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{{#Wiki_filter:ttl'igRP jfpVEZE ROCHESTER GAS AND ELECTRIC CORPORATION | {{#Wiki_filter:ttl'igRP jfpVEZE ROCHESTER GAS AND ELECTRIC CORPORATION ~ 89 EAST AVENUE, ROCHESTER N.Y..14649-0001 ROBERT C MECREDY T Et.E PHONE Vice President AREA CODE 71B 546 2700 | ||
~89 EAST AVENUE, ROCHESTER N.Y..14649-0001 | @irma Nuclear Production January 10, 1994 U.S. Nuclear Regulatory Commission Attn: Allen R. Johnson Project Directorate I-3 Document Control Desk Washington, DC 20555 | ||
ROBERT C MECREDY | |||
T Et.E PHONE AREA CODE 71B 546 2700 January 10, 1994 U.S.Nuclear Regulatory | ==Subject:== | ||
Commission | Reply to a Notice of Violation NRC Inspection Report No. 50-244/93-21, dated December 10, 1993 R.E. Ginna Nuclear Power Plant Docket No. 50-244 | ||
Attn: Allen R.Johnson Project Directorate | |||
I-3 Document Control Desk Washington, DC 20555 Subject: Reply to a Notice of Violation NRC Inspection | ==Dear Mr. Johnson:== | ||
Report No.50-244/93-21, dated December 10, 1993 R.E.Ginna Nuclear Power Plant Docket No.50-244 Dear Mr.Johnson: During an NRC inspection | |||
conducted on October 4, 1993 to October 13, 1993, a violation of NRC requirements | During an NRC inspection conducted on October 4, 1993 to October 13, 1993, a violation of NRC requirements was identified. | ||
was identified. | In accordance with the "General Statement of Policy and Procedure for NRC Enforcement Actions," 10 CFR Part 2, Appendix C, the violation is listed below: | ||
In accordance | "Plant technical specification 4.6.1.e.3.a requires that at least once per 18 months during shutdown, each emergency diesel generator shall be demonstrated to be operable by simulating a loss of offsite power in conjunction with a safety injection test signal and verifying de-energization of the emergency buses and load shedding from the emergency buses." | ||
with the"General Statement of Policy and Procedure for NRC Enforcement | Contrary to the above, on October 11, 1993, it was determined that testing to verify load shedding from the emergency buses was not performed during the 18 month surveillance testing. | ||
Actions," 10 CFR Part 2, Appendix C, the violation is listed below: "Plant technical specification | (1) the reason for the violation, or, if contested, the basis for disputing the violation: | ||
4.6.1.e.3.a | Rochester Gas & Electric Corporation (RG&E) accepts the violation. | ||
requires that at least once per 18 months during shutdown, each emergency diesel generator shall be demonstrated | We acknowledge that plant procedures did not adequately test the bus undervoltage logic, as required by Technical Specification (TS) 4 . 6. 1.e. 3 . (a) . | ||
to be operable by simulating | |||
a loss of offsite power in conjunction | Lettex: Page 2 | ||
with a safety injection test signal and verifying de-energization | |||
of the emergency buses and load shedding from the emergency buses." Contrary to the above, on October 11, 1993, it was determined | ==Subject:== | ||
that testing to verify load shedding from the emergency buses was not performed during the 18 month surveillance | Violation Response 93-21-01 Date: January 10, 1994 The reason for the violation, as stated in LER 93-005 (Docket Number 50-244, LER 93-005, dated November 10, 1993) was a mis-interpretation of TS surveillance requirements. The load shedding requirement of TS 4.6.1.e.3.{a) was interpreted as the shedding of non-essential loads powered from the emergency buses. The shedding of non-essential loads had been tested by simulating a safety injection (SI) signal during performance of procedures RSSP-2.1 (Safety Injection Functional Test) and RSSP-2.1A. (Safety Injection Functional Test Alignment / Realignment), which are performed each refueling outage. The need to verify load shedding capabilities of safeguards loads, with undervoltage and SI present, had not been considexed. | ||
testing.(1)the reason for the violation, or, if contested, the basis for disputing the violation: | (2) the corrective steps that have been taken and the results achieved: | ||
Rochester Gas&Electric Corporation (RG&E)accepts the violation. | The immediate corrective action was to perform the surveillance tests necessary to verify load shedding capability from the emergency buses. A procedure change notice (PCN) was developed for each associated PT-9.1 procedure (monthly surveillance test procedures for testing undervoltage protection for 480 volt safeguards busses 14, 16, 17, and 18). Testing was started on October 11, 1993, and was completed on October 12, 1993, within twenty-four hours of discovery. Details of this testing and test methodology are discussed in Attachment l. (To perfoim this testing, individual components were declared inoperable, one at a time, fox brief periods. No more than one component was inoperable at a given time, and the diesel generators (DGs) were maintained operable during the entire testing pexiod.) | ||
We acknowledge | The guidance of NRC Generic Letter {GL) 87-09, entitled "Sections 3.0 and 4.0 of the Standard Technical Specifications (STS) on the Applicability of Limiting Conditions for Operation and Surveillance Requirements", was followed. Both the "A" and "B" DGs were available to perform all intended functions throughout the discovery and surveillance testing period. | ||
that plant procedures | This testing demonstrated end-to-end operability of the under-voltage protection system. It verified undervoltage signals to safeguards components, and undervoltage in conjunction with SI signal to the Component Cooling'ater (CCW) pumps. Initial testing of the "B" CCW pump undervoltage / SI trip logic was indeterminate. At that time, the "B" CCW pump was declared inoperable, until further testing was conducted. The pump was subsequently verified to be fully operable, and was returned to service approximately twelve hours later. | ||
did not adequately | The testing conducted on October 11-12, in combination with the surveillance tests conducted during the 1993 outage, met the requixements of TS 4.6.1.e.3.(a), and verified that the safeguards functions would have performed as required. | ||
test the bus undervoltage | |||
logic, as required by Technical Specification (TS)4.6.1.e.3.(a). | Letter: Page 3 | ||
Lettex: Page 2 Subject: Violation Response 93-21-01 Date: January 10, 1994 The reason for the violation, as stated in LER 93-005 (Docket Number 50-244, LER 93-005, dated November 10, 1993)was a mis-interpretation | |||
of TS surveillance | ==Subject:== | ||
requirements. | Violation Response 93-21-01 Date: January 10, 1994 RG&E personnel subsequently reviewed the requirements of TS 4.6.1, and compared these requirements with surveillance proce-dures. No other noncompliances were identified. | ||
The load shedding requirement | (3) the corrective steps that will be taken to avoid further violations: | ||
of TS 4.6.1.e.3.{a) | 0 A review of Section 4 of the Ginna TS will be performed to ensure that there are implementing procedures for every surveillance required by TS. This review will be completed prior to completion of the next scheduled refueling outage. | ||
was interpreted | Results of a preliminary review of Section 4 have determined that there are sufficient procedural controls for implementing Section 4 requirements. | ||
as the shedding of non-essential | 0 A review of the identified implementing procedures will be performed to ensure that these procedures do, in fact, implement the TS requirements. This review will be completed prior to completion of the next scheduled refueling outage. | ||
loads powered from the emergency buses.The shedding of non-essential | 0 Procedures that verify load shedding capability will be upgraded to include safeguards loads, for conditions of undervoltage and SI, prior to completion of the next scheduled refueling outage. | ||
loads had been tested by simulating | (4) the date when full compliance will be achieved: | ||
a safety injection (SI)signal during performance | Full compliance with TS 4.6.1.e.3.(a) was achieved on October 12, 1993, at the completion of surveillance testing. | ||
of procedures | Very truly yours, Robert C. Mecredy xc: Mr. Allen R. Johnson (Mail Stop 14D1) | ||
RSSP-2.1 (Safety Injection Functional | PWR Project Directorate I-3 Washington, DC 20555 U.S. Nuclear Regulatory Commission Region I 475 Allendale Road King of Prussia, PA 19406 Ginna USNRC Senior Resident Inspector | ||
Test)and RSSP-2.1A.(Safety Injection Functional | |||
Test Alignment/Realignment), which are performed each refueling outage.The need to verify load shedding capabilities | Attachment 1 PT-9.1 Series Test Details The purpose of this test was to verify undervoltage safeguards load shedding capability. | ||
of safeguards | Monthly TS surveillance testing currently ensures each safeguards breaker can be stripped from the bus using the trip coil. To verify the undervoltage stripping capability, all that was necessary was to verify the integrity of the undervoltage logic contacts and associated circuitry, to the trip coils. Jumpers were used to simulate SI for the CCW pumps because their breakers trip on undervoltage coincident with SI signal. | ||
loads, with undervoltage | Testing Sequence: | ||
and SI present, had not been considexed. | 1 ~ Manipulate test switches and develop an undervoltage condition using test equipment. | ||
(2)the corrective | 2 ~ Verify auxiliary output relays energize to cause the trip function, initiated by appropriate operation of the intermediate digital control logic circuitry. | ||
steps that have been taken and the results achieved: The immediate corrective | 3 ~ Return test switches to normal and remove test equipment. | ||
action was to perform the surveillance | 4 ~ Verify component being tested is not, in service. | ||
tests necessary to verify load shedding capability | : 5. Measure the continuity of wiring between the undervoltage auxiliary relays and the breaker switchgear, using DC voltage measurements to ground. ) | ||
from the emergency buses.A procedure change notice (PCN)was developed for each associated | t | ||
PT-9.1 procedure (monthly surveillance | : 6. Verify normally open output relay contacts using resistance measurements. | ||
test procedures | 7 ~ Locally trip the associated auxiliary relay and verify proper indicator lamp response and relay contacts indicate closed by resistance measurement. | ||
for testing undervoltage | : 8. Reset the auxiliary relay and verify relay contacts indicate open by resistance measurement. | ||
protection | : 9. Repeat steps 1 8 for all four channels (27/X, 27/BX, 27D/X, and 27D/BX). | ||
for 480 volt safeguards | One test anomoly was identified, as noted in the violation response. Relay 86-16B, associated with the "B" CCW pump breaker, failed to meet the specified resistance acceptance criteria. | ||
busses 14, 16, 17, and 18).Testing was started on October 11, 1993, and was completed on October 12, 1993, within twenty-four | Emergency Maintenance procedure EM-778 was performed to verify the contact did in fact trip the breaker. After being verified, the contact was reworked by simple burnishing of exposed contact surfaces. ~ ~ ~ v | ||
hours of discovery. | |||
Details of this testing and test methodology | ~ 'i 0 | ||
are discussed in Attachment | |||
l.(To perfoim this testing, individual | ACCELERATED DISTRIBUTION DEMONSTRATION SYSTEM REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS) | ||
components | CCESSION NBR:9402010169 DOC.DATE'4/01/10 NOTARIZED: NO DOCKET FACIL:50-244 Robert Emmet Ginna Nuclear Plant, Unit 1, Rochester G 05000244 AUTH. NAME AUTHOR AFFILIATION MECREDY,R.C. Rochester Gas & Electric Corp. | ||
were declared inoperable, one at a time, fox brief periods.No more than one component was inoperable | RECIP.NAME RECIPIENT AFFILIATION JOHNSON,A.R. ProjectI Directorate I-3 | ||
at a given time, and the diesel generators (DGs)were maintained | |||
operable during the entire testing pexiod.)The guidance of NRC Generic Letter{GL)87-09, entitled"Sections 3.0 and 4.0 of the Standard Technical Specifications (STS)on the Applicability | ==SUBJECT:== | ||
of Limiting Conditions | Responds to violations noted in insp rept 50-244/93-21. | ||
for Operation and Surveillance | Corrective actions:surveillance tests necessary to verify load shedding capability from emergency buses performed & D procedure revised. | ||
Requirements", was followed.Both the"A" and"B" DGs were available to perform all intended functions throughout | DISTRIBUTION CODE: IE01D TITLE: General (50 COPIES RECEIVED:LTR 2 ENCL Dkt)-Insp Rept/Notice of Vi&o ation Response SIZE: $ | ||
the discovery and surveillance | / | ||
testing period.This testing demonstrated | NOTES:License Exp date in'ccordance with 10CFR2,2.109(9/19/72). 05000244 RECIPIENT COPIES RECIPIENT COPIES D ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL PD1-3 PD 1 1 JOHNSON,A 1 1 D INTERNAL: AEOD/DEIB 1 1 AEOD/DSP/ROAB 1 1 AEOD/DS P/TPAB 1 1 AEOD/TTC 1 1 DEDRO 1 1 NRR/DORS/OEAB 1 1' NRR/DRCH/HHFB 1 1 NRR/DRIL/RPEB- 1 NRR/DRSS/PEPB 1 1 NRR/PMAS/ILPB1 1 1 NRR/PMAS/ILPB2 | ||
end-to-end | ~BI~ | ||
operability | REG FILM 02 1 | ||
of the under-voltage protection | 1 1 | ||
system.It verified undervoltage | 1 1 | ||
signals to safeguards | 1 NUDOCS-ABSTRACT OGC/HDS1 RES/HFB 1 | ||
components, and undervoltage | 1 1 | ||
in conjunction | 1 1 | ||
with SI signal to the Component Cooling'ater (CCW)pumps.Initial testing of the"B" CCW pump undervoltage | 1 RGNT FILE Ol 1 1 EXTERNAL EG&G/BRYCE i J H ~ 1 1 NRC PDR 1 1 NSIC 1 1 R | ||
/SI trip logic was indeterminate. | D S | ||
At that time, the"B" CCW pump was declared inoperable, until further testing was conducted. | D D | ||
The pump was subsequently | NOTE TO ALL "RIDS" RECIPIENTS: | ||
verified to be fully operable, and was returned to service approximately | PLEASE HELP US TO REDUCE WASTE! CONTACT THE DOCUMENT CONTROL DESK, ROOM P 1-37 (EXT. 20079) TO ELIMINATEYOUR NAME FROM DISTRIBUTION LISTS FOR DOCUMENTS YOU DON'T NEEDI OTAL NUMBER OF COPIES REQUIRED: LTTR 22 ENCL 22 | ||
twelve hours later.The testing conducted on October 11-12, in combination | |||
with the surveillance | ,/ | ||
tests conducted during the 1993 outage, met the requixements | 't"'l'i"~lliPjt'I ~ ~ ~ VA ~ ~ G net | ||
of TS 4.6.1.e.3.(a), and verified that the safeguards | /'l'gjll,"i,",iiel't | ||
functions would have performed as required. | ' I t,/f//IP'(/ | ||
Letter: Page 3 Subject: Violation Response 93-21-01 Date: January 10, 1994 RG&E personnel subsequently | ROCHESTER GAS AND ELECTRIC CORPORATION ~ | ||
reviewed the requirements | F II 89 EAST AVENUE, ROCHESTER N.Y. 14649.OO0'I I | ||
of TS 4.6.1, and compared these requirements | ToAtt | ||
with surveillance | $ Tate ROBERT C. MECREDY TELEPHONE Vice Ptesident AREA CODE 716 546'2700 Ctnna Nuetear Ptoduetion January 10, 1994 U.S. Nuclear Regulatory Commission Attn: Allen R. Johnson Project Directorate I-3 Document Control Desk Washington, DC 20555 | ||
proce-dures.No other noncompliances | |||
were identified. | ==Subject:== | ||
(3)the corrective | Reply to a Notice of Violation NRC Inspection Report No. 50-244/93-21, dated December 10, 1993 R.E. Ginna Nuclear Power Plant Docket No. 50-244 | ||
steps that will be taken to avoid further violations: | |||
0 A review of Section 4 of the Ginna TS will be performed to ensure that there are implementing | ==Dear Mr. Johnson:== | ||
procedures | |||
for every surveillance | During an NRC inspection conducted on October 4, 1993 to October 13, 1993, a violation of NRC requirements was identified. | ||
required by TS.This review will be completed prior to completion | In acccrdance with the "General Statement of Policy and Procedure for NRC Enforcement Actions," 10 CFR Part 2, Appendix C, the violation is listed below: | ||
of the next scheduled refueling outage.Results of a preliminary | "Plant technical specification 4.6.l.e.3.a requires that at least once per 18 months during shutdown, each emergency diesel generator shall be demonstrated to be operable by simulating a loss of offsite power in conjunction with a safety injection test signal and verifying de-energization of the emergency buses and load shedding from the emergency buses." | ||
review of Section 4 have determined | Contrary to the above, on October 11, 1993, it was determined that testing to verify load shedding from the emergency buses was not performed during the 18 month surveillance testing. | ||
that there are sufficient | (1) the reason for the violation, or, disputing the violation: | ||
procedural | if contested, the basis for Rochester Gas & Electric Corporation (RG&E) accepts the violation. | ||
controls for implementing | We acknowledge that plant procedures did not adequately test the bus undervoltage logic, as required by Technical Specification (TS) 4. 6. 1.e.3. (a) . | ||
Section 4 requirements. | gw ~I To iQ '. | ||
0 | 9402010169 940110 PDR ADOCK 05000244 9 PDR | ||
implementing | |||
procedures | 0' Letter: Page 2 | ||
will be performed to ensure that these procedures | |||
do, in fact, implement the TS requirements. | ==Subject:== | ||
This review will be completed prior to completion | "Violation Response 93-21-01 Date: January 10, 1994 The reason for the violation, as stated in LER 93-005 (Docket Number 50-244, LER 93-005, dated November 10, 1993) was a mis-interpretation'of TS surveill'ance requirements. The load shedding requirement of TS 4.6.1.e.3.(a) was interpreted as the shedding of non-essential loads powered from ,the emergency buses. The shedding of non-essential loads had been tested by .simulating a safety injection (SI) signal .during performance of procedures RSSP-2.1 (Safety Injection Functional Test) and RSSP-2.1A (Safety Injection Functional Test Alignment / Realignment), which are performed each refueling outage. The need to verify load shedding capabilities of safeguards loads, with undervoltage and SI present, had not been considered., | ||
of the next scheduled refueling outage.Procedures | l (2) the corrective steps that have been taken and the results achieved: | ||
that verify load shedding capability | The immediate corrective action was to perform the surveillance tests necessary to verify load shedding capability from the emergency buses. A procedure change notice (PCN) was developed for each associated PT-9.1 procedure (monthly surveillance test procedures for testing 'undervoltage protection for 480 volt safeguards busses 14, 16, 17, and 18). Testing was started on October 11, 1993, and was completed on October 12, 1993, within twenty-four hours of discovery. Details of this testing and test methodology are discussed in Attachment 1.. (To perform this testing, indiyidua2. components were declared inoperable, one at a time, for brief periods. No more than one component was inoperable at a given time, and the diesel generators (DGs) were maintained operable during the entire testing period.) | ||
will be upgraded to include safeguards | The guidance of.NRC Generic Letter (GL) 87-09, entitled "Sections 3.0 and 4.0 of the Standard Technical Specifications (STS) on the Applicability of Limiting Conditions for Operation and Surveillance Requirements", was followed. ,Both the "A" and "B" DGs were available to perform all intended functions throughout the discovery. and surveillance testing period. | ||
loads, for conditions | This testing demonstrated end-to-end operability of the under-voltage protection system. It verified undervoltage signals to safeguards components, and undervoltage in conjunction with SI signal to the Component Cooling Water (CCW) pumps. Initial testing of the "B" CCW pump undervoltage "B" | ||
of undervoltage | / SI trip logic was indeterminate. At that time, the CCW pump was declared inoperable, until further testing was conducted. The pump was subsequently verified,to be fully operable, and was returned to service approximately twelve hours later. | ||
and SI, prior to completion | The testing conducted on October 11-12, in combination with the surveillance tests conducted during the 1993 outage, met the requirements of TS 4.6.1.e.3.(a), and verified that the safeguards functions would have performed as required. | ||
of the next scheduled refueling outage.(4)the date when full compliance | |||
will be achieved: Full compliance | Letter: Page 3 Subja't: Violation Response 93-21-01 Date: January 10, 1994 RG&E personnel subsequently reviewed the requirements of TS 4.6.1, and compared these requirements with surveillance proce-dures. No other noncompliances were identified. | ||
with TS 4.6.1.e.3.(a) | (3') the corrective steps that will be taken to avoid further violations: | ||
was achieved on October 12, 1993, at the completion | 0 A review of Section 4 of the Ginna TS will be performed to ensure that there are implementing procedures for every surveillance required by TS. This review will be completed prior to completion of the next scheduled refueling outage. | ||
of surveillance | Results of a preliminary review of Section 4 have determined that there are sufficient procedural controls for implementing Section 4 requirements. | ||
testing.Very truly yours, Robert C.Mecredy xc: Mr.Allen R.Johnson (Mail Stop 14D1)PWR Project Directorate | 0 A review of the identified implementing procedures will be performed to ensure that these procedures do, in fact, implement the TS requirements. This review will be completed prior to completion of the next scheduled refueling outage. | ||
I-3 Washington, DC 20555 U.S.Nuclear Regulatory | 0 Procedures that verify load shedding capability will be upgraded to include safeguards loads, for conditions of undervoltage and SI, prior to completion of the next scheduled refueling outage. | ||
Commission | (4) the date when full compliance will be achieved: | ||
Region I 475 Allendale Road King of Prussia, PA 19406 Ginna USNRC Senior Resident Inspector | Full compliance with TS 4.6.1.e.3.(a) was achieved on . | ||
Attachment | October 12, 1993, at the completion of surveillance testing. | ||
1 PT-9.1 Series Test Details The purpose of this test was to verify undervoltage | Very truly yours, Robert C. Mecredy xc: Mr. Allen R. Johnson (Mail Stop 14D1) | ||
safeguards | PWR Project Directorate I-3 Washington, DC 20555 U.S. Nuclear Regulatory Commission Region I 475 Allendale Road King of Prussia, PA 19406 Ginna USNRC Senior Resident Inspector | ||
load shedding capability. | |||
Monthly TS surveillance | Attachment 1 PT-9.1 Series Test Details The purpose of this test was to verify undervoltage safeguards load shedding capability. | ||
testing currently ensures each safeguards | Monthly TS surveillance test'ing currently ensures each safeguards breaker can be stripped from the bus using the trip coil. To verify the undervoltage stripping capability, all that was necessary was to verify the integrity of the undervoltage logic contacts and associated circuitry, to the trip coils. Zumpers were used to simulate SI for the CCW pumps because their breakers trip on undervoltage coincident with SI signal. | ||
breaker can be stripped from the bus using the trip coil.To verify the undervoltage | Testing Sequence: | ||
stripping capability, all that was necessary was to verify the integrity of the undervoltage | 1 ~ Manipulate test switches and develop an undervoltage condition using test equipment. | ||
logic contacts and associated | 2 ~ Verify auxiliary output relays energize to cause the trip function, initiated by appropriate operation of the intermediate digital control logic circuitry. | ||
circuitry, to the trip coils.Jumpers were used to simulate SI for the CCW pumps because their breakers trip on undervoltage | 3 ~ Return test switches to normal and remove test equipment. | ||
coincident | 4 ~ Verify component being tested is not in service. | ||
with SI signal.Testing Sequence: 1~Manipulate | : 5. Measure the continuity of wiring between the undervoltage auxiliary relays and the breaker switchgear, using DC voltage measurements to ground. | ||
test switches and develop an undervoltage | : 6. Verify normally open output relay contacts using resistance measurements. | ||
condition using test equipment. | 7 ~ Locally trip the associated auxiliary relay and verify proper indicator lamp response and relay contacts indicate closed by resistance measurement. | ||
2~Verify auxiliary output relays energize to cause the trip function, initiated by appropriate | : 8. Reset the auxiliary relay and verify relay contacts indicate open by resistance measurement. | ||
operation of the intermediate | : 9. Repeat steps 1 8 for all four channels (27/X, 27/BX, 27D/X, and 27D/BX). | ||
digital control logic circuitry. | One test anomoly was identified, as noted in the violation response. Relay 86-16B, associated with the "B" CCW pump breaker, failed to meet the specified resistance acceptance criteria. | ||
3~ | Emergency Maintenance'rocedure EM-778 was performed to verify the contact did in fact trip .the breaker. After being verified, the contact was reworked by simple burnishing of exposed contact surfaces. | ||
Verify component being tested is not, in service.Measure the continuity | |||
of wiring between the undervoltage | ~l}} | ||
auxiliary relays and the breaker switchgear, using DC voltage measurements | |||
to ground.)t Verify normally open output relay contacts using resistance | |||
measurements. | |||
7~ | |||
auxiliary relay and verify proper indicator lamp response and relay contacts indicate closed by resistance | |||
measurement. | |||
Reset the auxiliary relay and verify relay contacts indicate open by resistance | |||
measurement. | |||
9.Repeat steps 1 | |||
with the"B" CCW pump breaker, failed to meet the specified resistance | |||
acceptance | |||
criteria.Emergency Maintenance | |||
procedure EM-778 was performed to verify the contact did in fact trip the breaker.After being verified, the contact was reworked by simple burnishing | |||
of exposed contact surfaces.~~~v | |||
~'i 0 | |||
ACCELERATED | |||
DISTRIBUTION | |||
DEMONSTRATION | |||
SYSTEM REGULATORY | |||
INFORMATION | |||
DISTRIBUTION | |||
SYSTEM (RIDS)CCESSION NBR:9402010169 | |||
DOC.DATE'4/01/10 | |||
NOTARIZED: | |||
NO FACIL:50-244 | |||
Robert Emmet Ginna Nuclear Plant, Unit 1, Rochester G AUTH.NAME AUTHOR AFFILIATION | |||
MECREDY,R.C. | |||
Rochester Gas&Electric Corp.RECIP.NAME | |||
RECIPIENT AFFILIATION | |||
JOHNSON,A.R. | |||
I-3 | |||
noted in insp rept 50-244/93-21. | |||
Corrective | |||
actions:surveillance | |||
tests necessary to verify load shedding capability | |||
from emergency buses performed&procedure revised.DISTRIBUTION | |||
CODE: IE01D COPIES RECEIVED:LTR | |||
2 ENCL | |||
of Vi&o ation Response NOTES:License | |||
Exp date in'ccordance | |||
with 10CFR2,2.109(9/19/72). | |||
NRR/DRSS/PEPB | |||
NRR/PMAS/ILPB2 | |||
~BI~REG FILM 02 | |||
ROCHESTER GAS AND ELECTRIC CORPORATION | |||
TELEPHONE AREA CODE 716 546'2700 January 10, 1994 U.S.Nuclear Regulatory | |||
Commission | |||
Attn: Allen R.Johnson Project Directorate | |||
I-3 Document Control Desk Washington, DC 20555 Subject: Reply to a Notice of Violation NRC Inspection | |||
Report No.50-244/93-21, dated December 10, 1993 R.E.Ginna Nuclear Power Plant Docket No.50-244 Dear Mr.Johnson: During an NRC inspection | |||
conducted on October 4, 1993 to October 13, 1993, a violation of NRC requirements | |||
was identified. | |||
In acccrdance | |||
with the"General Statement of Policy and Procedure for NRC Enforcement | |||
Actions," 10 CFR Part 2, Appendix C, the violation is listed below: "Plant technical specification | |||
4.6.l.e.3.a | |||
requires that at least once per 18 months during shutdown, each emergency diesel generator shall be demonstrated | |||
to be operable by simulating | |||
a loss of offsite power in conjunction | |||
with a safety injection test signal and verifying de-energization | |||
of the emergency buses and load shedding from the emergency buses." Contrary to the above, on October 11, 1993, it was determined | |||
that testing to verify load shedding from the emergency buses was not performed during the 18 month surveillance | |||
testing.(1)the reason for the violation, or, if contested, the basis for | |||
We acknowledge | |||
that plant procedures | |||
did not adequately | |||
test the bus undervoltage | |||
logic, as required by Technical Specification (TS)4.6.1.e.3.(a).gw~I To iQ'.9402010169 | |||
940110 PDR ADOCK 05000244 9 PDR | |||
0' | |||
Letter: Page 2 Subject: "Violation | |||
Response 93-21-01 Date: January 10, 1994 The reason for the violation, as stated in LER 93-005 (Docket Number 50-244, LER 93-005, dated November 10, 1993)was a mis-interpretation'of | |||
TS surveill'ance | |||
requirements. | |||
The load shedding requirement | |||
of TS 4.6.1.e.3.(a) | |||
was interpreted | |||
as the shedding of non-essential | |||
loads powered from ,the emergency buses.The shedding of non-essential | |||
loads had been tested by.simulating | |||
a safety injection (SI)signal.during performance | |||
of procedures | |||
RSSP-2.1 (Safety Injection Functional | |||
Test)and RSSP-2.1A (Safety Injection Functional | |||
Test Alignment/Realignment), which are performed each refueling outage.The need to verify load shedding capabilities | |||
of safeguards | |||
loads, with undervoltage | |||
and SI present, had not been considered., l (2)the corrective | |||
steps that have been taken and the results achieved: The immediate corrective | |||
action was to perform the surveillance | |||
tests necessary to verify load shedding capability | |||
from the emergency buses.A procedure change notice (PCN)was developed for each associated | |||
PT-9.1 procedure (monthly surveillance | |||
test procedures | |||
for testing'undervoltage | |||
protection | |||
for 480 volt safeguards | |||
busses 14, 16, 17, and 18).Testing was started on October 11, 1993, and was completed on October 12, 1993, within twenty-four | |||
hours of discovery. | |||
Details of this testing and test methodology | |||
are discussed in Attachment | |||
1..(To perform this testing, indiyidua2. | |||
components | |||
were declared inoperable, one at a time, for brief periods.No more than one component was inoperable | |||
at a given time, and the diesel generators (DGs)were maintained | |||
operable during the entire testing period.)The guidance of.NRC Generic Letter (GL)87-09, entitled"Sections 3.0 and 4.0 of the Standard Technical Specifications (STS)on the Applicability | |||
of Limiting Conditions | |||
for Operation and Surveillance | |||
Requirements", was followed.,Both the"A" and"B" DGs were available to perform all intended functions throughout | |||
the discovery. | |||
and surveillance | |||
testing period.This testing demonstrated | |||
end-to-end | |||
operability | |||
of the under-voltage protection | |||
system.It verified undervoltage | |||
signals to safeguards | |||
components, and undervoltage | |||
in conjunction | |||
with SI signal to the Component Cooling Water (CCW)pumps.Initial testing of the"B" CCW pump undervoltage | |||
/SI trip logic was indeterminate. | |||
At that time, the | |||
The pump was subsequently | |||
verified,to | |||
be fully operable, and was returned to service approximately | |||
twelve hours later.The testing conducted on October 11-12, in combination | |||
with the surveillance | |||
tests conducted during the 1993 outage, met the requirements | |||
of TS 4.6.1.e.3.(a), and verified that the safeguards | |||
functions would have performed as required. | |||
Letter: Page 3 Subja't: Violation Response 93-21-01 Date: January 10, 1994 RG&E personnel subsequently | |||
reviewed the requirements | |||
of TS 4.6.1, and compared these requirements | |||
with surveillance | |||
proce-dures.No other noncompliances | |||
were identified. | |||
(3')the corrective | |||
steps that will be taken to avoid further violations: | |||
0 | |||
procedures | |||
for every surveillance | |||
required by TS.This review will be completed prior to completion | |||
of the next scheduled refueling outage.Results of a preliminary | |||
review of Section 4 have determined | |||
that there are sufficient | |||
procedural | |||
controls for implementing | |||
Section 4 requirements. | |||
A review of the identified | |||
implementing | |||
procedures | |||
will be performed to ensure that these procedures | |||
do, in fact, implement the TS requirements. | |||
This review will be completed prior to completion | |||
of the next scheduled refueling outage.Procedures | |||
that verify load shedding capability | |||
will be upgraded to include safeguards | |||
loads, for conditions | |||
of undervoltage | |||
and SI, prior to completion | |||
of the next scheduled refueling outage.(4)the date when full compliance | |||
will be achieved: Full compliance | |||
with TS 4.6.1.e.3.(a) | |||
was achieved on.October 12, 1993, at the completion | |||
of surveillance | |||
testing.Very truly yours, Robert C.Mecredy xc: Mr.Allen R.Johnson (Mail Stop 14D1)PWR Project Directorate | |||
I-3 Washington, DC 20555 U.S.Nuclear Regulatory | |||
Commission | |||
Region I 475 Allendale Road King of Prussia, PA 19406 Ginna USNRC Senior Resident Inspector | |||
Attachment | |||
1 PT-9.1 Series Test Details The purpose of this test was to verify undervoltage | |||
safeguards | |||
load shedding capability. | |||
Monthly TS surveillance | |||
test'ing currently ensures each safeguards | |||
breaker can be stripped from the bus using the trip coil.To verify the undervoltage | |||
stripping capability, all that was necessary was to verify the integrity of the undervoltage | |||
logic contacts and associated | |||
circuitry, to the trip coils.Zumpers were used to simulate SI for the CCW pumps because their breakers trip on undervoltage | |||
coincident | |||
with SI signal.Testing Sequence: 1~Manipulate | |||
test switches and develop an undervoltage | |||
condition using test equipment. | |||
2~Verify auxiliary output relays energize to cause the trip function, initiated by appropriate | |||
operation of the intermediate | |||
digital control logic circuitry. | |||
3~ | |||
Verify component being tested is not in service.Measure the continuity | |||
of wiring between the undervoltage | |||
auxiliary relays and the breaker switchgear, using DC voltage measurements | |||
to ground.6.Verify normally open output relay contacts using resistance | |||
measurements. | |||
7~ | |||
auxiliary relay and verify proper indicator lamp response and relay contacts indicate closed by resistance | |||
measurement. | |||
Reset the auxiliary relay and verify relay contacts indicate open by resistance | |||
measurement. | |||
9.Repeat steps 1 | |||
with the"B" CCW pump breaker, failed to meet the specified resistance | |||
acceptance | |||
~l | |||
}} |
Latest revision as of 18:22, 29 October 2019
ML17263A526 | |
Person / Time | |
---|---|
Site: | Ginna ![]() |
Issue date: | 01/10/1994 |
From: | Mecredy R ROCHESTER GAS & ELECTRIC CORP. |
To: | Andrea Johnson NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM), Office of Nuclear Reactor Regulation |
References | |
NUDOCS 9402010169 | |
Download: ML17263A526 (12) | |
Text
ttl'igRP jfpVEZE ROCHESTER GAS AND ELECTRIC CORPORATION ~ 89 EAST AVENUE, ROCHESTER N.Y..14649-0001 ROBERT C MECREDY T Et.E PHONE Vice President AREA CODE 71B 546 2700
@irma Nuclear Production January 10, 1994 U.S. Nuclear Regulatory Commission Attn: Allen R. Johnson Project Directorate I-3 Document Control Desk Washington, DC 20555
Subject:
Reply to a Notice of Violation NRC Inspection Report No. 50-244/93-21, dated December 10, 1993 R.E. Ginna Nuclear Power Plant Docket No. 50-244
Dear Mr. Johnson:
During an NRC inspection conducted on October 4, 1993 to October 13, 1993, a violation of NRC requirements was identified.
In accordance with the "General Statement of Policy and Procedure for NRC Enforcement Actions," 10 CFR Part 2, Appendix C, the violation is listed below:
"Plant technical specification 4.6.1.e.3.a requires that at least once per 18 months during shutdown, each emergency diesel generator shall be demonstrated to be operable by simulating a loss of offsite power in conjunction with a safety injection test signal and verifying de-energization of the emergency buses and load shedding from the emergency buses."
Contrary to the above, on October 11, 1993, it was determined that testing to verify load shedding from the emergency buses was not performed during the 18 month surveillance testing.
(1) the reason for the violation, or, if contested, the basis for disputing the violation:
Rochester Gas & Electric Corporation (RG&E) accepts the violation.
We acknowledge that plant procedures did not adequately test the bus undervoltage logic, as required by Technical Specification (TS) 4 . 6. 1.e. 3 . (a) .
Lettex: Page 2
Subject:
Violation Response 93-21-01 Date: January 10, 1994 The reason for the violation, as stated in LER 93-005 (Docket Number 50-244, LER 93-005, dated November 10, 1993) was a mis-interpretation of TS surveillance requirements. The load shedding requirement of TS 4.6.1.e.3.{a) was interpreted as the shedding of non-essential loads powered from the emergency buses. The shedding of non-essential loads had been tested by simulating a safety injection (SI) signal during performance of procedures RSSP-2.1 (Safety Injection Functional Test) and RSSP-2.1A. (Safety Injection Functional Test Alignment / Realignment), which are performed each refueling outage. The need to verify load shedding capabilities of safeguards loads, with undervoltage and SI present, had not been considexed.
(2) the corrective steps that have been taken and the results achieved:
The immediate corrective action was to perform the surveillance tests necessary to verify load shedding capability from the emergency buses. A procedure change notice (PCN) was developed for each associated PT-9.1 procedure (monthly surveillance test procedures for testing undervoltage protection for 480 volt safeguards busses 14, 16, 17, and 18). Testing was started on October 11, 1993, and was completed on October 12, 1993, within twenty-four hours of discovery. Details of this testing and test methodology are discussed in Attachment l. (To perfoim this testing, individual components were declared inoperable, one at a time, fox brief periods. No more than one component was inoperable at a given time, and the diesel generators (DGs) were maintained operable during the entire testing pexiod.)
The guidance of NRC Generic Letter {GL) 87-09, entitled "Sections 3.0 and 4.0 of the Standard Technical Specifications (STS) on the Applicability of Limiting Conditions for Operation and Surveillance Requirements", was followed. Both the "A" and "B" DGs were available to perform all intended functions throughout the discovery and surveillance testing period.
This testing demonstrated end-to-end operability of the under-voltage protection system. It verified undervoltage signals to safeguards components, and undervoltage in conjunction with SI signal to the Component Cooling'ater (CCW) pumps. Initial testing of the "B" CCW pump undervoltage / SI trip logic was indeterminate. At that time, the "B" CCW pump was declared inoperable, until further testing was conducted. The pump was subsequently verified to be fully operable, and was returned to service approximately twelve hours later.
The testing conducted on October 11-12, in combination with the surveillance tests conducted during the 1993 outage, met the requixements of TS 4.6.1.e.3.(a), and verified that the safeguards functions would have performed as required.
Letter: Page 3
Subject:
Violation Response 93-21-01 Date: January 10, 1994 RG&E personnel subsequently reviewed the requirements of TS 4.6.1, and compared these requirements with surveillance proce-dures. No other noncompliances were identified.
(3) the corrective steps that will be taken to avoid further violations:
0 A review of Section 4 of the Ginna TS will be performed to ensure that there are implementing procedures for every surveillance required by TS. This review will be completed prior to completion of the next scheduled refueling outage.
Results of a preliminary review of Section 4 have determined that there are sufficient procedural controls for implementing Section 4 requirements.
0 A review of the identified implementing procedures will be performed to ensure that these procedures do, in fact, implement the TS requirements. This review will be completed prior to completion of the next scheduled refueling outage.
0 Procedures that verify load shedding capability will be upgraded to include safeguards loads, for conditions of undervoltage and SI, prior to completion of the next scheduled refueling outage.
(4) the date when full compliance will be achieved:
Full compliance with TS 4.6.1.e.3.(a) was achieved on October 12, 1993, at the completion of surveillance testing.
Very truly yours, Robert C. Mecredy xc: Mr. Allen R. Johnson (Mail Stop 14D1)
PWR Project Directorate I-3 Washington, DC 20555 U.S. Nuclear Regulatory Commission Region I 475 Allendale Road King of Prussia, PA 19406 Ginna USNRC Senior Resident Inspector
Attachment 1 PT-9.1 Series Test Details The purpose of this test was to verify undervoltage safeguards load shedding capability.
Monthly TS surveillance testing currently ensures each safeguards breaker can be stripped from the bus using the trip coil. To verify the undervoltage stripping capability, all that was necessary was to verify the integrity of the undervoltage logic contacts and associated circuitry, to the trip coils. Jumpers were used to simulate SI for the CCW pumps because their breakers trip on undervoltage coincident with SI signal.
Testing Sequence:
1 ~ Manipulate test switches and develop an undervoltage condition using test equipment.
2 ~ Verify auxiliary output relays energize to cause the trip function, initiated by appropriate operation of the intermediate digital control logic circuitry.
3 ~ Return test switches to normal and remove test equipment.
4 ~ Verify component being tested is not, in service.
- 5. Measure the continuity of wiring between the undervoltage auxiliary relays and the breaker switchgear, using DC voltage measurements to ground. )
t
- 6. Verify normally open output relay contacts using resistance measurements.
7 ~ Locally trip the associated auxiliary relay and verify proper indicator lamp response and relay contacts indicate closed by resistance measurement.
- 8. Reset the auxiliary relay and verify relay contacts indicate open by resistance measurement.
- 9. Repeat steps 1 8 for all four channels (27/X, 27/BX, 27D/X, and 27D/BX).
One test anomoly was identified, as noted in the violation response. Relay 86-16B, associated with the "B" CCW pump breaker, failed to meet the specified resistance acceptance criteria.
Emergency Maintenance procedure EM-778 was performed to verify the contact did in fact trip the breaker. After being verified, the contact was reworked by simple burnishing of exposed contact surfaces. ~ ~ ~ v
~ 'i 0
ACCELERATED DISTRIBUTION DEMONSTRATION SYSTEM REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)
CCESSION NBR:9402010169 DOC.DATE'4/01/10 NOTARIZED: NO DOCKET FACIL:50-244 Robert Emmet Ginna Nuclear Plant, Unit 1, Rochester G 05000244 AUTH. NAME AUTHOR AFFILIATION MECREDY,R.C. Rochester Gas & Electric Corp.
RECIP.NAME RECIPIENT AFFILIATION JOHNSON,A.R. ProjectI Directorate I-3
SUBJECT:
Responds to violations noted in insp rept 50-244/93-21.
Corrective actions:surveillance tests necessary to verify load shedding capability from emergency buses performed & D procedure revised.
DISTRIBUTION CODE: IE01D TITLE: General (50 COPIES RECEIVED:LTR 2 ENCL Dkt)-Insp Rept/Notice of Vi&o ation Response SIZE: $
/
NOTES:License Exp date in'ccordance with 10CFR2,2.109(9/19/72). 05000244 RECIPIENT COPIES RECIPIENT COPIES D ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL PD1-3 PD 1 1 JOHNSON,A 1 1 D INTERNAL: AEOD/DEIB 1 1 AEOD/DSP/ROAB 1 1 AEOD/DS P/TPAB 1 1 AEOD/TTC 1 1 DEDRO 1 1 NRR/DORS/OEAB 1 1' NRR/DRCH/HHFB 1 1 NRR/DRIL/RPEB- 1 NRR/DRSS/PEPB 1 1 NRR/PMAS/ILPB1 1 1 NRR/PMAS/ILPB2
~BI~
REG FILM 02 1
1 1
1 1
1 NUDOCS-ABSTRACT OGC/HDS1 RES/HFB 1
1 1
1 1
1 RGNT FILE Ol 1 1 EXTERNAL EG&G/BRYCE i J H ~ 1 1 NRC PDR 1 1 NSIC 1 1 R
D S
D D
NOTE TO ALL "RIDS" RECIPIENTS:
PLEASE HELP US TO REDUCE WASTE! CONTACT THE DOCUMENT CONTROL DESK, ROOM P 1-37 (EXT. 20079) TO ELIMINATEYOUR NAME FROM DISTRIBUTION LISTS FOR DOCUMENTS YOU DON'T NEEDI OTAL NUMBER OF COPIES REQUIRED: LTTR 22 ENCL 22
,/
't"'l'i"~lliPjt'I ~ ~ ~ VA ~ ~ G net
/'l'gjll,"i,",iiel't
' I t,/f//IP'(/
ROCHESTER GAS AND ELECTRIC CORPORATION ~
F II 89 EAST AVENUE, ROCHESTER N.Y. 14649.OO0'I I
ToAtt
$ Tate ROBERT C. MECREDY TELEPHONE Vice Ptesident AREA CODE 716 546'2700 Ctnna Nuetear Ptoduetion January 10, 1994 U.S. Nuclear Regulatory Commission Attn: Allen R. Johnson Project Directorate I-3 Document Control Desk Washington, DC 20555
Subject:
Reply to a Notice of Violation NRC Inspection Report No. 50-244/93-21, dated December 10, 1993 R.E. Ginna Nuclear Power Plant Docket No. 50-244
Dear Mr. Johnson:
During an NRC inspection conducted on October 4, 1993 to October 13, 1993, a violation of NRC requirements was identified.
In acccrdance with the "General Statement of Policy and Procedure for NRC Enforcement Actions," 10 CFR Part 2, Appendix C, the violation is listed below:
"Plant technical specification 4.6.l.e.3.a requires that at least once per 18 months during shutdown, each emergency diesel generator shall be demonstrated to be operable by simulating a loss of offsite power in conjunction with a safety injection test signal and verifying de-energization of the emergency buses and load shedding from the emergency buses."
Contrary to the above, on October 11, 1993, it was determined that testing to verify load shedding from the emergency buses was not performed during the 18 month surveillance testing.
(1) the reason for the violation, or, disputing the violation:
if contested, the basis for Rochester Gas & Electric Corporation (RG&E) accepts the violation.
We acknowledge that plant procedures did not adequately test the bus undervoltage logic, as required by Technical Specification (TS) 4. 6. 1.e.3. (a) .
gw ~I To iQ '.
9402010169 940110 PDR ADOCK 05000244 9 PDR
0' Letter: Page 2
Subject:
"Violation Response 93-21-01 Date: January 10, 1994 The reason for the violation, as stated in LER 93-005 (Docket Number 50-244, LER 93-005, dated November 10, 1993) was a mis-interpretation'of TS surveill'ance requirements. The load shedding requirement of TS 4.6.1.e.3.(a) was interpreted as the shedding of non-essential loads powered from ,the emergency buses. The shedding of non-essential loads had been tested by .simulating a safety injection (SI) signal .during performance of procedures RSSP-2.1 (Safety Injection Functional Test) and RSSP-2.1A (Safety Injection Functional Test Alignment / Realignment), which are performed each refueling outage. The need to verify load shedding capabilities of safeguards loads, with undervoltage and SI present, had not been considered.,
l (2) the corrective steps that have been taken and the results achieved:
The immediate corrective action was to perform the surveillance tests necessary to verify load shedding capability from the emergency buses. A procedure change notice (PCN) was developed for each associated PT-9.1 procedure (monthly surveillance test procedures for testing 'undervoltage protection for 480 volt safeguards busses 14, 16, 17, and 18). Testing was started on October 11, 1993, and was completed on October 12, 1993, within twenty-four hours of discovery. Details of this testing and test methodology are discussed in Attachment 1.. (To perform this testing, indiyidua2. components were declared inoperable, one at a time, for brief periods. No more than one component was inoperable at a given time, and the diesel generators (DGs) were maintained operable during the entire testing period.)
The guidance of.NRC Generic Letter (GL) 87-09, entitled "Sections 3.0 and 4.0 of the Standard Technical Specifications (STS) on the Applicability of Limiting Conditions for Operation and Surveillance Requirements", was followed. ,Both the "A" and "B" DGs were available to perform all intended functions throughout the discovery. and surveillance testing period.
This testing demonstrated end-to-end operability of the under-voltage protection system. It verified undervoltage signals to safeguards components, and undervoltage in conjunction with SI signal to the Component Cooling Water (CCW) pumps. Initial testing of the "B" CCW pump undervoltage "B"
/ SI trip logic was indeterminate. At that time, the CCW pump was declared inoperable, until further testing was conducted. The pump was subsequently verified,to be fully operable, and was returned to service approximately twelve hours later.
The testing conducted on October 11-12, in combination with the surveillance tests conducted during the 1993 outage, met the requirements of TS 4.6.1.e.3.(a), and verified that the safeguards functions would have performed as required.
Letter: Page 3 Subja't: Violation Response 93-21-01 Date: January 10, 1994 RG&E personnel subsequently reviewed the requirements of TS 4.6.1, and compared these requirements with surveillance proce-dures. No other noncompliances were identified.
(3') the corrective steps that will be taken to avoid further violations:
0 A review of Section 4 of the Ginna TS will be performed to ensure that there are implementing procedures for every surveillance required by TS. This review will be completed prior to completion of the next scheduled refueling outage.
Results of a preliminary review of Section 4 have determined that there are sufficient procedural controls for implementing Section 4 requirements.
0 A review of the identified implementing procedures will be performed to ensure that these procedures do, in fact, implement the TS requirements. This review will be completed prior to completion of the next scheduled refueling outage.
0 Procedures that verify load shedding capability will be upgraded to include safeguards loads, for conditions of undervoltage and SI, prior to completion of the next scheduled refueling outage.
(4) the date when full compliance will be achieved:
Full compliance with TS 4.6.1.e.3.(a) was achieved on .
October 12, 1993, at the completion of surveillance testing.
Very truly yours, Robert C. Mecredy xc: Mr. Allen R. Johnson (Mail Stop 14D1)
PWR Project Directorate I-3 Washington, DC 20555 U.S. Nuclear Regulatory Commission Region I 475 Allendale Road King of Prussia, PA 19406 Ginna USNRC Senior Resident Inspector
Attachment 1 PT-9.1 Series Test Details The purpose of this test was to verify undervoltage safeguards load shedding capability.
Monthly TS surveillance test'ing currently ensures each safeguards breaker can be stripped from the bus using the trip coil. To verify the undervoltage stripping capability, all that was necessary was to verify the integrity of the undervoltage logic contacts and associated circuitry, to the trip coils. Zumpers were used to simulate SI for the CCW pumps because their breakers trip on undervoltage coincident with SI signal.
Testing Sequence:
1 ~ Manipulate test switches and develop an undervoltage condition using test equipment.
2 ~ Verify auxiliary output relays energize to cause the trip function, initiated by appropriate operation of the intermediate digital control logic circuitry.
3 ~ Return test switches to normal and remove test equipment.
4 ~ Verify component being tested is not in service.
- 5. Measure the continuity of wiring between the undervoltage auxiliary relays and the breaker switchgear, using DC voltage measurements to ground.
- 6. Verify normally open output relay contacts using resistance measurements.
7 ~ Locally trip the associated auxiliary relay and verify proper indicator lamp response and relay contacts indicate closed by resistance measurement.
- 8. Reset the auxiliary relay and verify relay contacts indicate open by resistance measurement.
- 9. Repeat steps 1 8 for all four channels (27/X, 27/BX, 27D/X, and 27D/BX).
One test anomoly was identified, as noted in the violation response. Relay 86-16B, associated with the "B" CCW pump breaker, failed to meet the specified resistance acceptance criteria.
Emergency Maintenance'rocedure EM-778 was performed to verify the contact did in fact trip .the breaker. After being verified, the contact was reworked by simple burnishing of exposed contact surfaces.
~l