ML18096A693

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Application for Amends to Licenses DPR-70 & DPR-75,modifying TS 3/4.3.1 Reactor Trip Sys Instrumentation,Lco,Action Requirements & Surveillance Requirements,Including Associated Tables
ML18096A693
Person / Time
Site: Salem  PSEG icon.png
Issue date: 05/06/1992
From: Labruna S
Public Service Enterprise Group
To:
Shared Package
ML18096A691 List:
References
NLR-N91105, NUDOCS 9205180184
Download: ML18096A693 (9)
v • d • e


Text

!.

COUNTY OF SALEM

s. LaBruna, being duly sworn according to law deposes and says:

I am Vice President - Nuclear Operations of Public Service forth in our letter dated ,

Electric and Gas Company, and as such, :;r:,find the matters set*

~m:{it;~~~*- concerning the Salem Unit Nos. 1 and 2 and H-ope Creek Generating Stations, are true to the best of my knowledge, information and belief.

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Subscribed and Sworn to before me this 1992 ELIZABETH J. KIDD Notary Public of New Jersey My Commission Expires April 25, 1995 My Commission expires on ~~~~~~~~~~~~~~~

  • Attachment 1 NLR-N91105 LCR 91-08 PROPOSED CHANGE TO TECHNICAL SPECIFICATIONS SALEM UNIT NOS. 1 AND 2 REACTOR TRIP SYSTEM INSTRUMENTATION I. Description of Change Modify Technical Specification 3/4.3.1, Reactor Trip System Instrumentation, as indicated below to provide consistency between the units, to address various administrative discrepancies, and to ensure technical accuracy.

A. Renumber Limiting Condition for Operation 3.3.1 and surveillance Requirements 4.3.1.1, 4.3.1.2, and 4.3.1.3 as 3.3.1.1, 4.3.1.1.1, 4.3.1.1.2, and 4.3.1.1.3 respectively.

(UNIT 2 ONLY)

B. TABLE 3.3-1, REACTOR TRIP SYSTEM INSTRUMENTATION

1. FUNCTIONAL UNITS 7 and 8, Overtemperature dT and Overpower dT. Remove all references to three loop operation. Remove item description for four loop operation. Align line items as required.

(UNITS 1 AND 2)

2. FUNCTIONAL UNITS 7 and 8, Overtemperature dT and Overpower dT. Change applicable ACTION from 2 to* 6.

(UNIT 1 ONLY)

3. FUNCTIONAL UNITS 16 and 17, Undervoltage - Reactor Coolant Pumps and Underfrequency - Reactor Coolant Pumps. Change the MINIMUM CHANNELS OPERABLE requirement from 4 to 3. (UNITS 1 AND 2)
4. FUNCTIONAL UNIT 18, Turbine Trip. Add line item designators for (a.) Low Autostop Oil Pressure and (b.) Turbine Stop Valve Closure. (UNIT 1 ONLY)
5. FUNCTIONAL UNIT 18b, Turbine Trip, Turbine Stop Valve Closure. Change the MINIMUM CHANNELS OPERABLE requirement from 4 to 3. (UNIT 2 ONLY) *
6. TABLE NOTATION *** Delete notation. (UNITS 1 AND 2)
7. ACTION 2C. Add the word POWER after RATED THERMAL.

(UNITS 1 AND 2)

NLR-N91105

8. ACTION 3. Move entire Action to page 3/4 3-6.

(UNIT 1 ONLY)

9. ACTION 3. Add Title ACTION 3 to associated Actions.

(UNIT 2 ONLY)

10. ACTIONS 3a, 3b, 4a, and 4b. Delete "the: prior to P-6 and "(Block of Source Range Reactor Trip) setpoint" after P-6. (UNIT 2 ONLY)
11. ACTION 8. Add ACTION 8 and mark as NOT USED, (UNITS 1 AND 2)
12. ACTION 9. Delete the current action and mark as NOT USED. (UNITS 1 AND 2)
13. ACTION 10. Change Deleted to NOT USED.

(UNITS 1 AND 2)

C. TABLE 3.3-2, REACTOR TRIP SYSTEM INSTRUMENTATION RESPONSE TIMES

1. FUNCTIONAL UNIT 21. Add Functional Unit 21, Reactor Trip Breakers, Not Applicable. (UNIT 1 ONLY)
2. FUNCTIONAL UNIT 22. Add Functional Unit 22, Automatic Trip Logic, Not Applicable. (UNIT 1 ONLY)

II. Reason and Justification for the Changes A. Renumber Limiting Condition for Operation 3.3.1 and Surveillance Requirements 4.3.1.1, 4.3.1.2, 4.3.1.3 as 3.3.1.1, 4.3.1.1.1, 4.3.1.1.2, and 4.3.1.1.3 respectively.

(UNIT 2 ONLY)

LCO and Surveillance Requirements are being renumbered to be consistent with Salem Unit 1 and to be more consistent with other specifications in the Salem Unit 2 Instrumentation Chapter. These are administrative changes.

B. TABLE 3.3-1, REACTOR TRIP SYSTEM INSTRUMENTATION

1. FUNCTIONAL UNITS 7 and 8, Overtemperature aT and Overpower aT. Remove all references to three loop operation. Remove item title for four loop operation.

Align line items as required. (UNITS 1 AND 2)

NLR-N91105

  • LCR 91-08 This change removes all references to three and four loop operation. The current Salem Accident Analysis does not support three loop operation. Three loop operation is not permitted at Salem. The proposed changes do not represent modification to plant equipment or operation.
2. FUNCTIONAL UNITS 7 and 8, Overtemperature AT and Overpower AT. Change applicable ACTION from 2 to 6.

(UNIT 1 ONLY)

Actions 2 and 6 are identical except that Action 2 contains an additional subpart "c" that only applies to Power Range Nuclear Instrumentation. Changing to Action 6 ensures the correct actions are addressed.

This change is consistent with Salem Unit 2 and Westinghouse Standard Technical Specifications. The proposed changes do not represent modifications to plant equipment or operation.

3. FUNCTIONAL UNITS 16 and 17, Undervoltage - Reactor Coolant Pumps and Underfrequency - Reactor Coolant Pumps. Change the MINIMUM CHANNELS OPERABLE requirement from 4 to 3. (UNITS 1 AND 2)

This change is necessary to apply Action 6 to these Functional Units. Action 6 allows for continued operation provided a failed channel is placed in the tripped condition within a given time period, and the Minimum Channels Operable requirement is one less than the Total Number of Channels. The proposed changes do not represent modifications to plant equipment or operation.

4. FUNCTIONAL UNIT 18, Turbine Trip. Add designators for line items: (a.) Low Autostop Oil Pressure and (b.)

Turbine Stop Valve Closure. (UNIT 1 ONLY)

Designators are being added to the two line items to ensure the Functional Units are identified properly.

The designators being added are consistent with other references in Salem Units 1 and 2 Technical Specifications. These are administrative changes.

~. -

NLR-N91105

5. FUNCTIONAL UNIT 18b, Turbine Trip, Turbine Stop Valve Closure. Change the MINIMUM CHANNELS OPERABLE requirement from 4 to 3. (UNIT 2 ONLY)

This change is necessary to apply Action 7 to this Functional Unit. Action 7 allows for continued operation provided a failed channel is placed in the tripped condition within a given time period, and the Minimum Channels Operable requirement is satisfied.

Continued operation is not possible unless the Minimum Channels Operable requirement is at least one less than the Total Number of Channels. The proposed change does not represent modifications to plant equipment or operation.

6. TABLE NOTATION*** Delete Notations (UNITS 1 AND 2)

This change removes a notation required for three loop operation. The current Salem Accident Analysis does not support three loop operation. Three loop operation is not permitted at Salem. This notation is not used.

This is an administrative change.

7. ACTION 2C. Add the word POWER after RATED THERMAL.

(UNITS 1 AND 2)

This change corrects a typographical error that omitted the word. This is an administrative change.

a. ACTION 3. Move entire Action to page 3/4 3-6.

(UNIT 1 ONLY)

This change will m1n1m1ze the potential of not reading the entire action. This is an administrative change.

9. ACTION 3. Add title ACTION 3 to the associated Actions. (UNIT 2 ONLY)

This change corrects a typographical error that omitted the title. This is an administrative change.

10. ACTIONS 3a, 3b, 4a, and 4b. Delete "the" prior to P-6 and "(Block of Source Range Reactor Trip) setpoint" after P-6. (UNIT 2 ONLY)

The description is being deleted to provide a more concise action requirement. This is consistent with Unit 1. The Reactor Trip System Interlocks are defined at the end of Table 3.3-1. These are administrative changes.

NLR-N91105

11. ACTION 8. Add ACTION 8 and mark as NOT USED.

(UNITS 1 AND 2)

Action 8 is being added to eliminate the possible confusion of an action number not being addressed.

There are no Functional Units that reference Action 8.

This is an administrative change.

12. ACTION 9. Delete the current action and mark as NOT USED. (UNITS 1 AND 2)

Action 9 was applicable for three loop operation. The current Salem Accident Analysis does not support three loop operation. Three loop operation is not permitted at Salem. There are no Functional Units that reference Action 9. This is an administrative change.

13. ACTION 10. Change Deleted to NOT USED.

(UNITS 1 AND 2)

Not used provides a more precise description. This is an administrative change.

C. TABLE 3.3-2, REACTOR TRIP SYSTEM INSTRUMENTATION RESPONSE TIMES.

1. FUNCTIONAL UNIT 21. Add Functional Unit 21, Reactor Trip Breakers, Not Applicable. (UNIT 1 ONLY)

This Functional Unit was omitted from Table 3.3-2. The change makes the table consistent with the other tables in the specification. This is an administrative change.

2. FUNCTIONAL UNIT 22. Add Functional Unit 22, Automatic Trip Logic, Not Applicable. , (UNIT 1 ONLY)

This Functional Unit was omitted from Table 3.3-2. The change makes the table consistent with the other tables in the specification. This is an administrative change.

  • J **.

NLR-N91105

  • LCR 91-08 III. Significant Hazards Consideration In accordance with 10CFR50.92, PSE&G has reviewed the proposed changes and concluded the proposed changes do not involve a significant hazards consideration because the changes would not:
1. Involve a significant increase in the probability or consequences of an accident previously analyzed.

A. Renumbering of line items within a specification is an administrative change, therefore, it would not increas~

the probability or consequences of a previously analyzed accident.

Bl. The current Salem Accident Analysis does not support three loop operation. Three loop operation is not permitted at Salem. Removal of references to three and four loop operation from the functional units for overtemperature dT and Overpower dT does not represent modifications to plant equipment or operation.

Therefore, these changes would not increase the probability or consequences of a previously analyzed accident.

B2. Changing the referenced Actions from Overtemperature dT and Overpower dT does not change the required actions.

Actions 2 and 6 are identical except that Action 2 contains an additional subpart "c" that only applies to Power Range Nuclear Instrumentation. The proposed changes do not represent modifications to plant equipment or operation. Therefore, these changes would not increase the probability or consequences of a previously analyzed accident. .

B3. Changing the Undervoltage - Reactor Coolant Pumps and Underfrequency - Reactor Coolant Pumps MINIMUM CHANNELS OPERABLE requirement from 4 to 3 is necessary to apply Action 6 to these Functional Units. Action 6 allows for continued operation provided a failed channel is placed in the tripped condition within a given time period, and the Minimum Channels Operable requirement is satisfied. Continued operation is not possible unless the Minimum Channels Operable requirement is at least one less than the Total Number of Channels. The proposed changes do not represent modifications to plant equipment or operation. Therefore, these changes would not increase the probability or consequences of a previously analyzed accident.

NLR-N91105

  • LCR 91-08 B4. Adding designators for Functional Units 18a and 18b is for identification only and is administrative.

Therefore, this change would not increase the probability or consequences of a previously analyzed accident.

B5. Changing the Turbine Trip Stop Valve Closure Minimum Channels Operable requirement from 4 to 3 is necessary to apply Action 7 to these Functional Units. Action 7 allows for continued operation provided a failed channel is placed in the tripped condition within a given time period, and the Minimum Channels Operable requirement is satisfied. Continued operation is not possible unless the Minimum Channels Operable requirement is at least one less than the Total Number

..of -Channels. The proposed changes do not represent modifications to plant equipment or operation.

Therefore, these changes would not increase the probability or consequences of a previously analyzed accident.

BG. Deleting the notation is an administrative change, because it is not referenced in the table. Therefore, this change would not increase the probability or consequences of a previously analyzed accident.

B7. Adding the word POWER after RATED THERMAL corrects a typographical error and is an administrative change.

Therefore, these changes would not increase the probability or consequences of a previously analyzed accident.

BB. Relocating part of an action to a different page is an administrative change. Therefore, this change would not increase the probability or consequences of a previously analyzed accident.

B9. Adding a title to the action is an administrative change to correct a typographical error. Therefore, these changes would not increase the probability or consequences of a previously analyzed accident.

BlO. Deleting the words that describe the P-6 interlock is an administrative change, and therefore, these changes would not increase the probability or consequences of a previously analyzed accident.

NLR-N91105

  • LCR 91-08 Bll. Adding Action 8 and designating as Not Used is an administrative change, and therefore, this change would not increase the probability or consequences of a previously analyzed accident.

B12. Deleting the current Action 9 and changing to Not Used is an administrative change. Action 9 is not referenced in the table. Therefore, these changes would not increase the probability or consequences of a previously analyzed accident.

B13. Changing Deleted to Not Used is an administrative change to provide a more clear description. Therefore, these changes would not increase the probability or consequences of a previously analyzed accident.

Cl. Adding Functional Unit 21, Reactor Trip Breakers, to Table 3.3-2 is an administrative change to ensure all functional units are addressed on each table.

Therefore, these changes would not increase the probability or consequences of a previously analyzed accident.

C2. Adding Functional Unit 22, Automatic Trip Logic, to Table 3.3-2 is an administrative change to ensure all functional units are addressed on each table.

Therefore, these changes would not increase the probability or consequences of a previously analyzed accident.

2. Create the possibility of a new or different kind of accident.

As stated above, the proposed changes are either administrative, or do not represent modifications to plant equipment or operation. Therefore, there can be no impact on plant response to the point where a different accident is created.

3. Involve a significant reduction in a margin of safety.

As stated above, the proposed changes are either administrative, or do not represent modifications to plant equipment or operation. Therefore, there can be no reduction in any margin of safety.

V. Conclusions Based on the information presented above, PSE&G has concluded there is no significant hazards consideration.

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