ML20235V989: Difference between revisions

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| document type = CORRESPONDENCE-LETTERS, NRC TO UTILITY, OUTGOING CORRESPONDENCE
| document type = CORRESPONDENCE-LETTERS, NRC TO UTILITY, OUTGOING CORRESPONDENCE
| page count = 4
| page count = 4
| project = TAC:63577, TAC:63578
| stage = RAI
}}
}}


=Text=
=Text=
{{#Wiki_filter:i
{{#Wiki_filter:i
  ,$1                                   July 17,1987 s,
,$1 July 17,1987 s,
Docket Nos. 50-338                             DISTRIBUTION and 50-339                           dDocketJile? OGC-Bethesda NRC PDR         E. Jordan Local PDR       J. Partlow PD22 Rdg.       ACRS (10)
Docket Nos. 50-338 DISTRIBUTION and 50-339 dDocketJile? OGC-Bethesda NRC PDR E. Jordan Local PDR J. Partlow PD22 Rdg.
Mr. W. L. Stewart                               S. Varga       Gray File Vice President - Nuclear Operations             G. Lainas Virginia Electric and Power Company             D. Miller Post Office Box 26666                           L. Engle                         j Richmond, Virginia 23261                                                         !
ACRS (10)
Mr. W. L. Stewart S. Varga Gray File Vice President - Nuclear Operations G. Lainas Virginia Electric and Power Company D. Miller Post Office Box 26666 L. Engle j
Richmond, Virginia 23261


==Dear Mr. Stewart:==
==Dear Mr. Stewart:==
 
1
1 I


==SUBJECT:==
==SUBJECT:==
REQUEST FOR ADDITIONAL INFORMATION ON ELIMINATION OF DYNAMIC EFFECTS 0F POSTULATED PRIMARY LOOP PIPE RUPTURES FROM DESIGN BASIS FOR NORTH ANNA POWER STATION UNITS 1 AND 2 (NA-1&2) (TAC NOS. 63577 AND 63578)
REQUEST FOR ADDITIONAL INFORMATION ON ELIMINATION OF DYNAMIC EFFECTS 0F POSTULATED PRIMARY LOOP PIPE RUPTURES FROM DESIGN BASIS FOR NORTH ANNA POWER STATION UNITS 1 AND 2 (NA-1&2) (TAC NOS. 63577 AND 63578)
By letter dated November 6, 1986, Virginia Electric and Power Company (VEPC0)   ,
By {{letter dated|date=November 6, 1986|text=letter dated November 6, 1986}}, Virginia Electric and Power Company (VEPC0) requested an amendment to Facility Operating License Nos. NPF-4 and NPF-7
requested an amendment to Facility Operating License Nos. NPF-4 and NPF-7       {
{
for NA-182, respectively. The proposed amendment would permit the redesign       ;
for NA-182, respectively. The proposed amendment would permit the redesign of the reactor coolant pump and steam generator supports, because the dynamic i
of the reactor coolant pump and steam generator supports, because the dynamic   i effects of postulated primary loop pipe ruptures would be eliminated from the   !
effects of postulated primary loop pipe ruptures would be eliminated from the design basis using " leak-before-break" technology as permitted by the revised General Design Criterion 4 (GDC-4) of Appendix A,10 CFR 50.
design basis using " leak-before-break" technology as permitted by the revised   l General Design Criterion 4 (GDC-4) of Appendix A,10 CFR 50.                     '
VEPC0 submitted the technical basis for the elimination of primary loop pipe ruptures for NA-1&2 in report WCAP-11163. The staff has reviewed the licensee's submittal for compliance with the revised GDC-4. The staff has prepared the i
VEPC0 submitted the technical basis for the elimination of primary loop pipe ruptures for NA-1&2 in report WCAP-11163. The staff has reviewed the licensee's ,
enclosed request for additional information and is also available to discuss this request with VEPCO.
submittal for compliance with the revised GDC-4. The staff has prepared the     i enclosed request for additional information and is also available to discuss this request with VEPCO.                                                         1 The reporting and/or recordkeeping requirements of this letter affect fewer     !
1 The reporting and/or recordkeeping requirements of this letter affect fewer than 10 respondents; therefore, OMB clearance is not required under P.L. 96-511.
than 10 respondents; therefore, OMB clearance is not required under P.L. 96-511.
Sincerely, Leon B. Engle, Project Manager l
Sincerely, Leon B. Engle, Project Manager       l Project Directorate II-2 Division of Reactor Projects-I/II
Project Directorate II-2 Division of Reactor Projects-I/II


==Enclosure:==
==Enclosure:==
As stated cc: See next page
As stated cc: See next page x
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2 Df DMp/87 L n91e1hc LRube steia ler 7/ g 7/ly/87 7/q/87 87072303B4 h oo33s PDR ADOCK PDR P


R Mr. W. L. Stewart                     North Anna Power Station l     Virginia Electric & Power Company     Units 1 and 2 cc:
R Mr. W. L. Stewart North Anna Power Station l
Richard M. Foster, Esq.               Atomic Safety and Licensing Appeal Cockrell, Quinn & Creighton               Board Panel 516 Cherry Tower                       U.S. Nuclear Regulatory Commission 920 South Cherry Street               Washington, DC 20555 i     Denver, Colorado 80222 l                                             Regional Administrator, Region II l
Virginia Electric & Power Company Units 1 and 2 cc:
Michael W. Maupin, Esq.               U.S. Nuclear Regulatory Commission Hunton, Williams, Gay and Gibson       Office of Executive Director P. O. Box 1535                           for Operations R}rhmond, Virginia 23212               101 Marietta Street N.W., Suite 2900 Atlanta, Georgia 30323 Mr. W. T. Lough Virginia Corporation Commission       Mr. E. W. Harrell Division of Energy Regulation         P. O. Box 402 P.~0. Box 1197                         Mineral, Virginia 23117 Richmond, Virginia 23209 Old Dominion Electric Cooperative Ellyn R. We iss, Esq.                 c/o Executive Vice President Harmon, Weiss and Jordan               Innsbrook Corporate Center 2001 S Street NW                       4222 Cox Road, Suite 102 Washington, DC 20009                   Glen Allen, Virginia 23060 Mr.' J. T. Rhodes                     Mr. William C. Porter, Jr.
Richard M. Foster, Esq.
Senior Vice President - Power Ops. County Administrator Virginia Electric and Power Co.       Louisa County Post Office Box 26666                 P. O. Box 160 Richmond, Virginia 23261               Louisa, Virginia 23093 Mr. Patrick A. O' Hare                 James B. Kenley, M.D., Commissioner Office of the Attorney General         Department of Health Supreme Court Building                 109 Governor Street 101 North 8th Street                   Richmond, Virginia 23219 l     Richmond, Virginia 23219 Resident Inspector / North Anna c/o U.S. NRC Senior Resident Inspector Route 2, Box 78 Mineral, Virginia 23117
Atomic Safety and Licensing Appeal Cockrell, Quinn & Creighton Board Panel 516 Cherry Tower U.S. Nuclear Regulatory Commission 920 South Cherry Street Washington, DC 20555 i
                                                                                    )
Denver, Colorado 80222 l
Regional Administrator, Region II l
Michael W. Maupin, Esq.
U.S. Nuclear Regulatory Commission Hunton, Williams, Gay and Gibson Office of Executive Director P. O. Box 1535 for Operations R}rhmond, Virginia 23212 101 Marietta Street N.W., Suite 2900 Atlanta, Georgia 30323 Mr. W. T. Lough Virginia Corporation Commission Mr. E. W. Harrell Division of Energy Regulation P. O. Box 402 P.~0. Box 1197 Mineral, Virginia 23117 Richmond, Virginia 23209 Old Dominion Electric Cooperative Ellyn R. W iss, Esq.
c/o Executive Vice President e
Harmon, Weiss and Jordan Innsbrook Corporate Center 2001 S Street NW 4222 Cox Road, Suite 102 Washington, DC 20009 Glen Allen, Virginia 23060 Mr.' J. T. Rhodes Mr. William C. Porter, Jr.
Senior Vice President - Power Ops.
County Administrator Virginia Electric and Power Co.
Louisa County Post Office Box 26666 P. O. Box 160 Richmond, Virginia 23261 Louisa, Virginia 23093 Mr. Patrick A. O' Hare James B. Kenley, M.D., Commissioner Office of the Attorney General Department of Health Supreme Court Building 109 Governor Street 101 North 8th Street Richmond, Virginia 23219 l
Richmond, Virginia 23219 Resident Inspector / North Anna c/o U.S. NRC Senior Resident Inspector Route 2, Box 78 Mineral, Virginia 23117
)
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ENCLOSURE
ENCLOSURE 3
                                                                                                              "    3                l'
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                              >q.                                                                                                     ,    e
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                                              -(. REQUEST FOR ADDIT 10NAL INFORMATION
REQUEST FOR ADDIT 10NAL INFORMATION e
                                    -+-                                                                                                 u                   .
-(.
y 4                         ON Ell.vlNATION t          OF POSTULATED PRIMARY LOOP PIPE RUPTURES                                                     I
-+-
((                                   ;''                AS A DESIGN BASIS
u y
                                                                                                                      +
4 ON Ell.vlNATION OF POSTULATED PRIMARY LOOP PIPE RUPTURES I
                    ,.                                VIRGINIA ELECTRIC AND POWER COMPANY                     ,                                          )
t
              ,            ,'                        NORTH ANNrl S WER STATION UNITS 1 AND 2                 L DOCKET WOS. 50-338 & 50-339
((
                                                                      '1<
AS A DESIGN BASIS
                                                                                                                        .g ~
+
1
VIRGINIA ELECTRIC AND POWER COMPANY
                                                                                            *              -%*s             O          ,y j
)
NORTH ANNrl S WER STATION UNITS 1 AND 2 L
DOCKET WOS. 50-338 & 50-339
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    )                 (1) The primary loop piping and fittings were fabricated from cast stainless
)
    }r steel. Describe whether the piping and fittings are centrifugal % cast 1 stainless steel or statically cast stainless steel.. Also, identM                                    the f                < ( welding process of the primary loop and indicate 11'solutiok annes) ling
(1) The primary loop piping and fittings were fabricated from cast stainless
                                                                                                    ''            M
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      ;                        was performed.                                                                                                               ,
steel. Describe whether the piping and fittings are centrifugal % cast
5                 (2) The material properties were presented.in Tables 3-I t$$ough@3 in n.
< ( welding process of the primary loop and indicate 11'solutiok annes) ling
g WCAP-11163. Describetwhether the propertfes are plant specific dataf* rom certified material test reports (CMTRs) cir Section III Code-minimut                                                       I
, 1 stainless steel or statically cast stainless steel.. Also, identM the rf M
                              ' values at joom temperature or operatirg timperdture. Provide the dlastic                                                   I modulus, yield strength, ultimate strengtd,VapC thuss-strain curve at                                                     f the lietting locatiBn v)d at the operading tes,perature.     '
was performed.
5 (2) The material properties were presented.in Tables 3-I t$$ough@3 in n.
g WCAP-11163. Describetwhether the propertfes are plant specific dataf* rom certified material test reports (CMTRs) cir Section III Code-minimut I
' values at joom temperature or operatirg timperdture. Provide the dlastic I
modulus, yield strength, ultimate strengtd,VapC thuss-strain curve at f
the lietting locatiBn v)d at the operading tes,perature.
n
n
                                              ,y                         ,    r n               %            f (3) It appeari'thth the'same strdrs-strain" relationship was use&in the fracture stability and. leakage calculations._The licensee should use the                                                 i lower-bound stress-strain relationship for the stability _ evaluation and
,y r n f
* the derage st(ess-strain relationship for the leakage evaluation, sy       -
(3) It appeari'thth the'same strdrs-strain" relationship was use&in the fracture stability and. leakage calculations._The licensee should use the i
                                                                                                                                                          )
lower-bound stress-strain relationship for the stability _ evaluation and the derage st(ess-strain relationship for the leakage evaluation, sy
was used for the fracture                                          i (4)Lberelasticfracturemechanics(LEFM)diculated"J"gp",itap
)
                        ^
(4)Lberelasticfracturemechanics(LEFM)diculated"J"gp",itap was used for the fracture i
                              ' stability (N hsis. However, from the e the associated Irwin plane-stress plastic zone tizes e not small       a j
' stability (N hsis. However, from the e j
i compared with the half-crack length "a". The licensee should use                                                     s       !
a the associated Irwin plane-stress plastic zone tizes e not small i
r            elastic-plastic fracture mechanics instead of LEFM procedures.
^
                  . (5) Limit load analysis was used to estimate the size of a stable crack.
compared with the half-crack length "a".
                              /However IMit lord analysis does not account for material toughness h mitations. In particular, low toughness themally-aged cast stainless                                                     ,
The licensee should use s
steel is involved in the present evaluation. The licensee should use a                                                 '
elastic-plastic fracture mechanics instead of LEFM procedures.
fracture stabilityJanalysis which accounts for material toughness.
r
                                                    ,. o (6)Lo$t critical and toughnt;ss critical locations were discussed. However, the leak-before break (LBB) evaluation margins should be demonstrated for l     the limiting lo"stion having the least fannble combinati6n of strcss<
. (5) Limit load analysis was used to estimate the size of a stable crack.
y,       ?
/However IMit lord analysis does not account for material toughness h mitations.
t.
In particular, low toughness themally-aged cast stainless steel is involved in the present evaluation. The licensee should use a fracture stabilityJanalysis which accounts for material toughness.
                                                                                      ,                                            c               l
(6)Lo$t critical and toughnt;ss critical locations were discussed. However, o
                                                        &y.
the leak-before break (LBB) evaluation margins should be demonstrated for l
s                                   .
the limiting lo"stion having the least fannble combinati6n of strcss<
i
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y, t.
c l
&y.
s i


l                                                                   I 1
l I 1
l and material properties. The limiting location may be defined from a fracture stability evaluation of the load critical and toughness critical locations. Since the primary loop piping is of a similar size, the location with the smallest stable crack size (independent of leakage) is the limiting location for LBB evaluations.
l and material properties. The limiting location may be defined from a fracture stability evaluation of the load critical and toughness critical locations. Since the primary loop piping is of a similar size, the location with the smallest stable crack size (independent of leakage) is the limiting location for LBB evaluations.
(7) The limiting location as discussed in item (6) above should be evaluated to demonstrate that the LBB margins are satisfied. Specifically, the margins are 10 on the leakage rate, 2 on the crack size, and 1.4 on the applied load, as discussed in detail in NUREG-1061, Volume 3. (Note that in the submittal, the licensee did not discuss the margin of 1.4 on the applied load. The licensee should include this margin of 1.4 on the appliedloadintheLBBevaluations.)
(7) The limiting location as discussed in item (6) above should be evaluated to demonstrate that the LBB margins are satisfied. Specifically, the margins are 10 on the leakage rate, 2 on the crack size, and 1.4 on the applied load, as discussed in detail in NUREG-1061, Volume 3.
(Note that in the submittal, the licensee did not discuss the margin of 1.4 on the applied load. The licensee should include this margin of 1.4 on the appliedloadintheLBBevaluations.)
4 1
4 1
i
i
    - - _ - _ - _          _ _ _ _ - _ _ - _ _ _ _ _ _ _ _ _ _ _ _}}
_ _ _ _ - _ _ - _ _ _ _ _ _ _ _ _ _ _ _}}

Latest revision as of 03:49, 3 December 2024

Forwards Request for Addl Info on Elimination of Postulated Primary Loop Pipe Ruptures as Design Basis,Per Util 861106 Request for Amends to Licenses NPF-4 & NPF-7.Identify Welding Process of Primary Loop & If Annealing Performed
ML20235V989
Person / Time
Site: North Anna  Dominion icon.png
Issue date: 07/17/1987
From: Engle L
Office of Nuclear Reactor Regulation
To: Stewart W
VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
References
TAC-63577, TAC-63578, NUDOCS 8707230384
Download: ML20235V989 (4)
v • d • e


Text

i

,$1 July 17,1987 s,

Docket Nos. 50-338 DISTRIBUTION and 50-339 dDocketJile? OGC-Bethesda NRC PDR E. Jordan Local PDR J. Partlow PD22 Rdg.

ACRS (10)

Mr. W. L. Stewart S. Varga Gray File Vice President - Nuclear Operations G. Lainas Virginia Electric and Power Company D. Miller Post Office Box 26666 L. Engle j

Richmond, Virginia 23261

Dear Mr. Stewart:

1

SUBJECT:

REQUEST FOR ADDITIONAL INFORMATION ON ELIMINATION OF DYNAMIC EFFECTS 0F POSTULATED PRIMARY LOOP PIPE RUPTURES FROM DESIGN BASIS FOR NORTH ANNA POWER STATION UNITS 1 AND 2 (NA-1&2) (TAC NOS. 63577 AND 63578)

By letter dated November 6, 1986, Virginia Electric and Power Company (VEPC0) requested an amendment to Facility Operating License Nos. NPF-4 and NPF-7

{

for NA-182, respectively. The proposed amendment would permit the redesign of the reactor coolant pump and steam generator supports, because the dynamic i

effects of postulated primary loop pipe ruptures would be eliminated from the design basis using " leak-before-break" technology as permitted by the revised General Design Criterion 4 (GDC-4) of Appendix A,10 CFR 50.

VEPC0 submitted the technical basis for the elimination of primary loop pipe ruptures for NA-1&2 in report WCAP-11163. The staff has reviewed the licensee's submittal for compliance with the revised GDC-4. The staff has prepared the i

enclosed request for additional information and is also available to discuss this request with VEPCO.

1 The reporting and/or recordkeeping requirements of this letter affect fewer than 10 respondents; therefore, OMB clearance is not required under P.L.96-511.

Sincerely, Leon B. Engle, Project Manager l

Project Directorate II-2 Division of Reactor Projects-I/II

Enclosure:

As stated cc: See next page x

.O LAgtW P,

2 Df DMp/87 L n91e1hc LRube steia ler 7/ g 7/ly/87 7/q/87 87072303B4 h oo33s PDR ADOCK PDR P

R Mr. W. L. Stewart North Anna Power Station l

Virginia Electric & Power Company Units 1 and 2 cc:

Richard M. Foster, Esq.

Atomic Safety and Licensing Appeal Cockrell, Quinn & Creighton Board Panel 516 Cherry Tower U.S. Nuclear Regulatory Commission 920 South Cherry Street Washington, DC 20555 i

Denver, Colorado 80222 l

Regional Administrator, Region II l

Michael W. Maupin, Esq.

U.S. Nuclear Regulatory Commission Hunton, Williams, Gay and Gibson Office of Executive Director P. O. Box 1535 for Operations R}rhmond, Virginia 23212 101 Marietta Street N.W., Suite 2900 Atlanta, Georgia 30323 Mr. W. T. Lough Virginia Corporation Commission Mr. E. W. Harrell Division of Energy Regulation P. O. Box 402 P.~0. Box 1197 Mineral, Virginia 23117 Richmond, Virginia 23209 Old Dominion Electric Cooperative Ellyn R. W iss, Esq.

c/o Executive Vice President e

Harmon, Weiss and Jordan Innsbrook Corporate Center 2001 S Street NW 4222 Cox Road, Suite 102 Washington, DC 20009 Glen Allen, Virginia 23060 Mr.' J. T. Rhodes Mr. William C. Porter, Jr.

Senior Vice President - Power Ops.

County Administrator Virginia Electric and Power Co.

Louisa County Post Office Box 26666 P. O. Box 160 Richmond, Virginia 23261 Louisa, Virginia 23093 Mr. Patrick A. O' Hare James B. Kenley, M.D., Commissioner Office of the Attorney General Department of Health Supreme Court Building 109 Governor Street 101 North 8th Street Richmond, Virginia 23219 l

Richmond, Virginia 23219 Resident Inspector / North Anna c/o U.S. NRC Senior Resident Inspector Route 2, Box 78 Mineral, Virginia 23117

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ENCLOSURE 3

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REQUEST FOR ADDIT 10NAL INFORMATION e

-(.

-+-

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4 ON Ell.vlNATION OF POSTULATED PRIMARY LOOP PIPE RUPTURES I

t

((

AS A DESIGN BASIS

+

VIRGINIA ELECTRIC AND POWER COMPANY

)

NORTH ANNrl S WER STATION UNITS 1 AND 2 L

DOCKET WOS. 50-338 & 50-339

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.g 1

~

O

,y

  • s j

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(1) The primary loop piping and fittings were fabricated from cast stainless

}

steel. Describe whether the piping and fittings are centrifugal % cast

< ( welding process of the primary loop and indicate 11'solutiok annes) ling

, 1 stainless steel or statically cast stainless steel.. Also, identM the rf M

was performed.

5 (2) The material properties were presented.in Tables 3-I t$$ough@3 in n.

g WCAP-11163. Describetwhether the propertfes are plant specific dataf* rom certified material test reports (CMTRs) cir Section III Code-minimut I

' values at joom temperature or operatirg timperdture. Provide the dlastic I

modulus, yield strength, ultimate strengtd,VapC thuss-strain curve at f

the lietting locatiBn v)d at the operading tes,perature.

n

,y r n f

(3) It appeari'thth the'same strdrs-strain" relationship was use&in the fracture stability and. leakage calculations._The licensee should use the i

lower-bound stress-strain relationship for the stability _ evaluation and the derage st(ess-strain relationship for the leakage evaluation, sy

)

(4)Lberelasticfracturemechanics(LEFM)diculated"J"gp",itap was used for the fracture i

' stability (N hsis. However, from the e j

a the associated Irwin plane-stress plastic zone tizes e not small i

^

compared with the half-crack length "a".

The licensee should use s

elastic-plastic fracture mechanics instead of LEFM procedures.

r

. (5) Limit load analysis was used to estimate the size of a stable crack.

/However IMit lord analysis does not account for material toughness h mitations.

In particular, low toughness themally-aged cast stainless steel is involved in the present evaluation. The licensee should use a fracture stabilityJanalysis which accounts for material toughness.

(6)Lo$t critical and toughnt;ss critical locations were discussed. However, o

the leak-before break (LBB) evaluation margins should be demonstrated for l

the limiting lo"stion having the least fannble combinati6n of strcss<

?

y, t.

c l

&y.

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l and material properties. The limiting location may be defined from a fracture stability evaluation of the load critical and toughness critical locations. Since the primary loop piping is of a similar size, the location with the smallest stable crack size (independent of leakage) is the limiting location for LBB evaluations.

(7) The limiting location as discussed in item (6) above should be evaluated to demonstrate that the LBB margins are satisfied. Specifically, the margins are 10 on the leakage rate, 2 on the crack size, and 1.4 on the applied load, as discussed in detail in NUREG-1061, Volume 3.

(Note that in the submittal, the licensee did not discuss the margin of 1.4 on the applied load. The licensee should include this margin of 1.4 on the appliedloadintheLBBevaluations.)

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