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a c' [ %o, UNITED STATES j - | |||
'#I j NUCLE AR REGULATORY COMMISSION w ASHINGToN, D. C. 20$$$ | |||
k ..... / Cetober 20, 1988 Docket No. 50-277/278 Facility: Peach Bottom Atomic power Station, Units 2 and 3 Littnsee: Philadelphia Electric Cr.aany | |||
==SUBJECT:== | |||
==SUMMARY== | |||
OF MEETING ON PROTECT!9N FROM DEGRADE 0 VOLTAGE CONDITIONS On October 19, 1688 the NRC staff met with representatives of the Philadelphia Electric Company in Rockville, Maryland. The meeting was for the purpose of discussing the licensee's submittal of September 7, 1988 on this subject. A list of attendees is provided in Enclosure 1. The agenda is provided in Enclosure 2. The meeting resulted in the following disposition for each of the agenda items. | |||
With respect to items 1 and 6. PEco agreed to provide a sumary of the voltage study with emphasis on a description of the input parameters to the study and a discussion of the adequacy of the voltage protet. tion at the 120 volt level. | |||
With respect to item 2. PECo agreed to provide a submittal describing the verification of the computer model used in the study; data musured in the plant will be compared to rodel predictions. In response to items 3 and 9 PECo agreed to identify the documents which centrol the timing of the addition of these lor.ds onto the ESF buses, and to include the timing of these loads in the Updated Final Safety Analysis Report. | |||
In response to it*m 4. PECo ccmitted to rivise its response to reflect the use by the load dispatcher of the information now available from voltage monitors at the north subitation to avoid unnecessarily degraded voltage conditions at the Peach Bottom plant. The response is to also include plans for action when the north substation grid voltage monitoring capability is not available. | |||
In re:ponse to item 5, the option of selecting alternate Core Spray Pump motor designs was discussed with the conclusion being that this was not practical due ' | |||
to the inability of an alternate motor selection by itself to completely meet the needs of the system and also riue to the considerable margins that continue to be available with the present motor design used in accordance with the licensee's recent proposal. No further information was requested. | |||
In response to item 7. PECo indicated that tolarances or the timing setpoints for load additions do reflect the manufacturer's recommended worst case tolerances plus measurement error plus additional margin for contingency i purposes. No further infonration was requested. i 1 | |||
In response to item 8. PECo comitted to describe in further detail its plans for taking inplant data and also for sampling from procurement stores to verify with sufficient confidence that these components will function as l described in the licensee's submittal. ' | |||
l S310270028 8910:0 (DR F | |||
ADOCK 05000277 FDC | |||
F. .o . | |||
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In sumary, the staff requested that PECo submit an integrated response i describing these comitments and the plans for implementing them. ! | |||
VRober hE. d /Il .s / 4 Martin Project Manager Project Directorate 1 2 | |||
( | |||
Division of Reactor Projects 1/l! i Office of Nuclear Reactor Regulation ; | |||
i | |||
==Enclosures:== | |||
As stated cc: Licensee / Applicant & Service List ! | |||
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. l in sumary. the staff requested that PECo submit an integrated response describing these comitments and the plans for implementing them. | |||
/s/ | |||
Robert E. Martin, Project Manager P"qject Directorate I-2 Duision of Reactor Projects I/l! | |||
Office of Nuclear Peactor Regulation | |||
==Enclosures:== | |||
As stated cc: Licensee / Applicant & Service List DISTRIBUTION Docket F11e ;~ | |||
HRC PDR Local POR PDI-2 Reading WButler RMartin/RClark OGC EJordan BGrimes NRC Participants ACRS (10) | |||
HBClayton CPorris DTondi FRosa 1 L in c:llt i | |||
i I | |||
I L | |||
{q')- | |||
Of .?/fM' PDI-2/0 i~' | |||
: f. rt'in:er FButler d | |||
/g/Zo/88 c g/88 ' | |||
i'. | |||
Mr. William M. Alden Peach Bottom Atomic Power Station, Philadelphia Electric Company Units 2 and 3 cc: | |||
Trcy B. Conner, Jr. , Esq. A. Heics. Coordinator 1747 Pennsylvania Aver.ue, N.W. I- ' | |||
wania State Clearinghouse Washington, D.C. 20006 e aor's Office of State Planning | |||
.d Development l'hiladelphia Electric Company P. O. Box 1323 ATTN: Mr._D. M. Smith, Vice President Harrisburg, Pennsylvania 17120 Peach Botk m Atomic Power Station Route 1, Box 208 Mr. Thcmas M, Gerusky, Director Delta, Per.nsylvania 17314 Bure w of Radiation Protection Pennsylvania Department of H. Ch;is Schwem Environmental Resources Vice President, Production P. O. Box 2063 Atlantic Electric Harrisburg, Pennsylvania 17120 P.O. Box 1500 1199 Black Horse Pike Mr. Albert R. Steel, Chairman Pleasantville, New Jersey 08232 Board of Supervisors Peach Bottom Township Resid?nt"Inspector R. D. #1 U.S. Nuclear Regulatory Comission Delta, Pennsylvania 17314 Peach Botten Atomic Power Statier P.O. Box 399 Pr. Gary Mock Delta, Pennsylvania 17314 P. O. Box 09181 Columbus, Ohio 43209 Regional Administrator, Region i V.S. Nuclear Regulatory Comission Delmarva Power and Light Company 475 Allendale Road c/o Jack Urban Kirg of Prussia, Pennsylvania 19406 General Haneger, Fuel Supply 800 King Street Mr. 3ryan W. Gorman P.O. Box 231 Manager - External Affairs Wilmington, DE 19899 Public Service S ectric & Gas Company P.O. Box 236, N?8 Mr. Tom Magette Hancocks Bridge, New Jersey 08038 Power Plant Research Program Department of Natural Resources B-3 Tewes State Office Building Annapolis, Maryland 21401 l | |||
Mr. Roland Fletcher ' | |||
Department of Environment I 201 West Preston Street l Baltimore, Maryland 21201 e | |||
- ~ | |||
{, l i. | |||
ENCLOSURE 1 ATTENDEES OCTOBER 19, 1988 NAME ORGANIZATION Robert Martin NRC, Project Manager Marilyn C. Kray PEco, Engineer-Licensing Robert D. Walker PECo Engineering W. J. Boyer PECo, Engineering | |||
. W. C. Birely PEco, Senior Licensing Engineer q C. Morris NRC, Reviewer 7 | |||
2 1 | |||
6 4 | |||
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, , ENCIOSURE 2 AGENDA | |||
: 1. Discuss the results of the revised voltage study which considers transients down to the 480 volt level. | |||
: 2. The predictions of the voltage transient study should be confirmed by measurements (data) acceptable to the staff. In Supplemental Information, Item 1, Model Validation, the licensee writes that measurements will be made. | |||
: 3. Whether the start timing for loads on the 4160 volt or 13,800 volt buses which can reduce transient voltages on the safety buses supplied by offsite power should bo incorporated into the Technical Specifications. | |||
These loads are: Emergency Service Water and Emergency Cooling Water Pumps; Cooling Tower Pumps and Fans; Emergency Diesel Generator Room Vent Supply Fans; and the Residual Heat Removal Compartment Coolers. | |||
4 Adequacy of the preferred power supply: Whether the preferred power supply voltages should be recorded, so that the frequency with which the voltage reaches, or goes below 95 pu, the design basis minimum voltage and..the duration of such excesses, is known. | |||
: 5. Discuss the preference to shift the timing of many systems versus selecting motors with the required torque at minimum voltage. | |||
: 6. One of the reasons for experiencing 480V bus voltages less than design basis minima, is said to be because, at the time the Peach Bottom Atomic Power Station was designed, it was not customary to go below 4160 volts in design analysis. The revised voltage study goes to 480 volts. | |||
Discuss assurance that there are no residual problems at 120 volts. | |||
: 7. All timing and minimum voltage specifications described in tha proposed amendments are point values without reference to tolerances; or to drift in undervoltage and timing relay calibrations. | |||
: 8. Comitments from licensee to subje:t all contactors, relays and other hardware specified by plant design to work at a voltage less than 10% | |||
of rated, to acceptance tests and to surveillance at intervals to be detennined, to ensure that components will continue to function outside manufacturers specified ranges. | |||
: 9. Discuss the current practice of dividing loads into Technical r | |||
SDecification loads and others not described in the Technical i Specification, but which must be synchronized with them. All loads which ! | |||
can influence the functional capability of safety systems should be accounted for. | |||
l | |||
. 1 | |||
-}} |
Latest revision as of 03:23, 30 December 2020
ML20205C960 | |
Person / Time | |
---|---|
Site: | Peach Bottom ![]() |
Issue date: | 10/20/1988 |
From: | Martin R Office of Nuclear Reactor Regulation |
To: | Office of Nuclear Reactor Regulation |
References | |
NUDOCS 8810270028 | |
Download: ML20205C960 (6) | |
Text
_ _ _ _ _ .
a c' [ %o, UNITED STATES j -
'#I j NUCLE AR REGULATORY COMMISSION w ASHINGToN, D. C. 20$$$
k ..... / Cetober 20, 1988 Docket No. 50-277/278 Facility: Peach Bottom Atomic power Station, Units 2 and 3 Littnsee: Philadelphia Electric Cr.aany
SUBJECT:
SUMMARY
OF MEETING ON PROTECT!9N FROM DEGRADE 0 VOLTAGE CONDITIONS On October 19, 1688 the NRC staff met with representatives of the Philadelphia Electric Company in Rockville, Maryland. The meeting was for the purpose of discussing the licensee's submittal of September 7, 1988 on this subject. A list of attendees is provided in Enclosure 1. The agenda is provided in Enclosure 2. The meeting resulted in the following disposition for each of the agenda items.
With respect to items 1 and 6. PEco agreed to provide a sumary of the voltage study with emphasis on a description of the input parameters to the study and a discussion of the adequacy of the voltage protet. tion at the 120 volt level.
With respect to item 2. PECo agreed to provide a submittal describing the verification of the computer model used in the study; data musured in the plant will be compared to rodel predictions. In response to items 3 and 9 PECo agreed to identify the documents which centrol the timing of the addition of these lor.ds onto the ESF buses, and to include the timing of these loads in the Updated Final Safety Analysis Report.
In response to it*m 4. PECo ccmitted to rivise its response to reflect the use by the load dispatcher of the information now available from voltage monitors at the north subitation to avoid unnecessarily degraded voltage conditions at the Peach Bottom plant. The response is to also include plans for action when the north substation grid voltage monitoring capability is not available.
In re:ponse to item 5, the option of selecting alternate Core Spray Pump motor designs was discussed with the conclusion being that this was not practical due '
to the inability of an alternate motor selection by itself to completely meet the needs of the system and also riue to the considerable margins that continue to be available with the present motor design used in accordance with the licensee's recent proposal. No further information was requested.
In response to item 7. PECo indicated that tolarances or the timing setpoints for load additions do reflect the manufacturer's recommended worst case tolerances plus measurement error plus additional margin for contingency i purposes. No further infonration was requested. i 1
In response to item 8. PECo comitted to describe in further detail its plans for taking inplant data and also for sampling from procurement stores to verify with sufficient confidence that these components will function as l described in the licensee's submittal. '
l S310270028 8910:0 (DR F
ADOCK 05000277 FDC
F. .o .
2 t
l l
In sumary, the staff requested that PECo submit an integrated response i describing these comitments and the plans for implementing them. !
VRober hE. d /Il .s / 4 Martin Project Manager Project Directorate 1 2
(
Division of Reactor Projects 1/l! i Office of Nuclear Reactor Regulation ;
i
Enclosures:
As stated cc: Licensee / Applicant & Service List !
t l
l t
I I
i t
I
[
i l
i i
l i
P I
l l
w_--n .,,,.,r,. -wr--,----~~ r ~'- s , w-~ - ~ ' -
. l in sumary. the staff requested that PECo submit an integrated response describing these comitments and the plans for implementing them.
/s/
Robert E. Martin, Project Manager P"qject Directorate I-2 Duision of Reactor Projects I/l!
Office of Nuclear Peactor Regulation
Enclosures:
As stated cc: Licensee / Applicant & Service List DISTRIBUTION Docket F11e ;~
HRC PDR Local POR PDI-2 Reading WButler RMartin/RClark OGC EJordan BGrimes NRC Participants ACRS (10)
HBClayton CPorris DTondi FRosa 1 L in c:llt i
i I
I L
{q')-
Of .?/fM' PDI-2/0 i~'
- f. rt'in:er FButler d
/g/Zo/88 c g/88 '
i'.
Mr. William M. Alden Peach Bottom Atomic Power Station, Philadelphia Electric Company Units 2 and 3 cc:
Trcy B. Conner, Jr. , Esq. A. Heics. Coordinator 1747 Pennsylvania Aver.ue, N.W. I- '
wania State Clearinghouse Washington, D.C. 20006 e aor's Office of State Planning
.d Development l'hiladelphia Electric Company P. O. Box 1323 ATTN: Mr._D. M. Smith, Vice President Harrisburg, Pennsylvania 17120 Peach Botk m Atomic Power Station Route 1, Box 208 Mr. Thcmas M, Gerusky, Director Delta, Per.nsylvania 17314 Bure w of Radiation Protection Pennsylvania Department of H. Ch;is Schwem Environmental Resources Vice President, Production P. O. Box 2063 Atlantic Electric Harrisburg, Pennsylvania 17120 P.O. Box 1500 1199 Black Horse Pike Mr. Albert R. Steel, Chairman Pleasantville, New Jersey 08232 Board of Supervisors Peach Bottom Township Resid?nt"Inspector R. D. #1 U.S. Nuclear Regulatory Comission Delta, Pennsylvania 17314 Peach Botten Atomic Power Statier P.O. Box 399 Pr. Gary Mock Delta, Pennsylvania 17314 P. O. Box 09181 Columbus, Ohio 43209 Regional Administrator, Region i V.S. Nuclear Regulatory Comission Delmarva Power and Light Company 475 Allendale Road c/o Jack Urban Kirg of Prussia, Pennsylvania 19406 General Haneger, Fuel Supply 800 King Street Mr. 3ryan W. Gorman P.O. Box 231 Manager - External Affairs Wilmington, DE 19899 Public Service S ectric & Gas Company P.O. Box 236, N?8 Mr. Tom Magette Hancocks Bridge, New Jersey 08038 Power Plant Research Program Department of Natural Resources B-3 Tewes State Office Building Annapolis, Maryland 21401 l
Mr. Roland Fletcher '
Department of Environment I 201 West Preston Street l Baltimore, Maryland 21201 e
- ~
{, l i.
ENCLOSURE 1 ATTENDEES OCTOBER 19, 1988 NAME ORGANIZATION Robert Martin NRC, Project Manager Marilyn C. Kray PEco, Engineer-Licensing Robert D. Walker PECo Engineering W. J. Boyer PECo, Engineering
. W. C. Birely PEco, Senior Licensing Engineer q C. Morris NRC, Reviewer 7
2 1
6 4
I e
w -, ,, -- -,, y , -n, , , - , . r-- ., - ,- - r ,-w-
F; .
- c. -
, , ENCIOSURE 2 AGENDA
- 1. Discuss the results of the revised voltage study which considers transients down to the 480 volt level.
- 2. The predictions of the voltage transient study should be confirmed by measurements (data) acceptable to the staff. In Supplemental Information, Item 1, Model Validation, the licensee writes that measurements will be made.
- 3. Whether the start timing for loads on the 4160 volt or 13,800 volt buses which can reduce transient voltages on the safety buses supplied by offsite power should bo incorporated into the Technical Specifications.
These loads are: Emergency Service Water and Emergency Cooling Water Pumps; Cooling Tower Pumps and Fans; Emergency Diesel Generator Room Vent Supply Fans; and the Residual Heat Removal Compartment Coolers.
4 Adequacy of the preferred power supply: Whether the preferred power supply voltages should be recorded, so that the frequency with which the voltage reaches, or goes below 95 pu, the design basis minimum voltage and..the duration of such excesses, is known.
- 5. Discuss the preference to shift the timing of many systems versus selecting motors with the required torque at minimum voltage.
- 6. One of the reasons for experiencing 480V bus voltages less than design basis minima, is said to be because, at the time the Peach Bottom Atomic Power Station was designed, it was not customary to go below 4160 volts in design analysis. The revised voltage study goes to 480 volts.
Discuss assurance that there are no residual problems at 120 volts.
- 7. All timing and minimum voltage specifications described in tha proposed amendments are point values without reference to tolerances; or to drift in undervoltage and timing relay calibrations.
- 8. Comitments from licensee to subje:t all contactors, relays and other hardware specified by plant design to work at a voltage less than 10%
of rated, to acceptance tests and to surveillance at intervals to be detennined, to ensure that components will continue to function outside manufacturers specified ranges.
- 9. Discuss the current practice of dividing loads into Technical r
SDecification loads and others not described in the Technical i Specification, but which must be synchronized with them. All loads which !
can influence the functional capability of safety systems should be accounted for.
l
. 1
-