ML20151P088

From kanterella
Jump to navigation Jump to search
Forwards Rev 2 to Mark I Long-Term Program Plant-Unique Analysis, Peach Bottom Units 2 & 3.Rept Covers Safety Relief Valve Discharge Lines & External Torus Attached Piping
ML20151P088
Person / Time
Site: Peach Bottom  Constellation icon.png
Issue date: 12/31/1985
From: Kemper J
PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC
To: Stolz J
Office of Nuclear Reactor Regulation
Shared Package
ML20151P092 List:
References
NUDOCS 8601030297
Download: ML20151P088 (2)


Text

- - _ -

( .

PHILADELPHIA Ei.ECTRIC COMPANY 2301 M ARKET STREET P.O. BOX 8699 PHILADELPHIA. PA.19101 (215)841 4502 JOHN S. KEMPER V IC E-PR E SI D E N T

. . . . . . . . . . . . . . . = ~

December 31, 1985 Mr. J. F. Stolz, Chief Docket Nos.: 50-277 Operating Reactors Branch No. 4 50-278 Division of Licensing U. S. Nuclear Regulatory Commission Washington, DC 20555

Subject:

Peach Bottom Atomic Power Station Units 2 6'3 Mark I Program - Torus Attached Piping i

References:

(1) Letter J. S. Kemper (PECo) to J. F. Stolz (NRC),

dated June 13, 1985 (2) Peach Bottom Atomic Power Station Units 2 & 3 Mark I Long Term Program, Plant Unique Analysis e Report, Revision 1, dated August, 1983 File: GOVT 1-1 (NRC)

Dear Mr. Stolz:

As described in the Reference (1) transmittal, we have completed our update of the Plant Unique Analysis Report (Reference (2)) which covers the safety relief valve discharge lines and the external torus attached piping. This update is contained in the attached addendum.

Also attached is a revised page 1-3/4 for Reference (2).

We have completed the as-built reconciliation (ABR) of the original scope modifications for both units, the evaluation of the valves in piping attached to the torus and the evaluation of the ECCS equipment nozzles and anchorages. Some additional modifications are required due to the ABR and the equipment nozzle evaluations. These modifications are in progress.

In addition, as a result of the ABR, we have concluded that some modifications will have to be made to the anchorages of the core spray pumps, residual heat removal (RHR) pumps and heat exchangers, and some of the valves in the torus attached piping. The high pressure coolant injection and the reactor core isolation cooling systems do not require modifications to their equipment (pumps and turbines) anchorages.

  • A
7

,} pl. 3 - (60)

t ,.

The conceptual modification designs for the valves and the ECCS equipment anchorages have been completed. These modifications include (1) additional tie-downs on the pumps between the base plates, pedestals, and floor (2) stiffening of structural support steel on the heat exchangers, and (3) bolt changes or stiffening plates on the valves.

We will be finalizing our designs and implementing the required modifications as soon as possible. We expect to complete all modifications by the end of the first quarter'of 1987 excluding any material delivery.and/or equipment availability problems.

We will notify your office when the remaining modifications have been completed.

Sincerely,

$$$f APB/pd12208507 Attachment 4

.-