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August 31, 1981
            ,                                                        EEUJ1!.0 CodRERONFENCF UNITED STATES OF AMERICA NUCLEAR ICGULATORY COMMISSION                                        @[
BEFORE THE ATOMIC SAFETY AND LICENSING BOARDU                                fI!          A<
lI          J
                                                                                                                                  'f '
In the Matter of                                                )                L'_    SEP 091981 m.              T
                                                                            )                  g( u.s."'"      m .%g            12 PENNSYLVANIA POWER & LIGHT COMPANY                              )                    'e
                                                                            )                      h                            f and                                          )    Docket Nos. 50
                                                                            )                  50-3        4          N ALLEGHENY ELECTRIC COOPERATIVE, INC.                            )
(Susquehanna Steam Electric Station,
                                                                            )
                                                                            )                      jfp
[                !.(N g
                                                                                                                                  's Units 1 and 2)                                                )
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3 11981 > :
APPLICANTS' STATEMENT OF MATERIAL FACTS cj?  .. civ.
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AS TO WHICH THERE IS NO GENUINE ISSUE                              /                      7 f
TO BE HEARD (CONTENTION 7C)                                        c)        cp Pursuant to 10 C.F.R. S 2.749(a) Applicants state, in support of their Motion for Summary Disposition of Contention 7C in this proceeding, that there i's no genuine issue to be heard with respect to the following material facts:
: 1. The BWR core spray system for the Susquehanna Steam Electric Station ("Susquehanna") consists of a number of distinct components: external piping; a transition between the piping and the vessel (the core spray safe end); a thermal sleeve; an internal core spray line; and the core spray sparger.                              The entire system is duplicated by means of a redundant and separate loop which contains the oame components.                          Affidavit of Joseph C. Lemaire in Support of Summary Disposition of Contention 7C ("Lemaire 7C Aff."),
para. 3.
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                                                                                    $ 3pj
 
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: 2. No cracking of core spray nozzles has ever been reported to General Electric Co. ("GE"), nor is GE aware of any such cracking. Cracking of these nozzles would not be expected in view of the relatively low cyclic thermal stresses in them and their successful overall performance throughout four hundred reactor years of service. Lemaire 7C Aff., para. 4.
: 3. Other portions of the core spray system have ex-perienced a low frequency of cracking in operating BWR's.
External core spray line cracking has occurred in BWR's using high carbon type 304 stainless steel.      The cracking in these cases was intergranular stress corrosion cracking (IGSCC).
Since Susquehanna uses carbon-limited stainless steel in the external core spray lines, cracking is not expected.      Id., para.
5.
: 4. Type 304 stainless steel core spray safe ends have also experienced IGSCC. In Susquehanna, Alloy 600 is used in the core spray safe ends and thermal sleeves, instead of type 304 stainless steel. Alloy 600 is more resistant to IGSCC and has never been reported to crack in core spray system safe ends or thermal sleeves of similar design. Id., para. 6.
: 5. IGSCC cracking has been verified in internal cora spray system piping of one operating reactor which utilized nigh carbon Type 304 stainless steel. Since the Susquehanna Units
;          utilize Type 304L stainless steel in the internal core spray line, cracking of internal core spray system piping is not expected. Id., para. 7.
: 6.                                                        Core spray sparger cracking has been reported in three operating reactors using higher carbon Type 304 stainless i
steel. Since the sparger cracking has not resulted in loose parts, NRC has approved continued operation of these reactors with spargers in this condition.                                                          The core spray spargers at Susquehanna are low carbon Type 304L stainless steel, which is known to resist the sensitization-related mechanism of                                                                  racking. Id.,
para. 8.
: 7.                                                        In summary, cracking has not been reported in BWR core sprav nozzles.                                                        Infrequent cracking has occurred in other portions of the core spray system, but only in materials substantially different from those used at 6usquehanna.                                                                      Id.,
para. 9.
Dated:  August 31, 1981.                                                                                                              ,
Respectfully submitted, SHAW, PIT'2 MAN , POTTS & TROWBRIDGE By          k                  /W M' #dq Jay E.- Silberg Matias F. Travieso-Diaz Counsel for Applicants 1800 M Street, N.W.
Washington, D.C. 20036 Telephone:          (202) 822-1000
_______ -_      -  -_- _}}

Latest revision as of 14:00, 28 January 2020

Statement of Matl Facts as to Which There Is No Genuine Issue to Be Heard Re Contention 7C.Related Correspondence
ML20010F443
Person / Time
Site: Susquehanna  Talen Energy icon.png
Issue date: 08/31/1981
From: Traviesodiaz
ALLEGHENY ELECTRIC COOPERATIVE, INC., PENNSYLVANIA POWER & LIGHT CO., SHAW, PITTMAN, POTTS & TROWBRIDGE
To:
Atomic Safety and Licensing Board Panel
References
NUDOCS 8109100202
Download: ML20010F443 (3)
v • d • e


Text

, -

August 31, 1981

, EEUJ1!.0 CodRERONFENCF UNITED STATES OF AMERICA NUCLEAR ICGULATORY COMMISSION @[

BEFORE THE ATOMIC SAFETY AND LICENSING BOARDU fI! A<

lI J

'f '

In the Matter of ) L'_ SEP 091981 m. T

) g( u.s."'" m .%g 12 PENNSYLVANIA POWER & LIGHT COMPANY ) 'e

) h f and ) Docket Nos. 50

) 50-3 4 N ALLEGHENY ELECTRIC COOPERATIVE, INC. )

(Susquehanna Steam Electric Station,

)

) jfp

[  !.(N g

's Units 1 and 2) )

I-

_ SEp h=\

3 11981 > :

APPLICANTS' STATEMENT OF MATERIAL FACTS cj? .. civ.

m . Uc.l , a['"4 (;;Hrj[

AS TO WHICH THERE IS NO GENUINE ISSUE / 7 f

TO BE HEARD (CONTENTION 7C) c) cp Pursuant to 10 C.F.R. S 2.749(a) Applicants state, in support of their Motion for Summary Disposition of Contention 7C in this proceeding, that there i's no genuine issue to be heard with respect to the following material facts:

1. The BWR core spray system for the Susquehanna Steam Electric Station ("Susquehanna") consists of a number of distinct components: external piping; a transition between the piping and the vessel (the core spray safe end); a thermal sleeve; an internal core spray line; and the core spray sparger. The entire system is duplicated by means of a redundant and separate loop which contains the oame components. Affidavit of Joseph C. Lemaire in Support of Summary Disposition of Contention 7C ("Lemaire 7C Aff."),

para. 3.

81091002O2 810831 gDRADOCK05000

$ 3pj

. o C

2. No cracking of core spray nozzles has ever been reported to General Electric Co. ("GE"), nor is GE aware of any such cracking. Cracking of these nozzles would not be expected in view of the relatively low cyclic thermal stresses in them and their successful overall performance throughout four hundred reactor years of service. Lemaire 7C Aff., para. 4.
3. Other portions of the core spray system have ex-perienced a low frequency of cracking in operating BWR's.

External core spray line cracking has occurred in BWR's using high carbon type 304 stainless steel. The cracking in these cases was intergranular stress corrosion cracking (IGSCC).

Since Susquehanna uses carbon-limited stainless steel in the external core spray lines, cracking is not expected. Id., para.

5.

4. Type 304 stainless steel core spray safe ends have also experienced IGSCC. In Susquehanna, Alloy 600 is used in the core spray safe ends and thermal sleeves, instead of type 304 stainless steel. Alloy 600 is more resistant to IGSCC and has never been reported to crack in core spray system safe ends or thermal sleeves of similar design. Id., para. 6.
5. IGSCC cracking has been verified in internal cora spray system piping of one operating reactor which utilized nigh carbon Type 304 stainless steel. Since the Susquehanna Units
utilize Type 304L stainless steel in the internal core spray line, cracking of internal core spray system piping is not expected. Id., para. 7.
6. Core spray sparger cracking has been reported in three operating reactors using higher carbon Type 304 stainless i

steel. Since the sparger cracking has not resulted in loose parts, NRC has approved continued operation of these reactors with spargers in this condition. The core spray spargers at Susquehanna are low carbon Type 304L stainless steel, which is known to resist the sensitization-related mechanism of racking. Id.,

para. 8.

7. In summary, cracking has not been reported in BWR core sprav nozzles. Infrequent cracking has occurred in other portions of the core spray system, but only in materials substantially different from those used at 6usquehanna. Id.,

para. 9.

Dated: August 31, 1981. ,

Respectfully submitted, SHAW, PIT'2 MAN , POTTS & TROWBRIDGE By k /W M' #dq Jay E.- Silberg Matias F. Travieso-Diaz Counsel for Applicants 1800 M Street, N.W.

Washington, D.C. 20036 Telephone: (202) 822-1000

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