ML19338D096

From kanterella
Jump to navigation Jump to search
Application to Amend License DPR-71 to Revise Tech Specs by Changing Temporary Spec Issued W/Amend 29 Re Safety Relief Valve Settings.Effective End Date of Spec Will Be Extended Until Completion of T-quencher Mod
ML19338D096
Person / Time
Site: Brunswick Duke Energy icon.png
Issue date: 09/15/1980
From: Utley E
CAROLINA POWER & LIGHT CO.
To:
Shared Package
ML19338D097 List:
References
NO-80-1330, NUDOCS 8009190425
Download: ML19338D096 (2)


Text

-

y V

( J *>

CD&L Carolina Power & Light Company September 15,-1980 FILE: NG-3514(B)

SERIAL NO:

NO-80-1330

Office of Nuclear' Reactor Regulation ATTENTION:

Mr. T. A. Ippolito, Chief

-Operating Reactors Branch No. 2 United States Nuclear Regulatory Commission Washington, D. C.

20555 BRUNSWICK STEAM ELECTRIC-PLANT, UNIT NO. 1 DOCKET NO. 50-325 LICENSE NO. DPR-71 REQUEST FOR LICENSE AMENDMENT SAFETY RELIEF VALVE SETPOINTS

Dear Mr. Ippolito:

In accordance with the Code of Federal Regulations, Title 10, Part 50.90 and..Part 2.101, Carolina Power & Light' Company (CP&L) hereby requests revisions to the Technical Specifications 'for its Brunswick Steam Electric Plant (BSEP)

Unit No. 1.

This change revises the temporary technical specification involving safety-relief valve (SRV) settings,. issued with Amendment 29, by extending the effective end-date of. this specification until the completion of the T-quencher

~

modification'rather than applying a specific end date. This change is being requested because of the changes in the BSEP outage. schedule. See CP&L letter from E. E. Utley to T. A. Ippolito dated September 2, 1980, Serial number NO-

'80-1273.

As stated in our supplement to LER l-79-107, which discussed damage to. an SRV' tail pipe, 'it was stated that installation of the T-quencher modification would eliminate the potential for.the. recurrence of an event similar to this type. As stated in.our letter of May 30,,1980, requesting the initial temporary

- change,:"There have -been no cases of simultaneous or near-simultaneous openings of safety-relief valve pairs with this large a differential in set point pressure."

. The ' conclusions reached.-by the NRC staff in the Safety Evaluation Reps t (SER)'~ to Amendment 29 did i 't tie the SRV setpoint temporary change to a specific.end date but did tie it to the completion of the T-quencher modifications, at which time it would be appropriate to delete the temporary cia:uge to Technical Specifications.

Based on the abmre we believe it is appropriate to retain the temporary

-specification until the completion'of the T-quencher modification.

411 FayetteviHe Street

  • P. O. Box 1551
  • Raleigh, N. C. 27602 E*;% m x 3W**?i"w " Tim 247355yW 1 M p m H E8 0 0 919 OM;-

A.

v

7 o

Mr. Ippolito Attached you will find the revised page number 3/4 4-4 with the changes indicated by a vertical line in the right hand column. We believe that this change is administrative in nature and enclose a check for $1,200.00 for a Class II amendment as per-10CFR 170.22.

Should you have any questions regarding this matter please contact my staff.

Yours very truly, k Q })pp a '

v

[

E. E. Utley Executive Vice President Power Supply and Engineering & Construction DCS/dk Attachment cc:

Mr. J. N. Hannon 1

Sworn to and subscribed before me this 15th day of September, 1980 l

1 Yvon d

h JJ e

Notary Public My commission expires:

October 4, 1981 5I OT ANY \\

5 s

5,

. P U B t. \\ C $ =b 1

I

)

1 L

. -