ML17300A844
| ML17300A844 | |
| Person / Time | |
|---|---|
| Site: | Palo Verde  |
| Issue date: | 05/11/1987 |
| From: | Haynes J ARIZONA PUBLIC SERVICE CO. (FORMERLY ARIZONA NUCLEAR |
| To: | NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM) |
| Shared Package | |
| ML17300A845 | List: |
| References | |
| 161-00205-JGH-B, 161-205-JGH-B, TAC-65697, NUDOCS 8705220167 | |
| Download: ML17300A844 (10) | |
Text
REQULATO INFORMATION DISTRIBUTION TEN (RIDS)
, ACCESSION NBR: 8705220167 DOC. DATE: 87/05/11 NOTARIZED:
NO DOCKET FACIL:STN-50-528 Palo Verde Nuclear Station.
Unit i. Arizona Pub li 05000528 AUTH. NAME AUTHOR AFFILIATION HAYNES> J. Q.
Arizona. Nuclear Power Prospect (formerly Arizona Public Serv RECIP. NAME RECIPIENT AFFILIATION Document Control Branch (Document Control Desk)
SUB JECT:
App 1ication for amend to License NPF-41
> revising Tech Specs to incorporate allowances for manually reducing low pressuri zer pressure 8c loe steam generator pressure trip setpoints. Fee paid.
DISTRIBUTION CODE:
A001D COPIES RECEIVED: LTR ENCL SI ZE:
TITLE:
OR Submittal:
General Distribution NOTES: Standardized plant. N. Davis> NNR: 1Cg.
05000528 RECIPIENT ID CODE/NAME PD5 LA LICITRA>E INTERNAL: ACRS NRR/DEST/ADE NRR/DOEA/TSB OQC/HDS1 EXTERNAL EGhQ BRUSKE> S NRC PDR NOTES:
COPIES LTTR ENCL 0
1 1
6 6
1 1
1 1
0 1
1 1
REC IPIENT ID CODE/NAME PD5 PD DAVIS> M ARM/DAF/LFMB NRR/DEST/ADS NRR /P MAS/ILRB 01 LPDR NSIC COP IES LTTR ENCL 5
5 1
1 0
1 1
1 1
1 1
1 1
TOTAL NUMBER OF COPlES REQUIRED:
LTTR 26 ENCL 23
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-c Arizona Nuclear Power Project P.o. BOX 52034 e
PHOENIX, ARIZONA85072-2034 Mav 11 1987 161-00505-JGH/BJA U.
S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, D. C. 20555
Subject:
Palo Verde Nuclear Generating Statio'n (PVNGS)
Unit 1 Docket No.
STN 50-528 (License No. NPF-41)
Proposed Technical Specification Change-Mode Applicability for Manual Setpoint Adjustments File: 87-E-056-026 87-F-005-419.05
Dear Sirs:
The purpose of this letter is to request a
change to the PVNGS Unit 1
Technical Specifications.
The proposed change revises Table Notations (2) and (3) of Technical Specification Table 2.2-1 and Table Notations (a) and (b) of Table 3.3-3 to change the applicable modes from "Modes 3-6" to "Modes 3-4".
These table notations provide the allowances for manually reducing the low pressurizer pressure and low steam generator pressure trip setpoints.
Implementation of this change will ensure consistency throughout the Technical Specifications and will update the PVNGS Unit 1
Technical Specifications to agree with those of Units 2 and 3.
Enclosed within this change request package are the following:
A.
B.
C.
D.
E.
F.
G.
Description of the Proposed Change.
Purpose of the Technical Specification.
Need for the Technical Specification Amendment.
Basis for No Significant Hazards Consideration.
Safety Evaluation for the Proposed Change.
Environmental Impact Consideration Determination.
Marked-up Technical Specification Change Page.
8705220167 870511 PDR ADOCN 05000528 P
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USNRC Document Control Desk Proposed Technical Specification Change-Mode Applicability for Manual Setpoint Adjustments 161-00205 Page 2
Pursuant to the requirements of 10CFR50.91(b)(l),
and by copy of this
- letter, we have notified the Arizona Radiation Regulatory Agency of this request for a Technical Specification change.
In accordance with the requirements of 10CFR170.12(c),
the license amendment application fee of
$150.00 has been forwarded to the USNRC License Fee Management Coordinator.
Very truly yours, J.
G. Haynes Vice President Nuclear Production JGH/BJA/ls Attachment cc:
0.
M. De Michele E. E.
Van Brunt, Jr.
G.
W. Knighton E.
A.Licitra R.
P.
Zimmerman Director ARRA J.
B. Martin A. C. Gehr (all w/a)
A.
DESCRIPTION OF THE PROPOSED CHANGE The purpose of this change is to revise Table Notations (2) and (3) of Technical Specification Table 2.2-1 and Table Notations (a) and (b) of Table 3.3-3 to change the applicable modes from "Modes 3-6" to "Modes 3-4".
These Table Notations delineate the allowances for manually reducing the low pressurizer pressure and low steam generator pressure trip setpoints as the pressures are reduced.
The low pressurizer pressure trip provides a
reactor trip and safety injection actuation in the event of a decrease in the Reactor Coolant System (RCS) inventory or in the event of an increase in heat removal by the secondary system.
The low steam generator pressure trip provides a
reactor trip and main steam isolation actuation in the event of an increase in heat removal by the secondary system.
These reactor trips and Engineered Safety Features Actuation System (ESFAS) actuations are discussed further in Sections 7.2 and 7.3 of CESSAR.
This change has already been made to the PVNGS Units 2, and 3
Technical Specifications.
The change was initially made, at the request of the NRC staff, during the PVNGS Unit 2 Technical Specification review process.
The applicable modes of Table, Notations (2) and (3) of Technical Specification Table 2.2-1 and Table Notations (a) and (b) of Table 3.3-3 are being changed to provide consistency between these tables and Technical Specification Limiting Conditions for Operation (LCOs) 3.3.1 and 3.3.2.
These LCOs only require the low pressurizer pressure and low steam generator pressure trip functions to be operable in Modes 1 through 4.
This is consistent with the safety analysis assumptions for these trip functions.
Therefore, since these protection functions are only required to be operable in Modes 1 through 4, there does not need to be any allowance in Technical Specification Tables 2.2-1 or 3.3-3 for manually reducing the trip setpoints while in Modes 5 or 6.
B.
PURPOSE OF THE TECHNICAL SPECIFICATION Table Notations (2) and (3) of Technical Specification Table 2.2-1 and Table Notations (a) and (b) of Table 3.3-3 provide the allowances for manually reducing the low pressurizer pressure and low steam generator pressure trip setpoints as the plant is being shutdown.
As described in Section 7.2 of
- CESSAR, the low pressurizer pressure and low steam generator pressure trips employ a variable setpoint that is manually reduced by the control room operator as the RCS pressure and/or secondary system pressure are decreased during plant shutdown.
C.
NEED FOR THE TECHNICAL SPECIFICATION AMENDMENT This proposed change will provide for consistency between the subject Table Notations and LCOs 3.3.1 and 3.3.2.
These LCOs only require the low pressurizer pressure and low steam generator pressure trips to be operable in Modes 1
through 4.
Additionally, this change will provide for consistency between the Units 1, 2 and 3
Technical Specifications since the Units 2 and 3
Technical Specification have already incorporated this change.
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DE BASIS FOR NO SIGNI ANT HAZARDS CONSIDERATION The proposed changes do not involve a
significant hazards consideration because:
(A)
Operation of Palo Verde Unit 1 in accordance with this change would not:
1)
Involve a" significant increase in the probability or consequences of an accident previously evaluated.
Basis:
The change will revise Table Notations (2) and (3) of
'echnical Specification Table 2.2-'1 and Table Notations (a) and (b) of Table 3.3-3 by changing the applicable modes from "Modes 3-6" to "Modes 3-4".
This will achieve consistency between this table and LCOs 3.3.1 and 3.3.2 which only require the low pressurizer pressure and low steam generator pressure trips to be operable in Modes 1-4.
- Thus, these trips are not required to be operable in Modes 5 and 6.
2)
Create the possibility of a new or different kind of accident from any accident previously analyzed.
Basis:
These changes will not reduce the coverage (in terms of plant operational modes) that is provided by the low pressurizer pressure and low steam generator pressure trip functions.
These trips are currently required to be operable in Modes 1 through 4 and these changes do not reduce this mode applicability.
3)
Involve a significant reduction in a margin of safety.
Basis:
The proposed changes will only revise an administrative limit on when the subject trip setpoints may be reduced during depressurization of the primary and secondary systems.
The proposed changes do not in any way reduce the protection that is provided by these trip functions.
(B)
The proposed amendment matches one of the examples given in 51FR7751 of amendments that do not involve a
significant hazards consideration.
Specifically, the proposed amendment is a change to achieve consistency throughout the Technical Specifications.
The change to Table Notations (2) and (3) of Technical Specification Table 2.2-1 and Table Notations (a) and (b) of Table 3.3-3 is a purely administrative change which will provide consistency between this table and Technical Specification LCOs 3.3.1 and 3.3.2.
These LCOs only require the low pressurizer pressure and low steam generator pressure trips to be operable in Modes 1 through 4.
E.
SAFETY EVALUATION FOR THE PROPOSED CHANGE The proposed Technical Specification changes will not increase the probability of occurrence or the consequences of an accident or malfunction of equipment important to safety previously evaluated in the FSAR.
This change will revise Table Notations (2) and (3) of Technical Specification Table 2.2-1 and Table
Notations (a) and (b) of Table 3.3-3 by changing the applicable modes from "Modes 3-6" To "Modes 3-4".
This change is being made in order to achieve consistency between this table and Limiting Conditions for Operation (LCOs) 3.3.1 and 3.3.2.
These LCOs only require the low pressurizer pressure trip (reactor trip
" and safety injection actuation) and the low steam generator pressure tr'ip (reactor trip and main steam isolation actuation) to be operable in Modes 1 through 4.
- Thus, the trip setpoint reduction allowance in Modes 5
and 6 is not necessary because the trips are not required to be operable in Modes'5 and 6.
The proposed Technical Specification changes will not create the possibility for an accident or malfunction of a
different type than any evaluated previously in the FSAR.
This change will not reduce the coverage (in terms of plant operational modes) that is currently provided by the low pressurizer pressure and low steam generator pressure trip functions.
These trips are currently required to be operable in Modes 1
through 4 and the proposed Technical Specification changes do not effect these protective functions.
The proposed Technical Specification changes will not reduce the margin of safety as defined in the basis for any Technical Specification.
The proposed changes will only revise an administrative limit on when the subject trip setpoints may be reduced during depressurization of the primary and secondary systems.
The changes do not in any way reduce the protection that is provided by these trip functions in Modes 1 through 4.
F.
ENVIRONMENTAL IMPACT CONSIDERATION DETERMINATION The proposed change does not involve an unreviewed environmental question because operation of Palo Verde Unit 1 in accordance with this change would not:
1.
Result in a
significant increase in any adverse environmental impact previously evaluated in the Final Environmental Statement (FES) as modified by the staff's testimony to the Atomic Safety and Licensing
- Board, Supplements to the FES, Environmental Impact appraisals or in any decisions of the Atomic Safety and Licensing Board; or 2.
Result in a significant change in effluents or power levels; or 3.
Results in matters not previously reviewed in the licensing basis for PVNGS which may have a significant environmental impact.
G.
MARKED-UP TECHNICAL SPECIFICATION CHANGE PAGES See attached marked up Technical Specification pages for Palo Verde Unit 1.