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BEFORE THE UNITED STATES NUCLEAR REGULATORY COMMISSION LICENSE NO. NPF-13 DOCKET No. 50-416 IN THE MATTER OF MISSISSIPPI POWER & LIGHT COMPANY and MIDDLE SOUTH ENERGY, INC. | |||
and SOUTH MISSISSIPPI ELECTRIC POWER ASSOCIATION AFFIRMATION I, J. P. McGaughy, Jr., being duly sworn, stated that I am Vice President | |||
- Nuclear of Mississippi Power & Light Company; that on behalf of Mississippi Power & Light Company, Middle South Energy, Inc., and South Mississippi Electric Power Association I am authorized by Mississippi Power & Light Company to sign and file with the Nuclear Regulatory Commission, this application for amendaent of the Operating License of the Grand Gulf Nuclear Station; that I signed this application as Vice President - Nuclear of Mississippi Power & Light Company; and that the statements made and the matters set forth therein are true and correct to the best of my knowledge, information and belief. | |||
] t I | |||
~ | |||
h A | |||
. ~P'.' McGaughg/ ff." | |||
STATE OF MISSISSIPPI COUNTY OF HINDS SUBSCRIBEDANDSWORNT0befoeme,aNogaryPublic,inandforthe County and State above named, this /d day of d u ,~l d , 1983. | |||
(SEAL) 8312210159 831214 PDR ADOCK 05000416 | |||
~ | |||
tws &Ye- | |||
[ Notary Public v | |||
. g My conmission expires: | |||
My Commission bpkes Ses. 2 0 1987, F12sp | |||
DEPOSIT GUARANTY N ATIONAL BANK 85 543 Jackson, Mississippl 39205 W | |||
, MIDDLE SOUTH ENERGY, INC. | |||
P.O. BOX 1640 | |||
* JACKSON, MISSISStPPI 39205 CHECK NO.12-0009 h | |||
JOINT CONSTRUCTION ACCOUNT H | |||
hg C\0A g | |||
E g, l OOL LA PS CENTS 12 02 83 l $1,200iOO PAY p q TO THE U.S. NUCLEAR REGULATORY COMM l | |||
'" ' WASHINGTON, D.C. 20555 ;,;i;;,; ;g ,, | |||
g ,, | |||
L _1 ., | |||
: 2. . , , | |||
*"~"*" " | |||
POO 30 3 3Ee a:OE 5 30 5t.3Es: e 2 3= 59 5= 2Er | |||
. - - . - _=. . _ . - | |||
TRANSMITTAL OF PROPOSED CHANCES TO GRAND GULF TECHNICAL SPECIFICATIONS | |||
==SUBJECT:== | |||
NS-83/43 ) | |||
Technical Specification Table 4.3.2.1-1, pages 3/4 3-20 through 3/4 3-23a. | |||
! DISCUSSION: Mississippi Power & Light (MP&L) Company committed in letter AECM-83/0640 dated October 14, 1983 to propose certain changes to the Technical Specifications. The two changes proposed herein to Technical Specification Table 4.3.2.1-1, Isolation Actuation Instrumentation Surveilhnee Requirements, are submitted in satisfaction of that commitment: | |||
: 1) Footnote (c) which requires trip unit calibration at least once per 31 days is added to all Rosemont trip units which do not presently refer to footnote (c). This change involves items 1.a. 1.d. 2.a. 2.c, 2.d. 2.e, 3.a. 3.b. | |||
4.e. 5.a. 5.b. 5.c. 5.k. 6.c, 6.d. and 6.e. | |||
: 2) The present channel calibration frequency for Riley Temperature Switches is at least once per 18 months (R). | |||
The proposed change is to at least once per 366 days (A). | |||
Items affected by this change are 2.f 2.g 4.c. 4.d. 4.f. | |||
4.g. 5.d. 5.e, 5.f. 5.g. 5.1, 5.j, 6.a. and 6.b. | |||
JUSTIFICATION: Technical Specification Tables 4.3.1.1-1 and 4.3.3.1-1 for the Reactor Protection System and the Energency Core Cooling Systems require monthly calibration frequencies for Rosemont Trip Units which exceeds the six month frequency recensended by the manufacturer. This monthly calibration frequency is not specified for all the Rosemont Trip Units associated with instrumentation in Table 4.3.2.1-1 (Isolation Actuation Instrumentation). Although not required by Tech Specs, all l Rosemont Trip Units are calibrated on a monthly frequency. To | |||
( ensure consistency among the Technical Specification Instru-mentation Tables, changes to Table 4.3.2.1-1 are requested to add the monthly calibratica of all Rosemont Trip Units to the Tech Specs (i.e. , the setpoints will be verified and adjusted as necessary in sceordance with Technical Specification requirements). | |||
Technical Specification Table 4.3.2.1-1 for the Isolation Actuation Instrumentation presently requires channel calibra-tion on a refueling frequency for temperature monitoring instrumentation. The present refueling calibration frequency corresponds to the calibration frequency assumed in the setpoint methodology by the Nuclear Steam Supply System (NSSS) vendor. However, the temperature switch manufacturer (Riley) recommends a yearly frequency for temperature switch calibra-tion. MP&L is currently meeting the yearly calibration recommendation, however, to promote consistency between j annufacturer's recommendations and the Technical Specifica-i tions, the changes proposed herein will require annual instead i of refueling channel calibration frequency for Riley tempera-i ture switches. | |||
M84rgi | |||
SIGNIFICANT HAZARDS CONSIDERATION: | |||
These proposed changes are made to promote consistency among Technical Specification Instrumentation Tables and between . | |||
manufacturer's recommended calibration frequency and the Technical Specification requirements. | |||
Rosemont Trip Units presently require calibration at least once per 31 days in Technical Specification Tables 4.3.1.1-1 and 4.3.3.1-1. Adding this 31 day calibration frequancy to all Rosemont Trip Units associated with instrumentation in Table 4.3.2.1-1 promotes consistency between these tables. | |||
The manufacturer of the temperature switches listed in Table 4.3.2.1-1 recommends a yearly calibration frequency. The proposed change to an annual calibration frequency promotes consistency between manufacturer's recommendations and Technical Specification requirements. The proposed annual calibration frequency is more conservative than the NSSS vendor's assumed setpoint methodology calibration frequency of at least once per 18 months. | |||
These proposed changes increase the surveillance requirements for the Rosemont Trip Units and Riley Temperature Switches listed in Table 4.3.2.1-1. As such, this change does not involve the reduction of safety margins and no significant increase in the probability or consequences of an accident previously evaluated is involved nor is the pessibility of a new or different kind of accident from any accident previously evaluated created. Thus the proposed change to the Technical Specification does not involve any significant hazards consideration. | |||
M84rg2 | |||
_ _ _ . , _ . _ - . _ _ . . _ _. ,__}} |
Revision as of 23:38, 13 May 2020
ML20083B443 | |
Person / Time | |
---|---|
Site: | Grand Gulf |
Issue date: | 12/14/1983 |
From: | Mcgaughy J MISSISSIPPI POWER & LIGHT CO. |
To: | |
Shared Package | |
ML20083B436 | List: |
References | |
NUDOCS 8312210159 | |
Download: ML20083B443 (4) | |
Text
--
BEFORE THE UNITED STATES NUCLEAR REGULATORY COMMISSION LICENSE NO. NPF-13 DOCKET No. 50-416 IN THE MATTER OF MISSISSIPPI POWER & LIGHT COMPANY and MIDDLE SOUTH ENERGY, INC.
and SOUTH MISSISSIPPI ELECTRIC POWER ASSOCIATION AFFIRMATION I, J. P. McGaughy, Jr., being duly sworn, stated that I am Vice President
- Nuclear of Mississippi Power & Light Company; that on behalf of Mississippi Power & Light Company, Middle South Energy, Inc., and South Mississippi Electric Power Association I am authorized by Mississippi Power & Light Company to sign and file with the Nuclear Regulatory Commission, this application for amendaent of the Operating License of the Grand Gulf Nuclear Station; that I signed this application as Vice President - Nuclear of Mississippi Power & Light Company; and that the statements made and the matters set forth therein are true and correct to the best of my knowledge, information and belief.
] t I
~
h A
. ~P'.' McGaughg/ ff."
STATE OF MISSISSIPPI COUNTY OF HINDS SUBSCRIBEDANDSWORNT0befoeme,aNogaryPublic,inandforthe County and State above named, this /d day of d u ,~l d , 1983.
(SEAL) 8312210159 831214 PDR ADOCK 05000416
~
tws &Ye-
[ Notary Public v
. g My conmission expires:
My Commission bpkes Ses. 2 0 1987, F12sp
DEPOSIT GUARANTY N ATIONAL BANK 85 543 Jackson, Mississippl 39205 W
, MIDDLE SOUTH ENERGY, INC.
P.O. BOX 1640
- JACKSON, MISSISStPPI 39205 CHECK NO.12-0009 h
JOINT CONSTRUCTION ACCOUNT H
hg C\0A g
E g, l OOL LA PS CENTS 12 02 83 l $1,200iOO PAY p q TO THE U.S. NUCLEAR REGULATORY COMM l
'" ' WASHINGTON, D.C. 20555 ;,;i;;,; ;g ,,
g ,,
L _1 .,
- 2. . , ,
- "~"*" "
POO 30 3 3Ee a:OE 5 30 5t.3Es: e 2 3= 59 5= 2Er
. - - . - _=. . _ . -
TRANSMITTAL OF PROPOSED CHANCES TO GRAND GULF TECHNICAL SPECIFICATIONS
SUBJECT:
NS-83/43 )
Technical Specification Table 4.3.2.1-1, pages 3/4 3-20 through 3/4 3-23a.
! DISCUSSION: Mississippi Power & Light (MP&L) Company committed in letter AECM-83/0640 dated October 14, 1983 to propose certain changes to the Technical Specifications. The two changes proposed herein to Technical Specification Table 4.3.2.1-1, Isolation Actuation Instrumentation Surveilhnee Requirements, are submitted in satisfaction of that commitment:
- 1) Footnote (c) which requires trip unit calibration at least once per 31 days is added to all Rosemont trip units which do not presently refer to footnote (c). This change involves items 1.a. 1.d. 2.a. 2.c, 2.d. 2.e, 3.a. 3.b.
4.e. 5.a. 5.b. 5.c. 5.k. 6.c, 6.d. and 6.e.
- 2) The present channel calibration frequency for Riley Temperature Switches is at least once per 18 months (R).
The proposed change is to at least once per 366 days (A).
Items affected by this change are 2.f 2.g 4.c. 4.d. 4.f.
4.g. 5.d. 5.e, 5.f. 5.g. 5.1, 5.j, 6.a. and 6.b.
JUSTIFICATION: Technical Specification Tables 4.3.1.1-1 and 4.3.3.1-1 for the Reactor Protection System and the Energency Core Cooling Systems require monthly calibration frequencies for Rosemont Trip Units which exceeds the six month frequency recensended by the manufacturer. This monthly calibration frequency is not specified for all the Rosemont Trip Units associated with instrumentation in Table 4.3.2.1-1 (Isolation Actuation Instrumentation). Although not required by Tech Specs, all l Rosemont Trip Units are calibrated on a monthly frequency. To
( ensure consistency among the Technical Specification Instru-mentation Tables, changes to Table 4.3.2.1-1 are requested to add the monthly calibratica of all Rosemont Trip Units to the Tech Specs (i.e. , the setpoints will be verified and adjusted as necessary in sceordance with Technical Specification requirements).
Technical Specification Table 4.3.2.1-1 for the Isolation Actuation Instrumentation presently requires channel calibra-tion on a refueling frequency for temperature monitoring instrumentation. The present refueling calibration frequency corresponds to the calibration frequency assumed in the setpoint methodology by the Nuclear Steam Supply System (NSSS) vendor. However, the temperature switch manufacturer (Riley) recommends a yearly frequency for temperature switch calibra-tion. MP&L is currently meeting the yearly calibration recommendation, however, to promote consistency between j annufacturer's recommendations and the Technical Specifica-i tions, the changes proposed herein will require annual instead i of refueling channel calibration frequency for Riley tempera-i ture switches.
M84rgi
SIGNIFICANT HAZARDS CONSIDERATION:
These proposed changes are made to promote consistency among Technical Specification Instrumentation Tables and between .
manufacturer's recommended calibration frequency and the Technical Specification requirements.
Rosemont Trip Units presently require calibration at least once per 31 days in Technical Specification Tables 4.3.1.1-1 and 4.3.3.1-1. Adding this 31 day calibration frequancy to all Rosemont Trip Units associated with instrumentation in Table 4.3.2.1-1 promotes consistency between these tables.
The manufacturer of the temperature switches listed in Table 4.3.2.1-1 recommends a yearly calibration frequency. The proposed change to an annual calibration frequency promotes consistency between manufacturer's recommendations and Technical Specification requirements. The proposed annual calibration frequency is more conservative than the NSSS vendor's assumed setpoint methodology calibration frequency of at least once per 18 months.
These proposed changes increase the surveillance requirements for the Rosemont Trip Units and Riley Temperature Switches listed in Table 4.3.2.1-1. As such, this change does not involve the reduction of safety margins and no significant increase in the probability or consequences of an accident previously evaluated is involved nor is the pessibility of a new or different kind of accident from any accident previously evaluated created. Thus the proposed change to the Technical Specification does not involve any significant hazards consideration.
M84rg2
_ _ _ . , _ . _ - . _ _ . . _ _. ,__