Mile Point Unit 1 Docket No. 50-220 DPR-63

Dear Mr. Lear:

Our letter of'ay 19, 1976 transmitted proposed changes to the Assembly Averaged Power-Void Relationship Technical Specification for Nine Mile Point Unit 1. 1'our letter of June 9, 1976 requested additional information regarding that'roposed change. The attached responses address the questions contained in your letter.

Sincerely, NIAGARA MOHAWK POWER CORPORATION Rudolph . Schnei der, peg(P~o po Vice President Electric Operations S. gang P Attachment

' ~

<5 il

't K 'i

c RESPOND. S TO JUNE 9, l976 NRC QUESTION NINE HILE POINT UNIT 1 Docket No. 50-220 DPR-63 RecCuest Provide a quanti tative explanation of'ow exposure dependent "B" values are calculated. Include examples which show how different values of "B" were calculated for two different exposures of the same fuel. The examples should show (1) the relationships (equations) assumed, and (2) the source and numerical values of all terms in the relationship for:

1. maximum Average Planar Linear Heat= Generation Rate (EQPLHGR) and Average Heat Generation Rate (q) (i.e., assumed peaking factors) .
2. Dryout Time. (i.e., h,g'n'"h., flow, average density, q).
3. "B" values (i.e., void fraction, peaking factor, power).

R~es ense The duration of nucleate boiling for non-jet pump plant ECCS analyses has been determined using the correlation (Equation 1, below) described in "General Electric Compliance with 10CFR50 Appendix K-Acceptance Criteria I.C.4." That correlation shows the time to boiling transition (dryout time) is a function exclusively of liquid volume fraction and power input to the bundle. Converged HAPLHGR limits and conservative axial power distributions were assumed for the dryout time determinations.

Both HAPLHGR limits and dryout times are exposure dependent. The following development shows how "B" values are calculated.

(0 ~ 31) (Pf) (hf ) Equation 1 gt II ht = time to transition boiling, hr.

3 p = saturated liquid density, ibm/ft h

enthalpy of'aporization, BTU/ibm fg gist V (1--a)

(~

/

q = Powor generation in bundle, BTU/hr = (PF) (FCP) (ABTU)

PF = bundle radial power factor FCP ~ fractional core power relative to 1850 Hh'BTU

= average bundle output at 1850 Hft, BTU/hr V = active coolant volume, ft3

a. = void fraction Therefore ht ='0.31) (P ) (hf ) (V) (1 - a.)

Equation 2 (ABTU) (PF) (FCP)

"B" Factor = (1 i

a.)

Equation 3 ~

(PF) (FCP) t Limiting this "B" factor relatioriship will assure that local power void values will not result in dr@out times shorter than those used.

in the ECCS Analysis.

Using Equation 2:

"B" Factor = (ABTU) Qt) Equation 4 (0.31) (P f) (hffg) (V)

Assumed nominal values are:

7 ABTU = 1.1869 x 10 BTU/hr pf ~ 45.977 ibm/ft3 hffg = 641 . 36 BTU/1 bm V ~ 1.2696 ft, Znitial Core V = 1.2948 ft3 , Reloads 1, 2, 3

r

~~

V = 1.2936 ft3 , Reloads 4, 5 Substituting the above values in Equation 4 yields the "B" factor relatiori-ships for the different reloads:

"B" Factor = (1022.688) (ht) 2'ni tial Core Equation 5 "B" Factor = (1002.784) (ht) Reloads 1, 2, 3 Equa,tion 6 "B" Factor = (1003.714) (b t) Reloads 4, 5 Equation 7 The folloving examples shov hov different values of "B" vere calculated for tvo different exposures of the same fuel (Reload 3):

~Ex osure ECCS Anal sis Dr out Times HAPLHGR 5000 7fVD/T 1.48 sec 10.68 25000 HVD/T 1.59 sec 9.92 Sunsti tuting the above dryout times in Equation 6 yields:

For 5000 IWD/T:

"B" Factor = (1002.784) (ht)

"B" Factor = 1002.784lhr) (1.48 sec) 3600 sec/hr "B" Factor = 0.412 For 25000 IWD/T:

"B" Factor = (1002.784) gt)

"B" Factor = (1002.784/hr) (1.59 sec) 3600 sec/hr "B" Factor = 0.443

e~eeest:

Demonstrate how "B" values are calculated to assure conservatism when using the dryout times assumed in the ECCS analysis.

R~es see As indicated in the above response, nominal values were .used to calculate, the "B" factors. Converged HApLHGR limits and conservative axial power distributions were assumed for t'e dryout time, determinations. 'In addition, a conservative c4rrelation (G.E. compliance with 10CFR50, Appendix K criteria I.C.4:) was used which was previously approved by the Commission.

A "B" Factor Limiting Condition for Operation is not necessary to assure that actual dryout times are conservative. Dryout time is only one of many conservative inputs used to determine HAPL/EGR limits, the ultimate restriction of interest. Sensitivity analyses performed by our fuel supplier have determined that the parameters used to calculate dryout time (void fraction, axial power distributions) are conservative when compared to normal plant operation.

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