ML20211C882

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Proposed Tech Specs Re Reactor Trip Sys & ESF Actuation Sys Instrumentation & Surveillance Requirements
ML20211C882
Person / Time
Site: Trojan File:Portland General Electric icon.png
Issue date: 10/17/1986
From:
PORTLAND GENERAL ELECTRIC CO.
To:
Shared Package
ML20211C796 List:
References
TAC-56816, NUDOCS 8610220047
Download: ML20211C882 (7)
v • d • e


Text

._

TABLE 3.3-1 REACTOR TRIP SYSTEM INSTRUMENTATION cE MINIMUM

  • - TOTAL NO. CHANNELS CHANNELS APPLICABLE

] FUNCTIONAL UNIT OF CHANNELS TO TRIP OPERABLE MODES ACTION

1. Manual Reactor Trip 2 1 2 1, 2 11 2 1 2 3*, 4*, 5* 10
2. Power Range, Neutron Flux A. High Setpoint 4 2 3 1 2 2#

B. Low Setpoint 4 2 3 III#,2 2#

3. Power Range, Neutron Flux 4 ~2 3 1, 2 2#

High Positive Rate

4. Power Range, Neutron Flux, 4 2 3 1, 2 2#

High Negative Rate

$ 5. Intermediate Range, Neutron Flux 2 1 2 18##, 2 3 Y

6. Source Range, Neutron Flux A. Startup 2 1 2 2## 4 B. Shutdown 2 1 2 3* , 4*, 5* 10 C. Shutdown 2 0 1 3,4,5 5
7. Overtemperature AT-Four Loop Operation 4 2 3 1, 2 6#

Three Loop Operation 4 1**- 3 1, 2 8

8. Overpower AT Four Loop Operation 4 2 3 1, 2 6#

Three Loop Operation 4 1** 3 1, 2 8 ,3, 8

g 9. Pressurizer Pressure - Low 4 2 3 19 6# ' lmmE"S _,

B C#~

g 10. Pressurizer Pressure - High 4 2 3 1, 2 6#

o- nl :n

,5 11. Pressurizer Water Level - High 3 2 2 1* 6# g-$

~

5 8610220047 861017 4 PDR ADOCK 0500 P

. . ~.

l

\

LCA 117, Rev. 2 l

. Attachment 1 Page 14 of 42 j TABLE 3.3-1 (Continued)

TABLE NOTATION

  • With the reactor trip system breakers in the closed position and the control rod drive system capable of rod withdrawal.
    • The channel (s) associated with the protective functions derived from the out of. service Reactor Coolant Loop shall be placed in the trip-ped condition.
  1. The provisions of Specification 3.0.4 are not applicable.
    1. When below the P-6 setpoint.
      1. When below the P-10 setpoint.
  • When above the P-7 setpoint.

(1) The applicable MODES and. ACTION statement for these channels.noted in Table 3.3-3 are more restrictive and, therefore, applicable.

ACTION STATEMENTS ACTION 1 - With the number of channels OPERABLE one less tLan the Mini-mum Channels OPERABLE requirement, be in at least HOT STANDBY within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />. One. channel may be bypassed'for up to 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> for surveillance testing per Specification 4.3.1.1 l provided the other channel is OPERABLE.

ACTION 2 With the number of OPERABLE channels one less than the Total Number of Channels, STARTUP and/or POWER OPERATION may pro-ceed provided all of the following conditions are satisfied:

! a. The inoperable channel is placed in the tripped condition within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.

b. The Minimum Channels OPERABLE requirement is met; how-ever, the inoperable channel may be bypassed for up to 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> for surveillance testing of other channels per Specification 4.3.1.1.
c. Either THERMAL POWER is restricted to $75% of RATED
THERMAL POWER and the Power Range Neutron Flux trip setpoint is reduced to $85% of RATED THERMAL POWER within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />; or, the QUADRANT POWER TILT RATIO is monitored at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />, per Specification 4.2.4.c.

TROJAN-UNIT 1 3/4 3-5 Amendment No. 33,

LCA 117, Rev. 2

- . Attachment 1 Page 15 of 42 TABLE 3.3-1 (Continued)

ACTION 3 - With the number of channels OPERABLE one less than the Minimum Channels OPERABLE requirement and with the THERMAL POWER level:

a. Below P-6, restore the inoperable channel to OPERABLE status prior to. increasing THERMAL POWER above the P-6 setpoint.
b. Above P-6, operation may continue, provided that THERMAL POWtR is expeditiously placed within the range of the Source Range or Power Range Instrumentation.

ACTION 4 - With the number of OPERABLE channels one less than the Mini-mum Channels OPERABLE requirement, suspend all operations involving positive reactivity changes.

ACTION 5 - With the number of channels OPERABLE one less than the Mini-mum Channels OPERABLE requirement, verify compliance with the SHUTDOWN MARGIN requirements of Specification 3.1.1.1 within.

1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> and at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> thereafter.

ACTION 6 - With the number of OPERABLE ach'nnels one less than the Total Number of Channels, STARTUP and/or POWER OPERATION may pro-ceed provided both of the following conditions are satisfied:

a. The inoperable channel is placed in the tripped condition within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.

b .- The Minimum Channels OPERABLE requirement is met; how-ever, the inoperable channel may be bypassed for up to 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> for surveillance testing of other channels per Specification 4.3.1.1.

l ACTION 7 -' With the number of OPERABLE channels less than the Total l Number of Channels, place the inoperable channel in the l

tripped condition within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />. Operation may continue until performance of the next required CHANNEL FUNCTIONAL TEST.

ACTION 8 - With a channel associated with an operating loop inoperable, l restore the inoperable channel to OPERABLE status within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.

One channel associated with an operating loop may be bypassed for up to 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> for surveillance testing per Specification 4.3.1.1.

TROJAN-UNIT 1 3/4 3-6 Amendment No. 33,

TABLE 4.3-1 REACTOR TRIP SYSTEN INSTRUNENTATION SURVEILLANCE REQUIREMENTS 5

7 E CHANNEL MODES IN WHICH q CHANNEL CHANNEL FUNCTIONAL SURVEILLANCE

_. FUNCTIONAL UNIT CHECK CALIBRATION TEST REQUIRED

1. Manual Reactor Trip N.A. N.A. 'R 1, 2, 3*, 4*, 5*
2. Power' Range, Neutron Flux .

A. High Setpoint S D(2,4), M(3,4) Q(11) 1, 2 Q(4,6)

8. Low Setpoint S R(4) S/U(1) 14 # , 2
3. Power Range, Neutron Flu.t. N.A. R(4) Q(11) 1, 2 High Positive Rate
4. Power Range, Neutron Flux, N.A. R(4) Q(11) 1, 2 High Negative Rate w 5. Intermediate Range, S R(4)# S/U(1) 14 # , 2

..' Neutron Flux o

6. Source R'ange, Neutron Flux S R(4,5) S/U(1), Q(11)# 2# , 3, 4, 5(9)
7. Overtemperature AT S R Q(11) 1, 2
8. Overpower AT S R Q(11) 1, 2

~

9. Pressurizer Pressure - Low S R Q(11) 19 l

{ 10. Pressurizer Pressure - High S R -Q(11) 1, 2 ,,

as e a

11. Pressurizer Wat.er Level - High S R Q(11) 1*
12. Loss of Flow - Single Loop S R Q(11) 1 *5"

,8 (Above P-8) ., %S y

, C ~ .*

~

. TABLE 4.3-2 Y

2 ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION

@ SURVEILLANCE REQUIREMENTS a

E

  • CHANNEL MODES IN WHICH

~

CHANNEL CHANNEL FUNCTIONAL' SURVEILLANCE FUNCTIONAL UNIT CHECK CALIBRATION TEST (2) REQUIRED l

1. SAFETY INJECTION I
a. Actuation Logic N.A. -N.A. M(1) 1, 2, 3, 4 l b. Manual Initiation N.A. N.A. R 1,2,3,4
c. Containment Pressure - High S R M 1,2,3,4 l } d. Pressurizer Pressure - Low S R M 1, 2, 3#

T e. Differential Pressure S R M 1, 2, 3##

I Ei$ Between Steam Lines - High

f. Steam Flow in Two Steam S R M 1, 2, 3## l Lines - High Coincident with Tavg - Low-Low or Steam Line Pressure - Low
2. CONTAINMENT SPRAY
a. Actuation Logic N.A. N.A. M(1) 1, 2, 3, 4
b. Manual Initiation N.A. N.A. R 1,2,3,4
$ ?NG

$ c. Containment Pressure - High-High S R M 1,2,3,4 'Sy{

b an.

I E .E C "

Attachment 2 Page 1 of 2 LCA 117, REVISION 2 RESOLUTION OF WOG/NRC COMMENTS ON WCAP-10271 WOG Guidance NRC Guidance (WOG Letter of 5/16/35) (NRC Letter of 7/24/85) Trojan Resolution l 1) WOG has an extensive write-up on A significant hazards consideration The significant hazards consideration the appropriate words to be used which follows the logic of the Safety in LCA 117, Rev. 2, follows the WOG for the significant hazards con- Evaluation Report is suggested. Do and NRC guidance as appropriate, sideration relating to not refer to " published ATWT accep-WCAP-10271. tance criteria" as proposed by the WOG. Also, do not cite specific risk values.

2) WOG recommends that staggered Staggered testing should be in the LCA 117, Rev. 2, specifies staggered testing be specified in the Technical Specifications, testing.

Technical Specifications.

1 Alternatively, specify staggered testing in a procedure.'

1

3) Establish procedures that Concur with WOG guidance. Common mode failure evaluation will require evaluation of failures be specified in procedures.

to determine if a common mode failure is involved.

4) WOG recommends two different NRC specifies only one ACTION state- We have only one ACTION statement, ACTION statements depending on ment and this ACTION should reflect which is written as if we had bypass
if you have bypass capability or the design. capability. However, our present not. WOG suggests including Technical Specifications are written both ACTION statements in the as if we had bypass capability.

1 Technical Specifications and use whichever is appropriate.

5) WOG recommends that we list the ---

Trojan does not have bypass capability.

Reactor Protection functions with bypass capability or for which we intend to install bypass capability.

l

' Attachment 2 Page 2 of 2 WOG Guidance NRC Guidance

! (WOC Letter of 5/16/85) (NRC Letter of 7/24/85) Trojan Resolution l

6) ESFAS surveillance is a separate NRC concurs with WOG. LCA 117, Rev. 2, follows the WOG-and issue. The. dual function RPS/ NRC guidance.

ESFAS instruments should be left

as ' monthly surveillance or add j a cautionary note.
7) Adequacy of setpoints and allow- NRC concurs with WOG. Future data will be collected.

able values should be evaluated I

based on reduced frequency of

, surveillance. Commit to review

historical data or trend future i data.

, 8) Power Range (low setpoint), . Power Range (low setpoint) and Inter- LCA 117, Rev. 2, conforms with the NRC Intermediate Range, and Source mediate Range should be tested only guidance.

] Range are tested only quarterly. during startup. Source Range should be tested quarterly and during startup.

9) ---

With_ regard to Note 1 of Table 4.3-1, LCA 117, Rev. 2, specifies 31 days.

change "7" days to "31" days, t

BLK/kal 1642G.986 I

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