ML20005F140
| ML20005F140 | |
| Person / Time | |
|---|---|
| Site: | Yankee Rowe |
| Issue date: | 01/05/1990 |
| From: | Devincentis J YANKEE ATOMIC ELECTRIC CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| Shared Package | |
| ML20005F141 | List: |
| References | |
| BYR-90-004, BYR-90-4, NUDOCS 9001120337 | |
| Download: ML20005F140 (16) | |
Text
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YANKEE ATOMIC ELuCTRIC COMPANY
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580 Main Street, Bolton, Massachusetts 01740-1398 m
k* v/AN KE IE '
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l, January 5, 1990 PC 231 L
BYR 90-004 p
' United States'Nucleat Regulatory Commission
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o Attentatm.,
Document Control Desk
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Washing t m DC 20555
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Referencest (a). License No. DPR-3 (Docket No. 50-29)
(b) USNRC Letter to Yanken, dated May 13, 1987
Subject:
Proposed Change to Technical Specifications to Allow Utilization L
and Increased Testing at Power cf a New Neutron Flux I
' Instrumentation System (Proposed Change 231)
Dear Sira li Pursuant to Section 50.90 of the Commission's Rules and Regulations, Yankee Atomic Electric Company (YAEC) hereby proposes the following amendment to Appendix A of the facility license.
1, Proposed Change
.. Reference is made to the Technical Specifications of Yankee Nuclear Power Station (YNPS), License No. DPR-3.
We propose to modify the Technical Specifications as described below:
1.
Technical Specification Pages 3/4 3-2, 3-4, 3-5, 3-6, and 3-8.
Modify pages to allow the testing of the low setpoint channel trip at power, and/or to clarify Specifications.
2.
Technical Specification Prges 3/4 3-3, 3-7, 3-9, 3-10, 3-12A, 3-13, 3-13A, 3-15A, and 3-16.
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Modify pages to allow the bypass and the testing of the neutron flux instrumentation trip logic at power, and/or to clarify Specifications.
3.
Technical Specification Pages 3/4 3-4, 7-1, 10-3, and 10-4.
Modify pages to take advantage of new adjustability in the upgraded system, and/or to clarify Specifications.
$0 9001120337 900105
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l United States Nuclear Regulatory Commission January 5, 1990 Attention Document Control Desk Page 2 i
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4.
Technical Specification Page 3/4 3-28.
Modify page to show new fire detector for the new instrumentation panel.
t A detailed explanation of these modifications is contained in The modified Technical Specification pages are contained in.
Description of Change t
This proposed change incorporates into the Technical Specifications modifications to allow Yankee to utilize a new Neutron Flux Instrumentation System, including its ability for enhanced testing at power, and modifications
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to clarify Specifications.
R_ealon and Basis for Change The present Neutron Flux Instrumentation System at YNPS was installed i
during the initial plant construction. The instrumentation's past and present performbce has been excellent.
However, due to advances in the capabilities of more modern systems and the difficulty to procure replacement parts. Yankee has decided to upgrade YNPS's system.
The upgraded system will be installed in the Control Room directly across r
from the existing system in a new panel. This panel accommodates new instrumentation drawers as well as relays, status lights, switches, and other devices needed to interface with the Reactor Protection System. Changes to the front of the Main Control Board (MCB) are minimal.
The source range, intermediate range, and start-up rate meters are reused. The six power level meters and associated gain adjustment potentiometers are replaced with new digital bargraph neters and gain adjustment push buttons. New alarms are provided on the MCE in addition to those presently used to complement the new neutron flux equipment.
Utilization of the upgraded system will require an allowance for bypassing, one train at a time, the new system trip logic during quarterly testing currently required for the Main Steam Isolation Trip Logic. This is due to the interface of the trip logic circuit (s) in the upgraded system with the existing Reactor Protection System trip logic circuits via a common reactor trip circuit (s).
The NRC in Amendment Number 105 to YNPS's Technical Specifications, Reference (b), noted that:
The current YNPS practice is to perform all elements of a nuclear instrument calibration during the monthly channel functional test, except for the calibration or test of the low trip setpoint which cannot be done at power.
This current practice by the licensee is more conservative than the current monthly channel functional test required by the Technical Specifications in that, it incorporates
r United States Nuclear Regulatory Commission January 5, 1990 i
Attention: Document Control Desk Page 3 all elements of the functional test to verify channel operability and in addition, performs a channel calibration.
Except for the low trip setpoint, the monthly test exceeds the current Technical Specification requirement to perform a quarterly channel calibration. During Inspection 50-29/87-02, the staff reviewed test procedures and test data, and verified that the channel functional test and the channel calibration as currently performed at YNPS provide assurance of channel operability that is equivalent in scope to channel functional test and calibrations specified by Westinghouse Standard Technical Specifications (STS) er. cept for testing the low trip setpoint.
The upgraded system will allow Yankee to perform testing of its low trip setpoint during the channel functional and calibration tests. Additionally, Yankee will also be able to perform a quarterly testing of relays in the new system trip logic circuits. This enhanced testing capability will give furthet assurance that this vital equipment will perform its safety function.
Safety Considerations This change is requested to allow Yankee to utilize a new Neutron Flux Instrumentation System, including its abilities for enhanced testing at power, and to clarify Specifications. As such, this proposed change would nott 1.
Involve a significant increase in the probability or consequences of an accident previously evaluated. The proposed Specification modifications compliment and take advantage of the broader adjustment and testing capability of the upgraded Neutron Flux Instrumentation System. This will further assure that the Neutron Flux Instrumentation System will be configured conservatively, perform as designed, and support the functions assumed in the accident analysis. Therefore, these proposed Specification modificc.ons do not involve a significant increase in the probability or consequences of an accident.
2.
Create the possibility of a new or different kind of accident from any accident previously evaluated. The proposed Specification modifications do not change Specification requirements for operation or surveillance of any piping systems, electrical power systems, or mechanical structures.
The proposed Specification modifications compliment and take advantage of the broader adjustment and testing capability of the upgraded Neutron Flux Instrumentation System.
This will further assure that the Neutron Flux Instrumentation System will be configured conservatively, perform as designed, and support the functions assumed in the accident analysis. Therefore, the proposed Specification modifications do not create the possibility of a new or different kind of accident from any accident previously ein h.ated.
1 3.
Involve a significant reduction in a margin of safety. The proposed l
Specification modifications do not change any Specification safety l
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l United States Nuclear Regulatory Conunission January 5, 1990 L
Attention: Document Control Desk Page 4 i
C limits, except to reduce setpoints not presently reduced (LCO 3.7.1.1 Action Statement,-LCO 3.10.3, and LCO 3.10.4) and provide further i
c
-conservatism. Therefore, the margin of safety is not reduced.
Based on the discussion above, it is concluded that there is reasonable assurance that operation of the Yankee plant, consistent with the proposed Technical Specifications, will not endanger the health and safety of the 4
public. This proposed change has been reviewed by the Nuclear Safety Audit and Review Committee.
t o
Schedule i
The installation of the new Neutron Flux Instrumentation System is planned to be completed during the Core XX-XXI refueling, scheduled to begin the middle of June 1990.
It.is requested that these proposed changes be 3
approved prior to the refueling outage with an implementation date consistent l
with the Core XXI startup.
We trust that you will find this submittal satisfactory; however, should.
i you desire additional information, please contact us.
Very truly yours, YANKEE ATOMIC ELECTRIC COMPANY bus.jp 1
!. DeVincentis J
Vice President i
r JDV/b11/0444v cc: USNRC Region I USNRC Resident Inspector. YNPS Attachments COMMONWEALTH OF MASSACHUSETTS)
)ss MIDDLESEX COUNTY
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Then personally appeared before me, J. DeVincentis, who, being duly sworn, did state that he is a Vice President of Yankee Atomic Electric Company, that he is duly authorized to execute and file the foregoing document in the name and on the behalf of Yankee Atomic Electric Company and that the statements therein are true to the best of his knowledge and belief.
bdkb1k Robert H. Groce' Notary Public My Conunission Expires August 29, 1991
7 ATTACHMENT A Proposed Change Synopsis
SUMMARY
This proposed change incorporates into the Technical Specifications modifications to allow Yankee to utilize a new Neutron Flux Instrumentation L
System, including its ability for enhanced testing at power, and modifications i
to clarify Specifications.
DISCUSSION The present Neutron Flux Instrumentation System at YNPS was installed during i
the initial plant construction.
The instrumentation's past and present performance has been excellent.
However, due to advances in the capabilities of more modern systems and the difficulty to procure replacement parts, Yankee has decided to upgrade YNPS's system.
The upgraded system will be installed in the Control Room directly across from the existing system in a new panel. This panel accommodates new instrumentation drawers as well as relays, status lights, switches, and other devices needed to interface with the Reactor Protection System. Changes to the front of the Main Control Board (MCB) are minimal. The source range, intermediate range, and start-up rate meters are reused. The six power level meters and associated gain adjustment potentiometers are replaced with new digital bargraph meters and gain adjustment push buttons. New alarms are provided on the MCB in addition to those presently used to complement the new neutron flux equipment.
Utilization of the upgraded system will require an allowance for bypassing, one train at a time, the new system trip logic during quarterly testing currently required for the Main Steam Isolation Trip Logic. This is due to the interface of the trip logic circuit (s) in the upgraded system with the existing Reactor Protection System trip logic circuits via a common reactor trip circult(s).
The NRC in Amendment Number 105 to YNPS's Technical Specifications, Reference (b), noted that:
The current YNPS practice is to perform all elements of a nuclear instrument calibration during the monthly channel functional test, except for the calibration or test of the low trip setpoint which cannot be done at power. This current practice by the licensee is more conservative than the current monthly channel functional test required by the Technical Specification in that, it incorporates all elements of the functional test to verify channel operability and in addition, performs a channel calibration. Except for the low trip 0444v
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ATTACHMENT A (continued)
Proposed Change Synopsis setpoint, the monthly test exceeds the current Technical Specification requirement to perform a quarterly channel calibration.
During Inspection 50-29/87-02, the staff reviewed test procedures and test data, and verified that the channel functional test and the channel calibration as currently performed at YNPS provide assurance of channel operability that is equivalent in scope to channel functional test and calibrations specified by Westinghouse Standard Technical Specifications (STS) except for testing the low trip setpoint.
The upgraded system will allow Yankee tu perform testing of its low trip setpoint during the channel functional and calibration tests. Additionally.
Yankee will also be able to perform a quarterly testing of relays in the new system trip logic circuits. This enhanced testing capability will give further assurance that this vital equipment will perform its safety function.
CONCLUSION This proposed change incorporates into the Technical Specifications modifications to allow Yankee to utilize a new Neutron Flux Instrumentation System including its ability for enhanced testing at power, and modifications to clarify Specifications.
Based on the considerations contained herein, it is concluded that there is reasonable assurance that operation of YNPS, consistent with this proposed Technical Specification, will not endanger the health and safety of the public. Therefore, this proposed change should be approved. 0444v i
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AITACEMENT 1 Page 1 of 9 Technical Soecification Changes Item Procosed N nge Reason and Basis _.for NP-e
- 1) Table 3.3-1, Modify Table 3.3-1, Functional Unit 2 The modification to Table 3.3-1, Functional Functional Unit 2 and Notation (1) to locate Notation (1)
Unit 2 and Notation (1) are clarifications with the mode in which it is applicable only. Table Notation (1) applies to Mode 1 and to clarify that the low setpoint trips only. Its relocation in the table is made are associated only with the three Power to reflect this. The high neutron flux - low Range channels. Refer to Pages 3/4 3-2 setpoint trip is associated only with the and 3/4 3-4 for the specific changes Power Range Channels.
proposed.
- 2) Table 3.3-1, Modify Table 3.3-1, Functional Units 14 Proposed Action Statement 24 clarifies the Functions 1 and 15, Action Statements to provide an current Action Statement for Table 3.3-1, Units 14 and 15 allowance for bypassing one train at a Functional Unit 14 (Action Statement 9) to time for surveillance testing of relays provide for the bypassing of ons trip logic in the trip logic circuits. Refer to train at a time for surveillance testing. This Pages 3/4 3-3, 3/4 3-7, and 3/4 3-7A for clarification is needed since portions of the specific changes proposed.
Functional Unit 14 must be bypassed during quarterly functional testing currently required for Functional Unit 15, otherwise a reactor trip would occur as a result of testing. The affected portions of Functional Unit 14 are derived from Functional Units 5, 7, 8 and 10 and exclude the nuclear instrumentation.
Proposed Action Statement 25 clarifies the current Action Statement for Table 3.3-1, Functional Unit 15 (Action Statement 8) to provide for the bypassing of one trip logic train at a time for surveillance testing. This clarification is needed since Functional Unit 15 must be bypassed during its (currently) required quarterly testing to prevent a reactor trip as a result of testing.
The new functional testing for Functional Unit 16 proposed for addition to Table 3.3-1 will also require the bypass of Functional Unit 14 (portions) and of Functional Unit 15.
AITACEMENT 1 Page 2 of 9 Technical Snecification Changts (Continued)
Rem Proposed N a-e Ba==a=
and Basis for N a-e
- 3) Table 3.3-1, Modify Table 3.3-1 adding Functional The addition of Functional Unit 16 to Functional Unit 16 Unit 16 to account for two new trains Table 3.3-1 accounts for the two new trains of of Nuclear Instrumentation Trip logic.
trip logic which are provided in a design Action Statement 24 is added to accompany change to replace the Nuclear Instrumentation.
this new functional unit and provides The applicable modes are consistent with those an allowance for bypassing one train at of Functional Units 2 and 3 which are the a time for surveillance testing. Refer associated instrument channels.
to Pages 3/4 3-3 and 3/4 3-7 for the specific changes proposed.
Proposed Action Statement 24 includes the action requirement from Action Statement 9 as well as a provision to allow bypassing of one trip logic train at a time for surveillance testing.
(Action Statement 9 is the current Action Statement used for Table 3.3-1, Functional Unit 14, which is applicable to the current Nuclear Instrumentation.) This allowance is needed for the proposed quarterly Functional Testing of the Nuclear Instrumentation Trip Iogic. This allowance is also needed with the implementation of the new Nuclear Instrumentation System for quarterly Functional Testing currently required for Functional Unit 15.
- 4) Table 3.3-1, Modify Table 3.3-1, Table Notation "#",
The modification to Table 3.3-1, Notation "#",
Table Notation "#"
to change the level below which the changes the point below which the Intermediate i
source range detector high voltage must Range Channel must energize the Source Range be energized. Refer to Page 3/4 3-4 for Channel detector high voltage. The Source Range the specific change proposed.
detector high voltage must be removed on increasing power level prior to reaching the maximum flux level specified for its operation. High voltage is automatically 1
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3 AIIACRIENT 1 Fage 3 of 9 Technical Snecification Cha p (Continued)
Item Pronosed Channe Reason and Bas _in__for n-a-e
- 4) Table 3.3-1, re-energized on decreasing power level.
Table Notation "#"
Protection (reactor trip) functions from the (Continued)
Source Range Channels are not assumed in the accident analysis or used in the Reactor Protection System.
The proposed notation for clarity specifies when the detector high voltage is energized rather than when it is de-energized. That is, when the Source Range Channel is functional.
The setpoint has been reduced from 5 x 10-9 to 5 x 10-10 amperes..The value of 5 x 10-10 amperes will provide for at least one and one half decades of Intermediate Range Channel operation above its bottom scale value of I x 10-11 amperes prior to source range cutoff.
- 5) Table 3.3-1 Modify Table 3.3-1, Action Statement 2d, The modification of Table 3.3-1, Action Action to specify that the period of two hours Statement 2d, specifies the two-hour period of Statement 2d allowed for coincidence operation is coincidence operation to be on a per-channel "per charnel." Refer to Page 3/4 3-5 for basis. New instruments are provided in a the specific change proposed.
design change for the replacement of the Nuclear Instrumentation. The replacement instruments for the Power Range and Intermediate Power Range Channels include an automatic calibration process which requires a minimum of approximately one hour to complete and is exclusive of functional testing. The two-hour period, specified on a per-channel basis, will allow the time needed for calibration.
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ATTACEMENT 1 Page_4 of 9 Technical Specification f% a-es (Continued)
Item Proposed r'h.nre n===on_and Basis for Cb---e
- 6) Table 3.3-1 Modify Table 3.3-1, Action Statement 3, for The modification of Table 3.3-1, Action Action clarification to remove the requirement to Statement 3, removes the requirement to " place Statement 3
" place the inoperable channel in the bypassed the inoperable channel in the bypassed condition condition within I hour " Refer to within I hour." The present instrumentation Page 3/4 3-5 for the specific change proposed. does not incorporate a specific feature to bypass a channel. Placing a channel in the bypassed condition serves to remove its trip function from the reactor trip logic. Although the bypass of an inoperable channel may be desirable to minimize exposure to potential spurious trips, it does not result in a more conservative protection configuration. The requirement to " place the inoperable channel in the bypassed condition within 1 bour" unnecessarily complicates the action statement. This modification is, therefore, made as a clarification.
- 7) Table 3.3-1 Modify Table 3.3-1, Action Statement 5, The modification of Table 3.3-1, Action Action for clarification to correct an error in Statement 5, corrects an error. The current Statement 5 referencing Specification 3.1.1.1.
Refer Action Statement makes reference to to Page 3/4 3-6 for specific change proposed.
Specification 3.1.1.1, which is applicable in Modes 1 and 2.
Specification 3.1.1.1.2 is the appropriate reference and is applicable in Mode 3.
(Functional Unit 4b is not applicable in Modes 1 and 2.)
- 8) Table 3.3-1 Modify Table 3.3-1, Action Statements 6 and 7 The modification of Table 3.3-1, Action Action to make the paragraph identifiers follow a Statements 6 and 7 is a change in paragraph Statements 6 consistent format. Refer to Page 3/4 3-6 for identification only.
It is made to provide a j
and 7 specific changes proposed.
consistent number, letter, and number format.
l Action Statement, Paragraphs 6.1, 6.2, 7.6.a, and 7.b.b now become 6.a, 6.b, 7.b.1, and 7.b.2.
l
ATTACIEENT 1 Page 5 of 9 Technical Soecification Channes (Continued)
Item Pronosed Nan-e Reason =ad Basis for Ch=a-c
- 9) Table 4.3-1, Modify Table 4.3-1, Functional Unit 2, The modification of Table 4.3-1, Functional Functional Unit 2 to return to the specification which Unit 2, returns the specification to that existed under amendments previous to which existed prior to Amendment 105. A Amendment 105. Refer to Pages 3/4 3-8 design change for the replacement of the and 3/4 3-10 for the specific change Nuclear Instrumentation includes provisions-proposed.
for calibration and testing at power of the low setpoint trip associated with each Power Range Channel. Amendment 105 was made to provide cirxification since this feature was not provided for by the original design.
4
- 10) Table 4.3-1 Modify Table 4.3-1, Functional Unit 15, This modification is made to clarify that the Functional to clarify that contacts or contact testing of relays in the trip logic circuit at Unit 15 combinations in the logic circuit may be power requires in part that contacts or contact simulated to operate relays in the trip combinations in the logic circuit be logic circuit. Refer to Pages 3/4 3-9 and simulated because the provision for more 3/4 3-10 for the specific change proposed.
detailed testing (at power) is not provided in the circuit design. Testing of the manual initiation and M S containment pressure O
functions of the logic circuit are specified to be performed at refueling intervals.
(Refer to Table 4.3-2, Functional Units 3c and 3d). Note that the trip logic circuit represented by Table 4.3-1, Functional Unit 15, and l
Table 4.3-2, Functional Units 3b, 3c, and 3d is the same circuit.
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ATTACHMENT 1 Page 6 of 9 Technical Snecification Chma-es (Continued)
Item Proposed M an-e
- -==an and Basis for f'h=a-e
- 11) Table 4.3-1, Modify Table 4.3-1 adding Functional The addition of Functional Unit 16 to Functional Unit 16 to account for two new trains Table 4.3-1 accounts for the two new. trains of Unit 16 of Nuclear Instrumentation Trip Logic.
trip logic which are provided in a design Refer to Pages 3/4 3-9 and 3/4 3-10 for change to replace the Nuclear Instrumentation.
the specific change proposed.
The modes listed are consistent with those of the associated instrument channels, Functional Units 2 and 3.
The quarterly functional testing frequency specified is consistent with that presently specified for Functional Unit 15.
The addition also specifies that contacts and contact combinations in the logic circuit may be simulated to operate relays in the trip logic circuit. This allowance will minimise the time required for the surveillance bypass of each train of trip logic. Simulation is also required for contact combinations including the permissive contacts for the start-up rate trip. The permissive contacts are normally open above 15 MWe to block the trip, and cannot be operated for testing at power.
- 12) Table 3.3-2 Modify Table 3.3-2, Functional Units 3b, Proposed Action Statement 26 clarifles the Functional 3c, and 3d, Action Statements to provide current Action Statement for these FUNCTIONAL Units 3b, 3c, allowance for bypassing one train at a UNITS (Action Statement 8) to provide for and 3d time for surveillance testing. Refer to bypassing of one trip logic train at a time for Pages 3/4 3-12A, 3/4 3-13, and 3/4 3-13A surveillance testing. This clarification is for the specific change proposed.
needed since these Functional Units must be bypassed during the (currently) required quarterly testing of Functional Unit 3b to prevent tripping the Main Steam Isolation
ATIACHMENT 1
-Page 7 of 9 Technical Snecification Channes (Continued)
Item Pronosed Channe Reason and Basis for N--e
- 12) Table 3.3-2 (Non-return) valves as a result of testing.
Functional Note that the trip logic circuit represented by Units 3b, 3c, Table 3.3-1, Functional Unit 15 and and 3d Table 3.3-2, Functional Units 3b, 3c, and 3d is (Continued) the same circuit. However, Functional Unit 15 in Table 3.3-1 is applicable as a Reactor Protective System Instrumentation Functional Unit since it also provides a Reactor Trip.
Action Statement 8 is deleted from Page 3/4 3-13 since it is incorporated in Action Statement 26 and is not used elsewhere in Table 3.3-2.
- 13) Table 4.3-2 Modify Table 4.3-2, Functional Unit 3b, The description provided above in Item 10 of Functional to clarify that contacts and contact this table is applicable. Note that the trip.
Unit 3b combinations in the logic circuit may be logic circuit represented by Table 4.3-1 simulated to operate relays in the trip Functional Unit 15 and Table 4.3-2, FuncLonal logic circuit. Refer to Pages 3/4 3-15A Units 3b, 3c, and 3d is the sanne circuit.
and 3/4 3-16 for the specific change proposed.
- 14) Table 3.3-6 Modify Table 3.3-6 to account for a fire The modification to Table 3.3-6 accounts for detector installed in the new Nuclear the fire detector installed in the new Nuclear Instrussentation panel. Refer to Instrumentation panel associated with the Page 3/4 3-28 for the specific change design change to replace the Nuclear proposed.
Instrumentation.
ATTACHMENT 1 Page 8 of 9.
Technical Specification Ch=a-es (Continued)
Item Pronosed t'han-e n===on =ad Basis for t'h_=?-e
- 15) LCO 3.7.1.1 Modify LCO 3.7.1.1 Action Statement The modification to LCO 3.7.1.1 Action Statement Action Statement to require that both the Power Range requires that the high setpoint trip associated and Intermediate Power Range Channel with both the Power Range and Intermediate Power high setpoint trips be reduced. This Range Channels be reduced and that their modification also clarifies that the respective scram logic be set for single Power Range and Intermediate Power Range channel operation.
Scram logic be set for single channel operation except as required for New instruments are provided in a design surveillance. Refer t: Page 3/4 7-1 for change to replace the Nuclear Instrumentation.
the specific change proposed.
This modification takes advantage of the ability to adjust the trip setpoint over the full range in the new instruments. This provides for additional conservatism beyond the present design.
The "**" notation is modified to add the Intermediate Power Range Channels and to clarify that the scram logic must be reset for coincidence operation to provide for surveillance. This must be done to prevent a reactor trip during a single channel surveillance. The two-hour allowance for coincidence operation is made on a per channel basis as done for Item 5 of this table.
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3 ATTACEMDIT 1 Page 9 of 9' Technical Soecification N ages (Continued) ltem Pronosed N nge
- ===on and Basis for Channe
- 16) ICO 3.10.3, Modify LCO 3.10.3 to require that the New instruments are provided in a design Surveillance high setpoint trip associated with both the change to replace the helear Instrumentation.
Requirement three Power Range. Nuclear Channels and the The modification of ICO 3.10.3 and SURVEILLANCE 4.10.3.3 three Intermediate Power Range Nuclear REQUIRDENT 4.10.3.3 takes advantage of the Channels be set at 125% of RATED THERMAL ability to adjust the trip setpoint over the POWER. SURVEILIANCE REQUIREMENT 4.10.3.3 full range in the new instruments. This is also modified to extend the present provides for additional conservatism beyond requirement to include the Intermediate the present design. The high setpoint trip Power Range Channels. Refer to is used (rather than the low and the high)
Page 3/4 10-3 for the specific change for both sets of channels fer consistency.
proposed.
- 17) LCO 3.10.4, Modify ICO 3.10.4 to require that the New instruments are provided in a design Surveillance high setpoint trip associated with both the change to replace the Nuclear Requirement three Power Range Nuclear Channels and the Instrumentation. The modification of l
4.10.4.2 three Intermediate Power Range Nuclear LCO 3.10.4 and SURVEILLANCE 1
Channels be set at 125% of RATED THERMAL REQUIRDENT 4.10.4.2 takes advantage of the i
POWER. SURVEILLANCE REQUIREMENT 4.10.4.2 ability to adjust the trip setpoint over the is also modified to include the Intermediate full range in the new instruments. This Power Range Channels. Refer to provides for additional conservatism beyond Page 3/4 10-4 for the specific change the present design. The high setpoint trip is proposed.
used (rather than the low and high) for both sets of channels for consistency.
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