ML18038A305
| ML18038A305 | |
| Person / Time | |
|---|---|
| Site: | Nine Mile Point  |
| Issue date: | 06/26/1990 |
| From: | Terry C NIAGARA MOHAWK POWER CORP. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| TASK-***, TASK-OR GL-90-04, GL-90-4, NMP1L-0511, NMP1L-511, NUDOCS 9007020100 | |
| Download: ML18038A305 (68) | |
Text
NIAGARAMOHAWKPOWER CORPORATION/301 PLAINFIELDROAD. SYRACUSE, N.Y. 13212/TELEPHONE (3(5) 474-1511 June 26, 1990 NMPlL 0511 U.S. Nuclear Regulatory Commi ssion Attn:
Document Control Desk Hashington, D.C.
20555 Re:
Nine Mile Point Unit 1
Docket No. 50-220 DPR-63 Re:
Nine Mile Point Unit 2 Docket No. 50-410 NPF-69 Gentlemen:
On April 25,
- 1990, the Nuclear Regulatory Commission issued a request for information concerning status of implementation of Generic Safety Issue (GSI) requirements (Generic Letter 90-04).
Enclosures 1 and 2 of this letter tabulate the requested status of implementation of GSIs as applicable to Nine Mile Point Unit 1
and Nine Mile Point Unit 2, respectively.
Very truly yours, NIAGARA NONAGON RIINER CORPORATION Ccp'.
D. Terry Vice President Nuclear Engineering and Licensing JMT/meed 8609G Enclosures xc:
Regional Administrator, Region I Mr. R. A. Capra, Director Mr.
R.
E. Martin, Pro]ect Manager Mr. H. A. Cook, Senior Resident Inspector Records Management
T
GS I'/HPA NUMBER 40 (B065)
TITLE Safety Concerns Associated with Pipe Breaks in the BWR Scram System Enclosure 1
Nine Mile Point Unit 1
APP1.1CAB I LITY Al 1 BNRs STATUS REMARKS NMPl's Scram Discharge Piping Inspection Program is described in our letter dated 12/15/86 and supplement dated 4/2/90.
41 (8058) 43 (B107)
Reliability of Air Systems All Plants BNR Scram Discharge Volume Systems All 81IRs NHPl submitted proposed Technical Specification Amendment on 12/27/88 Awaiting approval.
NMP1's response to GL 88-14 "Air Systems" is provided in our letter dated 4/1/89 Evaluations and Corrective Actions to be implemented by end of next refueling outage.
51 (L913) 67.3.3 (A017)
Improving the Reliability of Open-Cycle Service Hater Systems Improved Accident Monitoring All Plants All Plants NMPl's response to GL 89-13 "Service Hater Systems" is provided in our letter dated 2/16/90 Evaluations scheduled to be completed by end of next refueling outage.
NMP1's letter dated 7/31/89 described our compliance with RG 1.97 Additional long term actions will be described in letter currently scheduled for submittal 90 days after startup.
C - Complete NC No Changes Necessary NA Not Applicable I
Incomplete E - Evaluating
GSI /HPA NUMBER 75*(B076) 75 (8085)
TITLE Item 1.1 Post-Trip Review (Program Description and Procedure)
Item 1.2 Post-Trip Review Data and Information Capability Enclosure 1
Nine Mile Point Unit 1
APPLICABILITY All Plants Al 1 Plants STATUS REMARKS Refer to our 'letter dated 12/31/85.
NHPl's response to Item 1.2 is provided in our letters dated 11/8/83, 12/31/85 and telecon dated 11/26/85.
75 (B077) 75 (8086)
Item 2.1 Equipment Classification All Plants and Vendor Interface (Reactor Trip System Components)
Item 2.2.1 - Equipment Classification All Plants for Safety-Related Components Equipment Cl assi fication Program completed 12/31/85-Refer to our letter dated ll/2/88.
NMPl letters dated ll/8/83, 12/31/85 and 10/17/88 provide our response to Item 2.2.1.
75 (L003) 75 (8078)
Item 2.2.2 - Vendor.Interface for Safety-Related Components Items 3.1.1
& 3.1.2 Post Maintenance Testing (Reactor Trip System Components)
All Plants All Plants NMPl evaluating the requirements of GL 90-03.
Item 3.1.1-Refer to ouq letter dated ll/17/&6.
Item 3.1.2-Refer to our letter dated 12/31/85.
GSI item numbers correspond to Generic Letter 83-28 action item numbers.
C Complete NC - No Changes Necessary NA Not Applicable I - Incomplete
- Evaluating 8609G
GSI/HPA NUMBER 75 (8079)
TITLE Item 3.1.3 Post-Maintenance Testing-Changes to Test Requirements (Reactor Trip System Components)
Enclosure 1
Nine Mile Point Unit 1
APPLICABILITY All Plants STATUS 4
~
~
REMARKS Refer to our letter dated 12/31/85.
75 (B087) 75 (8088) 75 (8080) 75 (B081) 75 (B082)
Items 3.2.1
& 3.2.2 Post-Maintenance Testing (All Other Safety-Related Components)
Item 3.2.3 Post-Maintenance Testing-Changes to Test Requirements (All Other Safety-Related Components)
Item 4.1 Reactor Trip System Reliability (Vendor Related Modifications)
Items 4.2.1
& 4.2.2 Reactor Trip System Reliabi lity-Haintenance and Testing (Preventative Maintenance and Surveillance Program for Reactor Trip Breakers)
Item 4.3 Reactor Trip System Reliability Design Modifications (Automatic Actuation of Shunt Trip Attachment for Westinghouse and B&W Plants)
Al 1 Plants All Plants All Plants All PWRs All W & B&W.
NA NA NA Item 3.2.1-Refer to our letter dated 11/17/86.
Item 3.2.2-Refer to our letter dated 12/31/85.
Refer to our letter dated 12/31/85.
GSI-75 is concerned with Reactor Trip Breaker Modifications '- Applicable to PWR's only.
NMP1 is a
BWR NHPl is a
C - Complete NC No Changes Necessary NA - Not Applicable 1 - Incomplete E - Evaluating
Enclosure 1
Nine Mile Point Unit 1
GSI/MPA NUMBER 75 (B090) 75 (B091) 75 (B092) 75 (8093)
TITLE Item 4.3 Reactor Trip System Reliability Tech Spec Changes (Automatic Actuation of Shunt Trip Attachment for Westinghouse and B&W Plants)
Item 4.4 Reactor Trip System Reliability (Improvements in Maintenance and Test Procedures for B&W Plants)
Item 4.5.1 Reactor Trip System Reliability Diverse Trip Features (System Functional Testing)
Items 4.5.2
& 4.5:3 Reactor Trip System Reliability Test Alternatives and Intervals (System Functional Testing)
APPLICABILITY All H & BH Plants Al 1 B&H Plants All Plants All Plants STATUS NA REMARKS NMPl is a
NMPl is a
BHR (GE)
NMPl letters dated 7/31/84 and 12/31/84 provide our response to Item 4.5.1.
Item 4.5.2-Refer to our letters dated ll/8/83, 7/31/84, 12/31/84 and 4/13/89.
Item 4.5.3-Refer to our letters dated ll/8/83, 2/2/84, 4/30/84, 7/31/84, 7/2/85 and 12/31/85.
C Complete NC No Changes Necessary NA - Not Applicable 1
Incomplete
- Evaluating 8609G
V
~
GSI/MPA NUMBER 86 (BO&4)
TITLE Long Range Plan for Dealing with Stress Corrosion Cracking in BWR Piping Enclosure 1
Nine Mile Point Unit 1
APPLICABILITY All BWRs STATUS REMARKS ISI Program revisions to incorporate GL 88-01 requirements are scheduled for completion by next refuel-Tech Spec Amendment No.
107 incorporated the Tech Spec changes requested in GL 88-01.
93 (8098) 99 (L&17) 124 A-13 (8017)
Steam Binding of Auxiliary Feedwater Pumps RCS/RHR Suction Line Valve Interlock on PWRs Auxiliary Feedwater Syst'm Rel iabi 1 i ty Snubber Operabi 1 ity Assurance Hydraulic Snubbers All PWRs All PWRs AN0-152, Rancho Seco, Prairie Island
- 152, Crystal River-3 Ft. Calhoun All Plants NA NA NA NMPl is a
BWR GSI 124 is not applicable to NHPl.
NHPl Tech Spec Amendment No.
74 revised the NHPl snubber program to meet the intent of GL 84-13.
A-13 (8022)
Snubber Operability Assurance
All Plants Mechanical Snubbers NHPl Tech Spec Amendment No.
74 revised the NHPl snubber program to meet the intent of GL &4-13.
C - Complete NC - No Changes Necessary NA Not Applicable I Incomplete F - Evaluating 8609G
GSI/MPA NUMBER A-16 (D012)
TITLE Steam Effects on BHR Core Spray Distribution Enclosure 1
Nine Mile Point Unit 1
APPLICAB I I.ITY Oyster Creek 8
NMP-1 STATUS REMARKS GSI-A-16 is closed as described in GL 90-04, Enclosure 2.
A-35 (B023) 0-10 8-36 8-63 (8045)
Adequacy of Offsi te Power Systems Behavior of BHR.Hark III Containments Develop Design, Testing and Maintenance Criteria for Atmosphere Cleanup System Air Filtration and Adsorption Units for Engineered Safety Features Systems and for Normal Ventilation Systems Isolation of Low Pressure Systems Connected to the Reactor Coolant System Pressure Boundary All Plants All BNR Hark III Plants Al 1 Plants wi th OL NA Applications After 4/.1/80 Al 1 Plants NHPl letter dated 7/14/77 addressed technical concerns-NMPl Tech Spec Amendment No.
67 incorporated required Tech Spec changes.
NHP1 is a Hark I Plant.
NHPl's OL Application was before 4/1/80.
NHPl letter dated 3/19/80 addressed GSI B-63.
NRC letter dated 4/20/Bl contained Order for Modification of License-See Tech Spec 3.2.7.1.
C Complete NC No Changes Necessary NA - Not Applicable I - Incomplete E Evaluating 8609G
GSI/MPA NUMBER 40 (8065)
TITLE Safety Concerns Associated with Pipe Breaks in the BHR Scram System Enclosure 2
Nine Mile Point Unit 2 APPLICABILITY All OHRs STATUS REMARKS NMP2 complies with NUREG-0803 recommendations pn piping integrity as discussed in USAR Section 4.6.
41 (805&)
BHR Scram Discharge Volume Systems All BHRs Refer to USAR Section 4.6
'Functional Design of Reactivity Control Systems and Tech Spec Tables 4.3.6-1, 4.3.1.1-1.
43 (8107) 51 (L913) 67.3.3 (A017)
Reliability of Air Systems Improving the Reliability of Open-Cycle Service Hater Systems Improved Accident Monitoring All Plants All Plants All Plants C
NMP2's response to GL 88-1.4 "Air Systems" is provided in our letter dated 4/1/89.
Corrective actions and evaluations to be implemented by next outage.
NMP2's response to GL 89-13 "Service Hater Systems" is provided in our letter dated 2/16/90.
Evaluations scheduled to be completed end of the second refuel outage.
Refer to USAR Table 1.8-1 "Reg.
Guide 1.97".
C Complete, NC No Changes Necessary NA Not Applicable I
Incomplete
[ - Evaluating 8609G
M
GSI/MPA N(JMBER 7c)'(8076) 75 (B085)
TITLE Item 1.1 - Post-Trip Review (Program Oescription and Procedure)
Item 1.2 Post-Trip Review-Oata and Information Capability Enclosure 2
Nine Mile Point Unit 2 APPLICABILITY Al 1 Plants All Plants STATUS REMARKS NMP2's response to GL 83-28 "Salem ATWS Events" is provided in our letters dated 4/10/84, 12/20/85 and 4/15/86.
NHP2's response to GL 83-28 "Salem ATWS Events" is provided in our letters dated 4/10/84, 12/20/85 and 4/15/86.
75 (B077) 75 (B086) 75 (L003)
Item 2.1 Equipment Classification All Plants and Vendor Interface (Reactor Item 2.2.2 Vendor Interface for Safety-Related Components Al 1 Plants Trip System Components)
Item 2.2.1 - Equipment Classification All Plants for Safety-Related Components NHP2's response to GL 83-28 "Salem ATWS Events" is provided in our letters dated 4/10/84, 12/20/85 and 4/15/86.
NHP2's response to GL 83-28 "Salem ATWS Events" is provided in our letters dated 4/10/84, 12/20/85 and 4/15/86.
NMP2's response to GL 83-2 "Salem ATWS Events" is provided in our letters dated 4/10/84, 12/20/85 and 4/15/86.
GSI 75 item numbers correspond to Generic Letter 83-28 action item numbers.
C Complete NC No Changes Necessary NA - Not Applicable 1
Incomplete E - Evaluating 8609G
Enclosure 2
Nine Mile Point Unit 2 GSI/MPA NUMBF.R 75 (0078)
TITLE Items 3.1.1 5 3.1.2 Post Maintenance Testing (Reactor Trip System Components)
APPLICABILITY All Plants STATUS REMARKS NMP2's response to GL 83-26 "Salem ATWS Events" is provided in our letters dated 4/10/84, 12/20/85 ant 4/15/86.
75 (8079)
Item 3.1.3 - Post-Maintenance Testing-Changes to Test Requirements (Reactor Trip System Components)
All Plants NMP2's response to GL 83--.
"Salem ATWS Events" is provided in our letters dated 4/10/84, 12/20/85 ar:'.
4/15/86.
75 (8087) 75 (B088)
Items 3.2.1 E 3.2.2 Post-Maintenance Testing (All Other Safety-Related Components)
Item 3.2.3 Post-Maintenance Testing-Changes to Test Requirements (All Other Safety-Related Components)
Al 1 Plants All Plants NMP2's response'to GL 83-28 "Salem ATWS Events" is provided in our letters dated 4/10/84, 12/20/85 and 4/15/86.
NMP2's response to GL 83-28 "Salem ATWS Events" is provided in our letters dated 4/10/84, 12/20/85 and 4/15/86.
C Complete NC - No Changes Necessary NA Not Applicable I - Incomplete E - Evaluating 8609G
r
GSI/MPA NUMBER 75 (B080) 75 (8081)
TITLE Item 4.1 Reactor Trip System Reliability (Vendor Related Modifications)
Items 4.2.1
& 4.2.2 - Reactor Trip System Reliabi lity-Maintenance and Testing (Preventative Maintenance and Surveillance Program for Reactor Trip Breakers)
Enclosure 2
Nine Mile Point Unit 2 APPLICABILITY All Plants All PHRs STATUS NA
.REMARKS Refer to our letter dated 4/10/84 NMP2 is a BHR
/5 (B082) 75 (8090) 75 (8091)
Item 4.3 - Reactor Trip System Reliability - Oesign Modifications (Automatic Actuation of Shunt Trip Attachment for Westinghouse and B&H Plants)
Item 4.3 - Reactor Trip System Reliability Tech Spec Changes (Automatic Actuation of Shunt Trip Attachment for Westinghouse and B&H Plants)
Item 4.4 Reactor Trip System Reliability (Improvements in Maintenance and Test Procedures for B&H Plants)
All W & 0&H All H & BW Plants All B&H Plants NA NA NMP2 is a BHR (GE)
NMP2 is a
NMP2 is a
C Complete NC - No Changes Necessary NA Not Applicable I Incomplete E - Evaluating 8609G
Enclosure 2
Nine Mile Point'nit 2
GSI/MPA NUMBER 75 (8092) 75 (8093) 86 (8084) 93 (8098) 99 (LB'l7) 124 TITLE Item 4.5.1 Reactor Trip System Reliability Diverse Trip Features (System Functional Testing)
Items 4.5.2 5 4.5.3 Reactor Trip System Reliability Test Alternatives and Intervals (System Functional Testing)
Long Range Plan for Dealing with Stress Corrosion Cracking in BWR Piping Steam Binding of Auxiliary Feedwater Pumps RCS/RHR Suction Line Valve Interlock on PHRs Auxiliary Feedwater System Re 1 i abi 1 i ty APPLICABILITY Al 1 Pl an ts All Plants Al 1 BHRs Al 1 PHRs All PHRs AN0-172, Rancho Seco, Prairie Island
- 152, Crystal River-3 Ft. Calhoun STATUS NA NA REMARKS NMP2's response to GL 83-28 "Salem ATWS Events" is provided in our letters dated 4/10/84, 12/20/85 and 4/15/86.
NMP2's response to GL 83-2~
"Salem ATHS Events" is provided in our.letters dated 4/10/84, 12/20/85 and 4/15/86.
NMP2 response to GL 88-01 in our letters dated 7/28/88, 11/1/89, 12/14/89-Tech Spec Amendment No.
8 incorporated the Tech Spec changes requested in GL 88-01.
NMP2 is a
BHR NMP2 is a
BHR
, GSI 124 is not applicable to NMP2.
C Complete NC No Changes Necessary NA Not Applicable I Incomplete E Evaluating 8609G
0
GSI/HPA NUMBER TITLE Enclosure 2
Nine Mile Point Unit 2 APPLICABILITY STATUS REMARKS A-13 (8017)
Snubber Operability Assurance
All Plants Hydraulic Snubbers The NMP2 Tech Specs reflect the guidance'given in GL 84-13.
A-13 (8022)
Snubber Operability Assurance-Hechanical Snubbers Al 1 Plants The NHP2 Tech Specs reflect the guidance given in GL 84-13.
A-16 (D012)
A-35 (8923) 8-10 8-36 Steam Effects on BHR Core Spray Distribution Adequacy of Offsite Power Systems Behavior of BNR Mark III Containments Develop Design, Testing and Maintenance Criteria for Atmosphere Cleanup System Air Filtration and Adsorption Units for Engineered Safety Features Systems and for Normal Ventilation Systems Oyster Creek 8( NMP-1 All Pl ants All BHR Mark III Plants Al 1 Plants wi th OL NC Applications After 4/1/80 GSI A-16 is not applicable NHP2.
Refer to USAR Table 1.9-1 "SRP Conformance to Acc.
Cri ter>a".
NMP2 is a Hark II Plant Refer to USAR Table 1.8-1 Reg.
Guides 1.52, 1.140 8-63 (8045)
Isolation of Low Pressure Systems Connected to the Reactor Coolant System Pressure Boundary All Plants NC High pressure/low pressure Interlocks exist as described in USAR Section 7.6.2.2.1.
Tech Spec Surveillance Requirements in 4.4.3.2.2, 4.4.3.2.3, 4.4.3.2.4.
C Complete NC No Changes Necessary NA Not Applicable -.-
I Incomplete E Evaluating 8609G
'o
FACILITY NAME: NINE MILE POINT Unit 1 DOCKET NO.:
50-220 LICENSEE:
Niagara Mohawk Power Corporation ENCLOSURE 2 GSI Status Sumar GSI/MPA No.
40 (8065)
Title Safety Concerns
. Associated With Pipe Breaks In The BWR Scram System Licensee Status Determination C (04/02/90)
Staff Status Determination C (12/01/86)
Remarks The licensee's
- response, dated 12/15/86, to GL 86-01 described a piping inspection program with one alternate to the inspections described in the BWROG-8420 program.
The alternate inspection was implemented in the 1986 outage.
The review of the alternate inspection, based on additional information provided in a 4/2/90 letter (TAC 71392), is considered a
post-implementation review.
Therefore, the licensee's implementation date is considered to be 12/Ol/86.
41 (B058)
.I Volume Systems C (08/02/90)
This issue was dealt with by Orders addressing the short term requirements (issued on January 9,
1981) and the long term requirements (issued on June 24, 1983).
Classically,
~
this MPA would have been 2.1-1
r pH
FACILITY NAME: NINE MILE POINT Unit 1 DOCKET NO.:
50-220 LICENSEE:
Niagara Mohawk Power Corporation GSI Status Summar GSI/MPA No.
41 (B058)
(cont'd)
Title BWR Scram Discharge Volume Systems Licensee Status Determination Staff Status Determination C (08/02/90)
Remar ks implemented whenever the licensee implemented all requirements of the latter Order.
- However, the licensee took exception in 1981 to several requirements and these exceptions were not reconciled until the 1987-1990 period.
(See licensee letter of January 21,
- 1988, accession no. 8802170407).
These deviations were the subject of inspections in 1987.
They were finally resolved and closed out by License Amendment No.
118 on July 3, 1990.
Due to the extensive documentation involved, the nature of the issue and the absence of information indicating that the requirements of the MPA, as reviewed and approved by the NRC staff, had been implemented at any earlier time, the effective date of the concluding License Amendment No.
118 (issued on July 18, 1990) is taken on the implementation date for this MPA.
See TACS 71823 and 66750.
2.1-2
FACILITY NAME: NINE MILE POINT Unit 1 DOCKET NO.:
50-220 LICENSEE:
Niagara Mohawk Power Corporation GSI Status Sumar GSI/MPA No.
Title Licensee Status Determination Staff Status Determination Remarks 43 (8107) 51 (L913)
Reliability Of Air Systems Improving the Reliability of Open-Cycle Service Mater Systems I (1992)
I (next refueling outage-1992)
The licensee responded to GL 88-14 on 04/01/89.
The implementation is scheduled for the next refueling outage (early 1992).
The licensee divided the response into 3 phases.
The licensee indicates that the completed Phase I has demonstrated compliance with current system commitments and expectations and that the subject systems have provided reliable and safe service.
The staff considers that the licensee's evaluation approach is thorough and that the Phase I actions respond to a high percentage of GL 88-14's require-ments.
Accordingly, the staff has not disagreed with the licensee's schedule for completing its actions in response to GL 88-14.
The licensee responded to GL 89-13 on 02/16/90.
The licensee plans to complete their evaluation and propose 2.1-3
FACILITY NAME: NINE MILE POINT Unit 1 DOCKET NO.:
50-220 LICENSEE:
Niagara Mohawk Power Corporation GSI Status Summar GS I/MPA No.
51 (L913)
(cont'd)
Title Improving the Reliability of Open-Cycle Service Water Systems Licensee Status Determination Staff Status Determination I (next refueling outage-1992)
Remarks corrective actions as necessary by the end of the next refueling outage.
The Project Manager is concerned that, if the licensee waits until the end of the next refueling outage to complete such evaluations, then it will not be able to complete the subsequent actions on the schedule requested by GL 89-13.
The staff is requesting the licensee to reconsider the GL and to revise its response to the GL.
67.3.3 (A017)
Improved Accident Monitoring I (to be determined) 2.1-4 (a)
The Post-Accident Neutron Flux Monitoring issue remains open in accordance with TAC 69209.
Staff has been
'equested to review NMPC's responses and to provide SE; (b) Further licensee responses to issues identified in inspection audit are to be provided 90 days after startup (by October 29, 1990).
FACILITY NAME: NINE MILE POINT Unit 1 DOCKET NO.:
50-220 LICENSEE:
Niagara Mohawk Power Corporation GSI Status Sumar GSI/MPA No.
75 (B076) 75 (B085) 75 (B077) 75 (B086) 75 (LO03)
Title Item 1.1 - Post-Trip Review (Program Description and Procedure)
Item 1.2 - Post-Trip Review - Data and Information Capability Item 2.1 - Equipment Classification and Vendor Interface (Reactor Trip System Components)
Item 2.2. 1 - Equipment Classification for Safety-Related Components Item 2.2.2 - Vendor Interface for Saf ety-Rel ated Components Licensee Status Determination Staff Status Determination C (12/31/85)
C (12/31/85)
C (12/31/85)
C (12/31/85)
C (10/17/88)
C (10/17/88)
C (12/31/85)
C (12/31/85)
Remarks See licensee's remarks for details on all GL 83-28.
items.
Dates are those of licensee letters.
Generic Letter (GL) 90-03 issued on March 20, 1990, provides a
relaxation of GL 83-28 Item 2.2 Part 2.
GL 90-03 requires licensees to respond within 180 days of receipt of the letter.
2.1-5
FACILITY NAME:
DOCKET NO.:
LICENSEE:
NINE MILE POINT Unit 1
50-220 Niagara Mohawk Power Corporation GSI Status Summar GSI/MPA No.
75 (8078)
Tstl e Items 3.1.1 5 3.1.2-Post - Maintenance Testing (Reactor Trip System Components)
Licensee Status Determination C (11/17/86)
Item 3.1.1 (12/31/85)
Item 3.1.2 Staff Status Determination C 11/17/86 Item 3.1.1 (12/31/85)
Item 3.1.2 Remarks 75 (B079)
Item 3.1.3 - Post-Maintenance Testing-Changes to Test Require-ments (Reactor Trip System Components)
C (12/31/85)
C (12/31/85) 75 (B087) 75 (B088) 75 (B080)
Items 3.2.1 8 3.2.2-Post-Maintenance Testing (All Other Safety-Related Components)
Item 3.2.3 - Post-Maintenance Testing-Changes to Test Requirements (All Other Safety-Related Components)
Item 4.1 - Reactor Trip System Reliability (Vendor-Related Modifications)
C (11/17/86 Item 3.2.1 (12/31/85)
Item 3.2.2 C 12/31/85 C (11/17/86)
Item 3.2.1 (12/31/85)
Item 3.2.2 C (12/31/85) 2.1-6 For all PWRs; NMP-1 is a
BWR.
~ eX
~
FACILITY NAME:
DOCKET NO.:
LICENSEE:
NINE MILE POINT Unit 1
50-220 Niagara Mohawk Power Corporation GSI Status Summar GSI/MPA No.
Title Licensee Staff Status Status Determination Determination Remarks 75 (8081)
Items 4.2.1
& 4.2.2-Reactor Trip System Reliability-Maintenance arid Testing (Preventative Maintenance and Surveillance Program for Reactor Trip Breakers)
NA For all PHRs; NMP-1 is a BWR.
75 (B082) 75 (B090) 75 (B091)
Item 4.3 - Reactor Trip NA System Reliability-Design Modifications (Automatic Actuation of Shunt Trip Attachment for Westinghouse and BEW Plants)
Item 4.3 - Reactor Trip NA System Reliability-Tech Spec Changes (Automatic Actuation of Shunt Trip Attachment For Westinghouse and B&W Plants)
Item 4.4 - Reactor Trip NA System Reliability (Improvements in Maintenance and Test Procedures for B&W Plants)
NA NA 2.1-7 For W
BWR.
BWR.
BWR.
FACILITY NAME: NINE MILE POINT Unit 1 DOCKET NO.:
50-220 LICENSEE:
Niagara Mohawk Power Corporation GSI Status Sugar GSI/MPA No.
75 (B092) 75 (8093) 86 (B084)
Title Item 4.5.1 - Reactor Trip System Reliability-Diverse Trip Features (System Functional Testing)
Items 4.5.2 5 4.5.3-Reactor Trip System Reliability-Test Alternatives and Intervals (System Functional Testing)
Long Range Plan for Dealing with Stress Corrosion Cracking in BWR Piping Licensee Status Determination C (12/31/84)
C (4/13/89)
Item 4.5.2 12/31/85 Item 4.5.3 Staff Status Determination C (12/31/84)
C (4/13/89)
Item 4.5.2 (12/31/85)
Item 4.5.3 C (6/29/84)
Remarks Generic Letter 84-11 requested that information be provided.
NMPC's letter of 6/29/84 provided information in response to GL 84-11.
The staff's evaluation of MPA 8084 (TAC 55604) by letter dated 10/29/85 noted that its review of that response was complete.
Therefore, 6/29/84 is considered to be the implementation date for 8084.
MPA B-097/GL 88-01 superseded MPA B-084/GL 84-11 (F. Miraglia 2.1-8
FACILITY NAME: NINE MILE POINT Unit 1 DOCKET NO.:
50-220 LICENSEE:
Niagara Mohawk Power Corporation GSI Status Sumar
.GSI/MPA No.
86 (B084)
(cont'd) 93 (B098) 99 (L817)
Title Long Range Plan for Dealing with Stress Corrosion Cracking in BWR Piping Steam Binding of Auxiliary Feedwater Pumps RCS/RHR Suction Line Valve Interlock on PWRs Licensee Status Determination NA Staff Status Determination C (6/29/84)
Rema's memo of 1/25/88 to all PMs).
The staff evaluationof the response to GL 88-01 was provided in a letter dated 5/15/90.
GL 88-01 activities are beyond the scope of MPA B-084/GL 84-11 activities.
For all PWRs; NMP-1 is a
BWR.
124 Auxiliary Feedwater NA System Reliability Selected PWRs; NMP-1 is a
BWR.
2.1-9
FACILITY NAME: NINE MILE POINT Unit 1
DOCKET NO.:
50-220 LICENSEE:
'iagara Mohawk Power Corporation.
GSI Status Suranar GSI/MPA No.
A-13 (8017)
Tit1e Snubber Operability Assurance-Hydraulic Snubbers Licensee Staff Status Status Determination Determination C (09/23/85)
C (09/23/85)
Remarks The licensee responded to this GS I/MPA, which is based on the ll/20/80 NRC letter to all, licensees, except
GL 84-13 provided a revision to the surveillance requirements that were attached to the ll/20/80 NRC letter.
The licensee's responses to the snubber issues addressed by the ll/20/80 letter, dated 4/18/80, 3/20/81 and 10/05/83, were superse'ded by its responses to GL 84-13.
These responses, dated 3/13/85 and 5/06/85, were the subject of License Amendment No.
74 which was issued and effective on 9/23/85.
Therefore, the implementation date is considered to be 9/23/85 for this GSI/MPA.
2.1-10
FACILITY NAME: NINE MILE POINT Unit 1 DOCKET NO.:
50-220 LICENSEE:
Niagara Mohawk Power Corporation GSI Status Summar GSI/MPA No.
A-13 (8022)
Title Snubber Operability Assurance-Mechanical Snubbers Licensee Status Determination C (09/23/85)
Staff Status Determination C (09/23/85)
Remarks The licensee responded to this GSI/MPA, which is based on the ll/20/80 NRC letter to all, licensees, except
GL 84-13 provided a revision to the surveillance requirements that were attached to the ll/20/80 NRC letter.
The licensee's responses to the snubber issues addressed by the 11/20/80 letter, dated 4/18/80, 3/20/81 and 10/05/83, were superseded by its responses to GL 84-13.
These responses, dated 3/13/85 and 5/06/85, were the subject of License Amendment No.
74 which was issued and effective on 9/23/85.
Therefore, the implementation date is considered to be 9/23/85 for this GSI/MPA.
2.1-11
FACILITY NAME: NINE MILE POINT Unit 1 DOCKET NO.:
50-220 LICENSEE:
Niagara Mohawk Power Corporation GSI Status Sugar GSI/MPA No.
A-16 (D012)
Title Steam Effects on BWR Core Spray Distribution Licensee Status Determination C (04/25/90)
Staff Status Determination C (07/24/85)
Remarks By letter dated 7/24/85, the staff forwarded to the licensee the safety evaluation on core spray effectiveness in steam environment.
The analysis made by the licensee was found acceptable.
This letter contained T.S.
pages showing changes to the Bases mutually agreed on by the licensee and the staff.
A-35 (B023)
Adequacy of Offsite C (ll/09/84)
Power Systems C (11/09/84)
License Amendment No.
67 issued on 11/9/84 addressed the LCO and Surveillance requirements for equipment that provides for automatic initiation of the diesel 2.1-12
FACILITY NAME:
DOCKET NO.:
LICENSEE:
NINE MILE POINT Unit 1 50-220 Niagara Mohawk Power Corporation GSI Status Summar GSI/MPA No.
Title Licensee Status Determination Staff Status Determination Remarks A-35 (B023)
(cont'd)
B-3.0 B-36 Adequacy of Offsite C (11/09/84)
Power Systems Behavior of BMR Mark III Containments Develop Design, Testing and Maintenance Criteria for Atmosphere Cleanup System Air Filtration and Adsorption Units for Engineered Safety Features Systems and for Normal Ventilation Systems C ( ll/09/84) generators, should the grid voltage degrade.
NMP-1 has a
MARK I containment.
For all plants with OL applications after 4/1/80; NMP-1 was licensed in 1969.
B-63 (B045)
Isolation of Low Pressure Systems Connected to the Reactor Coolant System Pressure Boundary C (04/20/81)
C (04/20/81)
NMPC letter dated 3/19/80 addressed GSI B-63.
NRC letter dated 4/20/81 con-tained Order for Modifica-tion of license.
Also see Tech Spec 3.2.7.1.
2.1-13
FACILITY NAME: NINE MILE POINT Unit 2 DOCKET NO.:
50-220 LICENSEE:
Niagara Mohawk Power Corporation ENCLOSURE 2 GSI Status Summar GSI/MPA No.
40 (B065)
Tit1e Safety Concerns Associated With Pipe Breaks In The BWR Scram System Licensee Status Determination Staff Status Determination Remarks See NMPC comments.
Also see closeout in SER 4.6.
41 (B058) 43 (B107) 51 (L913)
BWR Scram Discharge Volume Systems Reliability Of Air Systems Improving the Reliability of Open-Cycle Service Water Systems I (spring 1991)
I (03/30/92)
See NMPC comments.
Also see closeout in SER 4.6.
The licensee responded to GL 88-14 on 04/01/89..The implementation is scheduled for the September 1990 refueling outage.
Documentation to be completed by January 1991 based on previous commitment which may slip some due to slip in first refueling outage schedule.
The licensee submitted the first of two required responses to GSI 89-13 on 2/16/90.
The licensee plans to complete their evaluation and proposed corrective actions as necessary, 2.2-1
%j V
e
~
1 FACILITY NAME: NINE MILE POINT Unit 2 DOCKET NO.:
50-220 LICENSEE:
Niagara Mohawk Power Corporation GSI Status Sutmar m
GSI/MPA No.
51 (L913)
(cont'd)
Title Improving the Reliability of Open-Cycle Service Mater Systems Licensee Status Determination Staff Status Determination I (03/30/92)
Remarks by the end of the second refueling outage.
The same concerns exist with this schedule as exist for Unit 1 schedule.
67.3.3 (A017)
Improved Accident Monitoring (a)
A License Condition requires that an isolation device issue be resolved during the first refueling outage.
(b) See Section 7.5.2.2 of SSER 4 wherein it is stated that NMP-2 meets RG 1.97 except for neutron flux.
75 (B076)
Item 1.1 - Post-Trip C (04/15/86)
Review (Program Description and Procedure)
NC (04/15/86)
See licensee's remarks for details on all GL 83-28 items.
Dates are those of licensee letters.
75 (B085) 75 (B077)
Item 1.2 - Post-Trip Review - Data and Information Capability
. Item 2.1 - Equipment Classification and Vendor Interface (Reactor Trip System Components)
C (04/15/86)
NC (04/15/86)
C (04/15/86)
NC (04/15/86) 2 ~ 2 2
r 0
FACILITY NAME:
DOCKET NO.:
LICENSEE:
NINE MILE POINT Unit 2 50-410 Niagara Mohawk Power Corporation GSI Status Sugar GSI/MPA No.
T1t1 e Licensee Status Determination Staff Status Determination Remarks 75 (B086) 75 (L003)
Item 2.2.1 - Equipment C (04/15/86)
NC (04/15/86)
Classification for Safety-Related Components Item 2.2.2 - Vendor Interface for Safety-Related Components GL 90-03 issued on 3/20/90 requires a response within 180 days.
By letter dated 8/21/90, the licensee changed the "C" status as shown on their 6/26/90 response to an "E" status.
75 (B078) 75 (B079) 75 (B087)
Items 3.1.1 II 3.1.2 -
C Post - Maintenance Testing (Reactor Trip System Components)
Item 3.1.3 - Post-Maintenance Testing-Changes to Test Require-ments (Reactor Trip System Components)
Items 3.2.1 5 3.2.2 -
C Post-Maintenance Testing (All Other Safety-Related Components)
NC (4/15/86)
NC (4/15/86)
NC (4/15/86) 2 ~ 2 3
C
FACILITY NAME:
DOCKET NO.:
LICENSEE:
NINE MILE POINT Unit 2 50-410 Niagara Mohawk Power Corporation GSI Status Sumnar GSI/MPA No.
75 (B088) 75 (B080)
Title Item 3.2.3 - Post-Maintenance Testing-Changes to Test Requirements (All Other Safety-Related Components)
Item 4.1 - Reactor Trip System Reliability (Vendor-Related Modifications)
Licensee Staff Status Status'eterminationDetermination C
NC (4/15/86)
NA Remarks For PWRs.
NMP-2 is a
BWR.
75 (B081)
Items 4.2.1 II 4.2.2-Reactor Trip System Reliability-Maintenance and Testing (Preventative Maintenance and Surveillance Program for Reactor Trip Breakers)
NA NA For PHRs.
NMP-2 is a
BWR.
75 (B082)
Item 4.3 - Reactor Trip NA System Reliability-Design Modifications (Automatic Actuation of Shunt Trip Attachment for Westinghouse and BSW Plants)
NA For W
8 B&W PWRS.
NMP-2 is a BWR.
2.2-4
r
FACILITY NAME:
DOCKET NO.:
LICENSEE:
NINE MILE POINT Unit 2 50-410 Niagara Mohawk Power Corporation GSI Status Summar GSI/MPA No.
75 (8090) 75 (8091) 75 (8092) 75 (8093)
Title Item 4.3 - Reactor Trip System Reliability-Tech Spec Changes (Automatic Actuation of Shunt Trip Attachment For Westinghouse and BOW Plants)
Item 4.4 - Reactor Trip System Reliability (Improvements in Maintenance and Test Procedures for BSW Plants)
Item 4.5.1 - Reactor Trip System Reliability-Diverse Trip Features (System Functional Testing)
Items 4.5.2 5 4.5.3-Reactor Trip System Reliability-Test Alternatives and Intervals (System Functional Testing)
Licensee Status Determination NA NA Staff Status Determination NA NC (4/15/86)
NC (4/15/86)
Remarks For W
BOW PWRs.
NMP-2 is a
BWR.
for BSW PWRs.
NMP-2 is a
BWR.
2.2-5
FACIlITY NAME: NINE MILE POINT Unit 2 DOCKET NO.:
50-410 LICENSEE:
Niagara Mohawk Power Corporation GSI Status Summar GSI/MPA No.
86 (B084)
Title Long Range Plan for Dealing with Stress Corrosion Cracking in BMR Piping Licensee Status Determination Staff Status Determination C (05/21/84) 2.2-6 Remarks GL 84-11 requested that information be provided.
NMPC's letter of 5/21/84 responded to GL 84-11.
NMPC indicated that the Preservice and Inser vice Inspection plan submitted as part of the FSAR included inspection require-ments for piping systems that could be affected by IGSCC.
Therefore, 5/21/84 is considered to be the implementation date for B084.
Subsequent assessments of the IGSCC issue were included in the SER section 5.2.3 and in the staff's evaluation, dated 8/17/90, of the response to MPA B097/GL 88-01.
These latter activities are beyond the scope of MPA 8084/GL 84-11.
C C;
le
c&
FACILITY NAME: NINE MILE POINT Unit 2 DOCKET NO.:
50-410 LICENSEE:
Niagara Mohawk Power Corporation GSI Status Summar GSI/MPA No.
93 (B098) 99 (L817)
Title Steam Binding of Auxiliary Feedwater Pumps RCS/RHR Suction Line Valve Interlock on PWRs Licensee Status Determination NA Staff Status Determination NA Remarks for all PWRs.
NMP-2 is a BWR.
For all PWRS.
NMP-2 is a
BWR.
124 A-13 (8017)
A>>13 (B022)
A-16 (D012)
Auxiliary Feedwater NA System Reliability Snubber Operability C
Assurance-Hydraulic Snubbers Snubber Operability C
Assurance - Mechanical Snubbers Steam Effects on BWR NA Core Spray Distribution NA NC For selected PWRs.
NMP-2 is a
BWR.
See NMPC coment.
See NMPC comment.
Not applicable to NMP-2 2 ~ 2 7
\\
0 4
FACILITY NAME: NINE MILE POINT Unit 2 DOCKET NO.:
50-410 LICENSEE:
Niagara Mohawk Power Corporation GSI Status Summar GSI/MPA No.
A-35 (B023)
B-10 B-36 B-63 (B045)
Title Adequacy of Offsite Power Systems Behavior of BWR Mark III Containments Develop Design, Testing and Maintenance Criteria for Atmosphere Cleanup System Air Filtration and Adsorption Units for Engineered Safety Features Systems and for Normal Ventilation Systems Isolation of Low Pressure Systems Connected to the Reactor Coolant System Pressure Boundary Licensee
- Staff Status Status Determination Determination NC NC NC 2.2-8 Remarks See NMPC comment.
Reviewed for NMP-2 in response to revision of SRP.
See SER Section 8.4.1.
NMP-2 has a
MARK II containment.
See NMPC comment.
See SER Section 6.5.5.
See NMPC comment.
See SER Sections 7.6 and 5.4.7.
5' 1