ML20151T404

From kanterella
Jump to navigation Jump to search

Forwards Safety Evaluation Supporting Elimination of Postulated Primary Loop Pipe Ruptures from Design Basis for Facility,Per Util 851025 & 861031 leak-before-break Evaluations & WCAP-11699
ML20151T404
Person / Time
Site: Trojan File:Portland General Electric icon.png
Issue date: 08/05/1988
From: Chan T
Office of Nuclear Reactor Regulation
To: Cockfield D
PORTLAND GENERAL ELECTRIC CO.
Shared Package
ML20151T408 List:
References
TAC-06596, TAC-6596, NUDOCS 8808160351
Download: ML20151T404 (3)


Text

a August 5, 1988 Docket No. 50-344 Mr. David W. Cockfield Vice President, Nuclear Portland General Electric Company 121 S.W. Salmon Street Portland, Oregon 97204

Dear Mr. Cockfield:

SUBJECT:

ELIMINATION OF DYNAMIC EFFECTS OF POSTULATED PRIMARY LOOP PIPE RUPTURES FROM DESIGN BASIS FOR TROJAN NUCLEAR PLANT (TAC NO. M596)

By letters dated October 25, 1985 and October 31, 1986, Portland General Electric Company (PGE) submitted a "leak-before-break" (LBB) evaluation of the reactor coolant loop piping for the Trojan Nuclear Plant.

PGE proposed to apply the LBB methodology to eliminate the dynamic effects of postulated primary loop pipe ruptures from the design basis for Trojan,-as permitted by therevisedGeneralDesignCriterion4(GDC-4)ofAppendixAto10CFR50.

By letter dated March 14, 1988, PGE submitted the final technical basis for the elimination of primary loop pipe ruptures for Trojan in Westinghouse report WCAP-11699 in response to the staff's request for additional information.

We have reviewed your submittals and find the Trojan primary loop piping in compliance with the revised GDC-4. Thus, the dynamic effects of postulated primary loop pipe ruptures may be eliminated from the design basis of Trojan.

Our Safety Evaluation is enclosed.

Sincerely, original signed by Terence L. Chan, Project Manager Project Directorate V Division of Reactor Projects - III, IV, V and Special Projects

Enclosure:

As stated cc: w/ enclosure i

See next page i

DISTRIBUTION fDocketFileE TLChar "NRC T ldcal~PDRs OGC-Rockville g(q0[f PDS Reading EJordan GMHolahan BGrimes l

JLee ACRS (10) dr g

F g/(/88

$/$/88 8808160351 880805 ADOCK0500g4

- DR

p nov o

UNITED STATES g

8 NUCLEAR REGULATORY COMMISSION o

'h WASHINGTON, D. C. 20555

+#

,y,,

August 5, 1988 Docket No. 50-344 Mr. David W. Cockfield Vice President, Nuclear Portland General Electric Company 121 S.W. Salmon Street Portland, Oregon 97204

Dear Mr. Cockfield:

SUBJECT:

ELIMINATION OF DYNAMIC EFFECTS OF POSTULATED PRIMARY LOOP PIPE RUPTURES FROM DESIGN BASIS FOR TROJAN NUCLEAR PLANT (TAC NO. 06596)

By letters dated October 25, 1985 and October 31,1986,(PortlandGeneralLBB) evaluation of Electric Company (PGE) submitted a "leak-before-break" the reactor coolant loop piping for the Trojan Nuclear Plant.

PGE proposed to apply the LBB methodology to eliminate the dynamic effects of postulated primary loop pipe ruptures from the design basis for Trojan, as permitted by the revised General Design Criterion 4 (GDC-4) of Appendix A to 10 CFR 50.

By letter dated March 14, 1988, PGE submitted the final technical basis for the elimination of primary loop pipe ruptures for Trojan in Westinghouse report WCAP-11699 in response to the staff's request for additional information.

We have reviewed your submittals and find the Trojan primary loop piping in compliance with the revised GDC-4.

Thus, the dynamic effects of postulated primary loop pipe ruptures may be eliminated from the design basis of Trojan.

Our Safety Evaluation is enclosed.

Sinc el,

erence L. Chan, Project Manager

~

roject Directorate V Division of Reactor Projects - III, IV, V and Special Projects

Enclosure:

As stated cc: w/ enclosure See next page i

i' Mr. David W. Cockfield Portland General Electric Company Trojan Nuclear Plant cc:

Senior Resident Inspector U.S. Nuclear Regulatory Commission

-Trojan Nuclear Plant Post Office Box 0 Rainier, Oregon 97048 Mr. Michael J. Sykes, Chairman Board of County Commissioners Columbia County St. Helens, Oregon 97501 Mr. William T. Dixon Oregon Department of Energy Salem, Oregon 97310 Regional Administrator, Region V U.S. Nuclear Regulatory Commission 1450 Maria Lane, Suite 210 Walnut Creek, California 94596 1

l 4

i

.