Text

Amend 134 to License NPF-1,revising Tech Specs by Increasing Setpoint Tolerance for Pressurizer & Main Steam Safety Valves
	ML20238B008
Person / Time
Site:	Trojan File:Portland General Electric icon.png
Issue date:	09/01/1987
From:	Knighton G; Office of Nuclear Reactor Regulation
To:	;
Shared Package
ML20238A996	List: ML20238A992; ML20238B008; ML20238B018;
References
	NUDOCS 8709090505
	Download: ML20238B008 (8)
	v • d • e

_ _ _ _ _ _ _ - _ _ _ _ _ - - _ _ _ _

h, .. UNITED STATES L 1 -

n NUCLEAR REGULATORY COMMISSION r,, ,j WASHINGTON. D. C. 20666

"% /

PORTLAND GENERAL ELECTRIC COMPANY THE CITV 0F EUGENE,' OREGON PACIFIC POWER AND LIGHT COMPANY

_ DOCKET N0. 50-344 TROJAN NUCLEAR PLANT AMENDMENT TO FACILITY OPERATING LICENSE

,; ~ Amendment No.134 License No. NPF-1

'1. The Nuclear Regulatory Comission (the Commission) has found that:

A. . The application for amendment by Portland General Electric Company, et al.. (the licensee) dated February 11, 1987 complies with the st'aiidards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the.Comission's regulations set forth in 10 CFR Chapter I; B. The facility will operate in conformity with the application, the provisions of the Act, and the regulations of the Comission; C. There is reasonable assurance (i) that the activities authorized by this amendment. can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; D. The issuance of this amendment will not be inimical to the common I defense and security or to the health and safety of the public; and E. The issuance of this amendment 1s in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.

8709090505 070901 c PDR ADDCK 05000344:

P PDR

= _ _ _ _ _

- ___ _ _ -_ ._~

[

2.. Accordingly,.the' license is amended by changes to the Technical

.Specificat_ ions as. indicated in the attachment to this license

. amendment, and paragraph 2.C.(2) of Facility.0perating License No. NPF-1.is hereby amended to read as follows:

-(2)-TechnicalSpecifications The Tech'nical Specifications contained in Appendices A and B, as revised'.through Amendment No.134, are hereby incorporated in the license. .The licensee shall operate the facility in accordance with the Technical Specifica-tions, except where otherwise stated in specific license conditions.

3. This license amendment is' effective 30 days after the date of its issuance.

FOR THE NUCLEAR REGULATORY COMMISSION ~

O kl Af?

rp George W. Knighton, Director Project Directorate V Division of Reactor Projects - III, IV, V and Special Projects

Attachment:

. Changes to the Technical Specifications-9 Date of Issuance: September 1,1987 l

1

j l

1 i

l i

w-- . , ,

, .c ,

..=

J. "

. September 1,1987,

+

s >,

o ATTACHMENT TO LICENSE' AMENDMENT-NO.134' lM - TO FACILITY 0PERATING LICENSE N0' NPF-l' DOCKET NO. 50-344L b

Revise. Appendix A as follows:

! Remove Pages Insert Pages 1

3/4 4-3 3/4 4-3 3/4 4-4 --3/4 4-4 3/4 7 3/4 7-l'

~3/4L7-4^ 3/417-4 B.3/4 7 .B 3/4_7-1 e

b -

.-~ 'f j <

1 l._ REACTOR COOLANT SYSTEM sSAFETY' VALVES - SHUTDOWN-LIMITING CONDITION FOR OPERATION q 3.4'.2 'A minimum of one pressurizer code safety valve shall be OPERABLE' with a21ift' setting of 2485 PSIG (12%).

APPLICABILITY:- MODES 4'and:5.

ACTION

a.' With no pressurizer code safety valve OPERABLE, immediately suspend all operations: involving positive reactivity changes and place an OPERABLE

.RHR loop into operation in the shutdown cooling mode.

b. In the event a safety valve fails or:is;found inoperable. a Special Report shall be' prepared and submitted'to the Commission pursuant-to-Specification 6.9.2 within 30' days. The report shall describe the circumstances' surrounding the f ailure, including-the cause, if known.

SURVEILLANCE REQUIREMENTS 4'.4.2 1 The pressurizer code safety valve shall be demonstrated OPERABLE-per Surveillance Requirement 4.4.3.

y 1

i' l-1:

TROJAN-UNIT 1- 3/4 4-3 Amendment No. 97, 134

. l" September 1, 1987 3

.I -

REACTOR COOLANT SYSTEM 3/4.4.3 SAFETY AND RELIEF VALVES - OPERATINJ SAFETY VALVES LINITING CONDITION FOR OPERATION 3.4.3.1 All pressurizer code safety valves shall be OPERABLE with a lift L setting of 2485 PSIG (12%).

APPLICABILITY: MODES 1, 2 and 3.

ACTION:

a. With a pressurizer code safety valve inoperable,'either restore the inoperable valve to OPERABLE status within 15 minutes or be

'in HOT SHUTDOWN within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

b. In the event a safety valve fails or is found inoperable, a Special Report shall be prepared and submitted to the Commission pursuant to Specification 6.9.2 within 30 days. The. report shall' describe the circumstances surrounding the f ailure, including the j cause, if known,

c. The provisions of Specification 3.0.4 may be suspended for one

' valve at a time for up to 18 hours2.083333e-4 days 0.005 hours 2.97619e-5 weeks 6.849e-6 months for entry into and during p operation in Mode 3 for the purpose of setting the pressurizer code safety valves under ambient (hot) conditions provided a preliminary cold setting was made prior to heatup.

SURVEILLANCE REQUIREMENTS 4.4.3 No additional Surveillance Requirements other than those required by Specification'4.0.5.

TROJAN-UNIT 1 3/4 4-4 Amendment No. 56, 74, 8#, 97,134 September 1, 1987

c i" ,, . . : . -

lL3/4.7 PLANT SYSTEMS 3/4.7.1 TURBINE CYCLE SAFET'Y' VALVES LIMITING CONDITION FOR OPERATION 3.7.1.1 All main steam line code safety valves associated with each steam generator shall be OPERABLE.

APPLICABILITY: MODES 1, 2 and 3.

' ACTION:

a. With 4 reactor coolant loops and associated steam generators in operation and with one or more main steam line code safety valves inoperable, operation .in MODES 1, 2 and 3 may proceed provided, that within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months , either the inoperable valve is restored to OPERABLE status or the. Power Range Neutron Flux High Setpoint trip is reduced per Table 3.7-1; otherwise, be in COLD SHUTDOWN within the next 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months '.

b. With 3 reactor coolant loops end associated steam generators in' operation and with one or more main steam line code safety valves associated with an operating loop inoperable, operation in MODES 1, 2 and 3 may proceed provided, that within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months , g either the inoperable valve is restored to'0PERABLE status or.

the Power Range Neutron Flux High Setpoint trip is reduced per Table 3.7-2; otherwise, be in COLD SHUTDOWN within the next-36 hours.

c. The provisions of Specification 3.0.4 are not applicable.

SURVEILLANCE REQUIREMENTS 1

4.7.1.1 Each main steam line code safety valve shall be demonstrated OPERABLE,.with lift settings and orifice sizes as shown'in Table 4.7-1, when tested ' pursuant to Specification 4.0.5.

i I

TROJAN-UNIT 1 3/4 7-1 Amendment No. 74,134 l?

September 1, 1987 w_m_mm-__ _ _ _ _ .m_ - - . - ____m-.__

s s e e s s s h h e e e c c h h h E n n c c c Z i i n n n I i i i S . .

q q . . .

E s s q q q E s s s I 5 5 F 0 0 0 0 0 I

R 1 1 6 6 6 O 1 1 1 1 1

= = =

Q Q R R R

)

2 1

( g g g g g i i i i i E s s s s s U p p p p p L

P A 3 4 4 4 4 O V 9 2 3 4 5 O 1 2 2 2 2 L E 1 1 1 1 1 L - - - - -

R B 7 6 6 6 6 E A 4 7 8 9 0 P W 1 1 1 1 2 O 1 1 1 1 1 S L E L 1 V A

- L 7 A V G 4

Y N E T I g g g g g L E T i i i i i B F T s s s s s A A E p p p p p

, T S S 0 0 0 0 0 E T 7 0 1 2 3 N F 1 2 2 2 2 I I 1 1 1 1 1 L L M

A E 1 2 3 4 5 T 7 7 7 7 7 S 2 2 2 2 2 2 2 2 2 2 V V V V V S S S S S n P P P P P 1 2 3 4 5 5 5 5 5 5 2 2 2 2 2 2 2 2 2 2 R V V V V V E S S S S S B c P P P P P M

U , , , , ,

N 1 2 3 4 5 3 3 3 3 3 E 2 2 2 2 2 V 2 2 2 2 2 L - - - - -

A V V V V V V S S S S S B P P P P P 1 2 3 4 5 1 1 1 1 1 2 2 2 2 2 2 2 2 2 2 V V V V V S S S S S

^ P P P P F a b c d e goy E ~ "x& n k @B@~ z E?9n,c i

o e

j' .

M; j n' +

Q.1 y

y s l

g 4- 'j usQ -r 3/4.7 ' PLANT SYSTfijS 4

+ , . j BASES 'A lA f

3 /4 '. 7 .1 TURBINE CYCLE w u A

~

3/4.7.1.1' SAFETY VALVES' i The OPERABILITY of'the ma,'m steam line code safety valves ensures that the'secontarV' system pressure will be limited to within 110%- 4

_ (1305 psig) ff!1its design pressure of 1185 psig during the most severe anticipated system operational transient. The maximum relieving.-

capacity is associated with W turbine trip f rom 100% RATED THERMAL' '

POWER coincident with an c55umediloss of condenser heat.s # 2 (i.e., no steam bypass9 to the condenser). *'

3 S

u .

The specified valve lift settings-and relieving capacities are in accordance with the requirements- of Section III- of the ASME Boiler and . ,

Pressure Code, 1971 Edition. The safety valves are' tested in accordance with the requirements of Section. XI of 'the ' ASME Code. The lift settinh ,

allowable values are consistent withithe safety analysis. The. safety 3 i analysis is not as restrictive as 7.he ASME Code. Therefore, in the event a safety valve difts outsid W of the Section XI allowed tolerance, the Section'XI' provihons for adj ssting the setpoint and testing addi-

-tional valves'applics. The totaj relieving capacity for all valves on' all.

of;the steam lines is 16.47 x 10- gbs/hr which is 109 percent cf the total secondary steam flow of(15.07 x 10 lbs/hr at 100% RATED THERMAL POWER. A minimum of' 2 OPERABLE safety valves per operable steam generator ensures that sufficiertyelieving capacit./ is available for the allowable THERMAL POWER restriction'in Table 3.7-2, 1- ay a STARTUP1rgd/or POWER OPERATION is allowable with safdty valves.

inoperable wishin'the limitations of the ACTION requirements on the basis of the reduction in secondary system steam flow and THERMAL POWER required by the reduced reactor trip settings of the Power Rangedieutron Flux channels. The, reactor trip 'setpoint reductions are derived on the following bases:- ,

i 1

For 4 loop operation '

SP = 3, (109)

X

.i l For 3g bop operation

~

SP =

X x (75)

Where: l l-l SP =' re6ced reactor trip setpoint in percent of RAMD THHHAL POWER g

V = rnsyimum number of inoperable safety valves per steam line b

TROJAN-UNIT 1 B 3/4 7-1 Amendment No. 134 i September 1,1987 ,.!

s .

3

ML20238B008

Text

Attachment:

= = =

Navigation menu

Search