ML20041C533
| ML20041C533 | |
| Person / Time | |
|---|---|
| Site: | Maine Yankee |
| Issue date: | 02/22/1982 |
| From: | Garrity J Maine Yankee |
| To: | Haynes R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| Shared Package | |
| ML20041C534 | List: |
| References | |
| CAL-82-01, CAL-82-1, JHG-82-39, MN-82-30, NUDOCS 8203020213 | |
| Download: ML20041C533 (7) | |
Text
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'%==us b February 22, 1982 JHG-82-39 MN-82-30 C
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m'UD United States Nuclear Regulatory Commission g90.1
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Region I 2L ikg:k/dM ff 631 Park Avenue King of Prussia, Pennsylvania 19406 g
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.;q Attention: Ronald C. Haynes
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Regional Administrator RO M
References:
(a) License No. DPR-36 (Docket No. 50-309)
(b) USNRC letter to MYAPCo dated January 29, 1982, Confirmatory Action Letter 82-01
Subject:
Safety Injection Actuation Signal - Redundant Logic Relays and Power Supplies
Dear Sir:
Reference (b) requested Maine Yankee to submit a description of the design change to provide redundant logic relays and redundant power supplies.
The need for this change resulted from design review which found the automatic safety injection actuation logic to be susceptible to single failure and/or loss of power events under certain postulated accident conditions..
The design changes are described and shown in the circles on the attachments.
We trust this information is satisfactory.
Should you have any further questions, please feel free to contact us.
Sincerely yours, MAINE YANKEE ATOMIC POWER COMPANY p00 0
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John H. Garrity, Senio Director I(
Nuclear Engineering and Licensing JHG/bjp Attachments - EDCR 82-7 Insic1?rI 0, C2IGIN E (hartifled27_
M-1" 8203020213 820222 PDR ADOCK 05000309 P
.b.RAU r0ax WE_iOO_i REVISION 2 i
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...__._ _ CNG-INEER-ING -
DESIGN CHANGE REQUEST.
EDCR N0.:
82-7 PLANT: MAINE YANKEE NUCLEAR SERVICES DIVISION Sa61 g,o,f719 YANKEE ATOMIC ELECTRIC C0.
EDCR TITLE:
SAFETY INJECTION ACTUATION LOGIC MODIFICATION
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D COGNIZANT ENGINEER DATE ENGINEERING PREPARATION GROUP MANAGER DATE m,
w AND REVIEW DEPARTMENT MANAGER DATE OPERATIONAL QA DEPT.
REVIEW OQA0 MANAGER DATE
~"ERATIONAL PROJECTS
./T. ACCEPTANCE OPERATIONAL PROJECT MANAGER DATE s
4 EDCR 82-7 Page 2 of 6 MY EDCR 82-7 DETAILED SAFETY INJECTION ACTUATION LOGIC MODIFICATION
1.0 REFERENCES
(a) USNRC Letter to Maine Yankee, dated January 29, 1982, Confirmatory Action Letter 82-01.
(b) Maine Yankee Letter to the USNRC, dated February 2, 1982, #MN-82-20.
2.0 ENCLOSURES (A)
Revised Drawings (B) Revised FSAR Drawing
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(C) Reference (t) O D
3.0 ORGANIZATIONS RESPONSIBLE FOR THE DETAILED DESIGN The Ins trument and Control Engineering Group of the Plant Engineering Department has lead responsibility with input from Electrical and Mechanical Engineering.
4.0 COST ESTIMATE Mate rials
$ 500.00 Ins talla tion 2,000.00 NSD Engineering 5,960.00 Total
$8,460.00 5.0 S CHEDU LE 5.1 Equipment Procurement Equipment required for this modification is available in the storeroom at the plant.
FOR INFGRMATiON Q.1 V DNAEIr EDCR 82-7 l
Page 3 of 6 I*
5.2 Implementation
Implementation of this FDCR is scheduled for the l
March 1982 outage.
i 6.0 REASON FOR CHANGE During a design review of the Safety Injection actuation logic, the safety injection actuation logic was found to be susceptible to single failures and/or loss of power events.
This change will correct that problem and provide additional protection for steam generator tube rupture or steam line breaks.
7.0 DESCRIPTION
OF CHANGE This change will add redundant actuation logic circuits to the existing E
This will be done by using existing spare relay contacts off the O
system.
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pressurizer pressure bistable indicators and existing spare relay contacts off the high containment pressure switches. These relay
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-J two out of four logic contacts will be used to make two new redundant L.I O
These new circuits vill drive two new relays which will trip c
circuits.
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both trains of the Safety Injection System. A loss of power and/or a o
L.t single f alure will not prevent this new sys tem from operating.
Manual actuation of the system will remain the same.
8.0 DESIGN CRITERIA ANSI N45.2.2-1972, " Packaging, Shipping, 8.1 Quality Assurance:
Receiving, Storage, ano Handling of Items for Nuclear Power Plants."
8.2 Technic al :
IEEE Criteria No. 279, 1968, " Criteria for Protection Sys tems for Nuclear Power Genera ting Sta tions."
FOR INFO'?.e.iAlied DRAEI EDCR 82-7 Page 4 of 6 9.0 EQUIPMENT PROCUREMENT INFORMATION 9.1 Spe ci fic a tion :
Equipment used in this design was procured to meet requirements for mounting in the main control board.
9.2 Bill of Materials:
Item Quan ti ty Description 0
1 2
CE HFA Relays, 6 N.,[ C on ta c t s,
125 VDC - Stock 2
100 f t.
Control Board SIS Wire-Stock 10.0 Drawings Drawing No.
Title 11550-ESK-7H /
Elem. Diag. Aux. Sys tem Control SH.8 (SIAS Logic Set Up Circuits) 11550-ESK-7J /
Elem. Diag. Aux. Sys tem Control SH.9 11550-ESK-7K '
Elem. Diag. Aux. System Control SH.10, 11550-FE-3DAJ /
Wir. Diagram - Rear MTD EQUIP. SH.28 Main Control Board Section "C"
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Wir. Diagram - Rear MTD EQUIP. SH.27 ll550-FE-3DAH Main Control Board Section "C" b
/4 11550-FE-3D p /
External Conn Diagram SH.2Y, Main Control Board Section "C" 11550-FE-3DM Wir. Diagram - Front MTD EQUIP. SH.21 Main Control Board Section "C" 11550-ESK-4P /
Outline Main Control Board SH.14, Vertical Rear MY-E-50-014 SH.9A Sa fety Injection Actuation - Nuclear Sa fety A Re la ted
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EOR INFORMAW ppg ONLY.
EDCR 82-7 Page 5 of 6 11.0 CALCULATIONS AND ANALYSES A seismic analysis will be done by the MEG of PED and will be complete prior to declaring this design operational.
12.0 PROCEDURES 12.1 Welding:
Not Applicable
- 12. 2 NDE : Not Applicable 12.3 Ins tallation and Tes t:
Installation and test will be done per site generated procedures.
12.4 Other: None 13.0 FSAR/FHSR PAGES AFFECTED Figure 7.3-1 (See Enclosure B).
14.0 LICENSING 14.1 Technical Specification Pages Aff ected:
Not Applicable.
14.2 Proposed Change Letter:
Not Applicable.
15.0 SAFETY EVALUATION 15.1 The sa fety injection actuation system is a safety class system. The logic and relays are also part of that safety class sys tem.
n ew The addition of a redundant set of actuation logic circuits will increase the reliability of the SIAS Sys tem.
A loss of control power, or a single failure of either the;D hbhpressurizer pressure actuation relay or a high containment pressure actuation relay, will not r esul t in a loss of automatic safety injection actuation.
E0R JNFORMAll0N DR g ONLY l
EDCR 82-7 Page 6 of 6 15.2 The new redundant actuation logic is designed to provide assurance that a safety injection actuation will occur when required.
In light of the above discussion, this EDCR does not impair the safety to the general public, in that it does not:
1.
Increase the probability of occurrence of a previously evaluated accident; 2.
Create the possibility of an unreviewed accident; or 3.
Reduce the margin of safety as defined in Technical Speci fica tions.
15.3
Conclusion:
The proposed modification has been analyzed to assure tha t it does not create any unreviewed safety questions as defined in 10CFR50.59(a)(2).
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