ML19249E516

Forwards Response to NUREG-0313, Technical Rept on Matl Selection & Processing Guidelines for BWR Coolant Pressure Boundary Piping, Re Unit 1.Response for Unit 2 Will Be Submitted by Jan 1979

ML19249E516
Person / Time
Site:	Grand Gulf
Issue date:	06/30/1978
From:	Mcgaughy J MISSISSIPPI POWER & LIGHT CO.
To:	Stolz J Office of Nuclear Reactor Regulation
References
RTR-NUREG-0313, RTR-NUREG-313 AECM-78-42, NUDOCS 7910010621
Download: ML19249E516 (3)

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p ooucnow occo ruc e June 30, 1978 U. S. Nuclear Regulatory Commission Light Water Reactors Branch No. 1 Division of Project Management Washington, D. C.

20555 Attention:

Mr. John F. Stolz, Chief

SUBJECT:

Grand Gulf Nuc1 car Station Units 1 & 2 Docket Mos. 50/416, 50/417 File 0260/15515/L-835.0/L-813.0 MP&L Position on NUREG-0313 Technical Report on bbterial Scicction and Processing Guidelines for BWR Coolant Pressure Boundary Piping AECM-78/42 As requested in your letter dated February 28, 1978, please find attached our response on NUREG-0313 " Technical Report on Material Selection and Process-ing Guidelines for BWR Coolant Pressure Boundary Piping." As requested our response addresses each subsection in Sections II and III of NUREG-0313.

This response pertains to Unit 1.

Our position on Unit II will be sub-mitted by January, 1979.

If you have any questions on the attached response, please let us know.

Yours truly, lY v

J. P. McGaughy, Jr.

Director of Power Production DRB/db Position on NUREG-0313 for (Grand Gulf Nuc1 car Station - Unit I)

Enclosure:

cc:

Mr. Robert McGehee Mr. Troy Conner Mr. N. L. Stampicy 781920019 l

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1032 Member Middle South Utilities System

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j Mississippi Power & Light Company Position on NUREG - 0313 for Grand Gulf tbclear Station - Unit 1 l

Section II II.1 stainless steel reactor coolant pressure boundary (RCPB) fittings for 2 inch and under sizes is of type 304L stainless steel RCPB piping and fittings greater than 2 inches in carbon content h.035 percent (i.e. type 304).

To the extent these piping spools (including piping, fittings, and shop supplied in the solution annealed condition.

ly 80 percent of the total number of piping spools greater es in size are in the solution annealed condition.

Field welds solution annealed.

1 II.2 4.dvanced s tage of cons truction of this Unit, solu tion annealment of pipe ends is impractical.

II.3 tion is not applicable.

Section III

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III.1 3dations of this subsection will be implemented as applicable.

II.2.A(1) idations of this subsection will be implemented for non-servict

.ncs.

II.2.A(2).a if Unit 1 leak detection system meets the position described in uide 1.45.

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' Subsection III.2.A.(2).b It is requested that the following limiting conditions for plant operation be implemented in lieu of the recommendations specified in this subsection:

With any increase in the rate of unidentified leakage in excess of 2gpm above a baseline leakage rate (to be determined during stsrtup) within a period of 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />, reduce the leakage rate below this limit or be in hot shutdown within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in cold shutdown within the next 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

When the total unidentified leakage attains a rate of Sgpm above the baseline leakage (to be determined during startup) reduce the leakage to less than the Sgpm limit within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> or be in hot shutdown within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in cold shutdown within the next 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

l The above limiting conditions for operation would allow a reasonabic amount of time for evaluation of the problem and implementation of corrcctive action.

Subsection III.2.A.(2).c The recomuendations of this subsection will be impicmented.

Subsection III.2.B.(1) l The recommendations of this subsection will be implemented.

Subsection III.2.B.(2)

This subsection is not applicable.

The recirculation system bypass piping I

as well as the " stub tubes" have been deleted.

In addition, the reactor core spray piping is carbon steel.

Subsection III.2.B.(3) i The recommendations of this subsection will be impicmented.

Subsection III.2.B. (41 The recomm' dations of this subsection will be implemented.

1032

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