ML20195E229

Responds to Generic Ltr 88-11, NRC Position on Radiation Embrittlement of Reactor Vessel Matls & Its Impact on Plant Operations

ML20195E229
Person / Time
Site:	Prairie Island
Issue date:	10/28/1988
From:	Musolf D NORTHERN STATES POWER CO.
To:	NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM)
References
GL-88-11, NUDOCS 8811070304
Download: ML20195E229 (3)

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c Northem States S.,y Company 414 Neollet Malt M,nneapohs, Minnesota 55401.W27 Telephone (612) 330-5500 October 28, 1988 Generic Letter 8811 Director of Nuclear Reactor Regulation U S Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555 PRAIRIE IS1AND NUCLEAR GENF. RATING PIANT Docket Nos. 50 282 License Nos. DPR 42 50 306 DPR 60 Response to Generic letter 88 11 0-netic Letter 88 11. "NRC Position on Radiation Embrittlement of Reactor Vestsl Materials and Its Impact on Plant Operations", requested that li-cense,,a use the methods described in Revision 0, to Regulatory Guide 1.99, "Radiation Embrittlement of Reactor Vessel Materials", to predict the ef-feet of neutron radiation on reactor vessel materials and to provide the Commission with the results of their technical anal' sis and any required actions.

In response to that request, revised pressure tertperature limits for Prairie Island Units 1 and 2 have been calculated by Westinghouse utili:ing the methods described in Revision 2 to Regulatory Guide 1.99.

A cortparison of the revised and existing pressure tereperature limita (attached) shows that for Prairie Island the revised limits, based on Revision 2 to Regula-tory Guide 1.99, are no more restrictive than the existing limits, which are based on Revision 1 to Regulatory Guide 1.99.

As a result, i m,il e tt e n t a -

tion of the revised pressure tertperature limits will not require any major changes to plant equipment, procedures or operations.

A license amendaent request will be submitted by Decen.ber 31, 1988 to in-corporate the revised pressure tersperature limits into the Prairie Island Technical Specifications. Any required changes to plant procedures or to the Low Tertperature Overpressure Protection System setpoints and enable temperatures will be irrplemented following approval of the license amend-rre nt.

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8811070304 001028 l

PDR ADOCK 05000282

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Direetor of NRR North < n States Power Company October 28, 1988 Page 2 i

Please contact us if you have an) quoetiens related to our re:ponse to Ceneric Letter 88 11.

i D M Now.

t David Musolf Manager Nuclear Support Services e

c: Regional Administrator III, NRC NRR Project Manager, NRC Senior Resident Inspector, NRC C Charnoff Attachment i

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e Direc\\or of NRR October 28. 1988 Att,achment Heat Up Curve Comparison Reg. Guide 199 Rev 1 ss. Rev 2 (First 15 FFPY of Operatl0n)

Indicated RCO Pressure (Pole)

I r /

3260 t /-

2000

/_.

t

,,,0 11 1800 l'l Itto 1000 740 800 l

250 0

0 60 100 160 200 250 300 360 400 480 600 indicated ACS Flwid Torperstwee (D00 FI

- Ro te. Re 1 -- Ro sie Rev.

Cooldown Curve Comparison L

Re9. Guide 199 Rev i vs. Rev 2 (First 15 EFPY of Operation)

Indicated RCS Preteure (Psit) 2$00

$1 l l

2250 11/-

2000

/ --

r 1780 i

lit 1800 4

Y 91,,n 1250

//

1000

-f

//

jj IrhIi1 250 0

0 80 100 140 200 250 300 350 400 480 500 Indicated RCS Flud Temperstwto (Des F) l

- RO 199 Rev.1

-*- RO 19 9 Rev.

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