ML102240063
| ML102240063 | |
| Person / Time | |
|---|---|
| Site: | Millstone  |
| Issue date: | 07/21/2010 |
| From: | Price J Dominion, Dominion Nuclear Connecticut |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| 10-367, FOIA/PA-2011-0115 | |
| Download: ML102240063 (17) | |
Text
Dominion Nuclear Connecticut, Inc.
5000 Dominion Boulevard, Glen Allen, Virginia 23060 Jkominionllf Web Address: www.dom.com July 21, 2010 U.S. Nuclear Regulatory Commission Serial No.10-367 Attention: Document Control Desk NSSL/MLC RO Washington, DC 20555 Docket No.
50-423 License No.
NPF-49 DOMINION NUCLEAR CONNECTICUT, INC.
MILLSTONE POWER STATION UNIT 3 LICENSE AMENDMENT REQUEST TO RELOCATE TECHNICAL SPECIFICATION 3/4.7.14, AREA TEMPERATURE MONITORING In accordance with the provisions of 10 CFR 50.90, Dominion Nuclear Connecticut, Inc. (DNC) is submitting a license amendment request to relocate Millstone Power Station Unit 3 (MPS3) Technical Specification (TS) 3/4.7.14, "Area Temperature Monitoring," and associated Table 3.7-6, to the MPS3 Technical Requirements Manual (TRM).
DNC is proposing this change to the MPS3 TSs on the basis of the NRC's "Final Policy Statement on Technical Specifications Improvements for Nuclear Power Reactors" (58 FR 39132), dated July 22, 1993; and, the results of the NRC staff review of Westinghouse report, WCAP-11618, "Methodically Engineered, Restructured and Improved Technical Specifications, Merits Program - Phase II Task 5, Criteria Application," as documented in letter dated May 9, 1988 to R. A.
Newton, Chairman of the Westinghouse Owners Group (References 1 and 2).
Relocating TS 3/4.7.14 to the TRM will continue to provide adequate controls for area temperature monitoring in those areas designated in TS Table 3.7-6. The TRM is a licensee-controlled document that is administered under the provisions of 10 CFR 50.59. Changes to the TRM require compliance with 10 CFR 50.59 and are reviewed and approved by the Facility Safety Review Committee (FSRC) prior to implementation. provides a description and assessment of the proposed change.
Attachments 2 and 3 provide the MPS3 marked-up TS pages and TS Bases pages, respectively.
The marked-up TS Bases pages are provided for information only.
Similar license amendment changes have been approved by the NRC for Seabrook Unit 1 (Amendment No. 63 issued October 1, 1999), Shearon Harris Unit 1 (Amendment No. 62 issued August 28, 1995), and Vogtle Units 1 and 2 (Amendment Nos. 83 and 61, respectively, issued January 23, 1995).
DD0
Serial No: 10-367 Docket No. 50-423, Relocate TS 3/4.7.14 Page 2 of 3 The proposed amendment does not involve a Significant Hazards Consideration pursuant to the provisions of 10 CFR 50.92.
The FSRC has reviewed and concurred with the determinations herein.
Issuance of this amendment is requested no later than July 28, 2011, with the amendment to be implemented within 60 days.
In accordance with 10 CFR 50.91(b), a copy of this license amendment request is being provided to the State of Connecticut.
Should you have any questions in regard to this submittal, please contact Ms.
Wanda Craft at (804) 273-4687.
Sincerely, J. JAln rice Vice Prisident-Nuclear Engineering COMMONWEALTH OF VIRGINIA COUNTY OF HENRICO The foregoing document was acknowledged before me, in and for the County and Commonwealth aforesaid, today by J. Alan Price, who is Vice President - Nuclear Engineering of Dominion Nuclear Connecticut, Inc. He has affirmed before me that he is duly authorized to execute and file the foregoing document in behalf of that company, and that the statements in the document are true to the best of his knowledge and belief.
Acknowledged before me this QlS4day ofi-*12,4,2010.
axpires:
z Notary Public n
Commonwealth of Virginia Not My Com sion Expires Apr 30. 2013 I I' C n-T Attachments:
- 1. Evaluation of Proposed License Amendment
- 2. Marked-Up Technical Specification Pages
- 3. Marked-Up Technical Specification Bases Pages (For Information Only)
Commitments made in this letter: 'None
Serial No: 10-367 Docket No. 50-423 Relocate TS 3/4.7.14 Page 3 of 3
References:
- 1. Westinghouse Owners Group Letter, OG-87-43, dated November 12, 1987, R. A. Newton to USNRC Document Control Desk,
Subject:
"Westinghouse Owners Group, MERITS Program Phase II, Task 5 Criteria Application Topical Report."
- 2. Results of the NRC staff review of Westinghouse report, WCAP-11618, "Methodically Engineered, Restructured and Improved Technical Specifications, Merits Program - Phase II Task 5, Criteria Application," as documented in letter dated May 9, 1988 to R. A. Newton, Chairman of the Westinghouse Owners Group.
cc:
U.S. Nuclear Regulatory Commission Region I Regional Administrator 475 Allendale Road King of Prussia, PA 19406-1415 C. J. Sanders NRC Project Manager U.S. Nuclear Regulatory Commission, Mail Stop 08B3 One White Flint North 11555 Rockville Pike Rockville, MD 20852-2738 NRC Senior Resident Inspector Millstone Power Station Director Bureau of Air Management Monitoring and Radiation Division Department of Environmental Protection 79 Elm Street Hartford, CT 06106-5127
Serial No.10-367 Docket No. 50-423 ATTACHMENT I LICENSE AMENDMENT REQUEST TO RELOCATE TECHNICAL SPECIFICATION 3/4.7.14, AREA TEMPERATURE MONITORING EVALUATION OF PROPOSED LICENSE AMENDMENT DOMINION NUCLEAR CONNECTICUT, INC.
MILLSTONE POWER STATION UNIT 3
Serial No.10-367 Docket No. 50-423 Relocate TS 3/4.7.14, Page 1 of 6 LICENSE AMENDMENT REQUEST TO RELOCATE TECHNICAL SPECIFICATION 3/4.7.14 "AREA TEMPERATURE MONITORING" TO THE TECHNICAL REQUIREMENTS MANUAL
1.0 INTRODUCTION
In accordance with the provisions of 10 CFR 50.90, Dominion Nuclear Connecticut, Inc. (DNC) is submitting a license amendment request to relocate Millstone Power Station Unit 3 (MPS3) Technical Specification (TS) 3/4.7.14, "Area Temperature Monitoring," and associated Table 3.7-6, to the MPS3 Technical Requirements Manual (TRM).
DNC is proposing this change to the MPS3 TSs on the basis of the NRC's "Final Policy Statement on Technical Specifications Improvements for Nuclear Power Reactors" (58 FR 39132), dated July 22, 1993; and, the results of the NRC staff review of Westinghouse report, WCAP-1 1618, "Methodically Engineered, Restructured and Improved Technical Specifications, Merits Program - Phase II Task 5, Criteria Application," as documented in letter dated May 9, 1988 to R. A. Newton, Chairman of the Westinghouse Owners Group.
2.0 PROPOSED CHANGE
S The proposed change to TS 3/4.7.14 is to remove this section, and associated Table 3.7-6, in its entirety and replace with the word DELETED. See Attachment 2 for the marked-up technical specification* pages.
3.0 BACKGROUND
Area temperature limits for MPS3 have been established to ensure environmentally qualified equipment will not be exposed to temperatures beyond which they were originally qualified, and will therefore remain operable to perform their intended safety function. These limits and their corresponding plant locations are presently contained in TS 3/4.7.14. The consequences of exceeding the area temperature limits are that extended exposure to elevated temperatures could impact the instrument accuracy per the original equipment specifications and contribute to equipment degradation that exceeds the rate assumed by the MPS3 Environmental Qualification (EQ) Program.
Extended exposure to elevated temperatures in excess of 136 degrees F could contribute to equipment degradation that exceeds the rate assumed by the MPS3 EQ Program. This has not occurred to date.
Serial No.10-367 Docket No. 50-423 Relocate TS 3/4.7.14, Page 2 of 6
4.0 TECHNICAL ANALYSIS
DNC is proposing this change to the MPS3 TSs on the basis of the NRC's "Final Policy Statement on Technical Specifications Improvements for Nuclear Power Reactors" (58 FR 39132), dated July 22, 1993; and, the results of the NRC staff review of Westinghouse report, WCAP-1 1618, "Methodically Engineered, Restructured and Improved Technical Specifications, Merits Program - Phase II Task 5, Criteria Application," as documented in letter dated May 9, 1988 to R. A. Newton, Chairman of the Westinghouse Owners Group.
The NRC's "Final Policy Statement on Technical Specifications Improvements for Nuclear Power Reactors" provided a specific set of four objective criteria to determine which of the design conditions and associated surveillances should be located in TSs as limiting conditions for operation (LCOs). The Final Policy Statement noted that implementation of these additional criteria, as amended to 10 CFR 50.36, may cause some requirements presently in TSs to no longer merit inclusion in TSs. Based upon application of 10 CFR'50.36 criterion, the following determination was made:
Criterion 1) Area temperature monitoring is not installed instrumentation that is used to detect, and indicate in the control room, a significant abnormal degradation of the reactor coolant pressure boundary. Thus, area temperature monitoring does not satisfy Criterion 1 for retention in TSs.
Criterion 2) Area temperature monitoring is not a process variable, design feature, or operating restriction that is an initial condition of a design basis accident or transient analysis that either assumes the failure of or presents a challenge to the integrity of a fission product barrier. Therefore, area temperature monitoring does not satisfy Criterion 2 for retention in TSs.
Criterion 3) Area temperature monitoring is not a structure, system, or component that is part of the primary success path and which functions or actuates to mitigate a design basis accident or transient that either assumes the failure of or presents a challenge to the integrity of a fission product barrier. Therefore, area temperature monitoring does not satisfy Criterion 3 for retention in TSs.
Criterion 4) Based upon a Probabilistic Risk Assessment (PRA) summary report for the Merits Program (contained in Section 4 of WCAP-11618), area temperature monitoring was not identified as a significant risk contributor. Therefore, area temperature monitoring does not satisfy Criterion 4 for retention in TSs.
Additionally, in WCAP-1 1618, the Westinghouse Owners Group (WOG) applied the NRC's screening criteria to the Westinghouse Standard Technical Specifications (NUREG-0452, Revision 4 and draft Revision 5). Among the specifications to which the screening criteria were applied was TS 3/4.7.13, Area Temperature Monitoring.
Serial No.10-367 Docket No. 50-423 Relocate TS 3/4.7.14, Page 3 of 6 Based upon that application, it was concluded that the area temperature monitoring LCO did not merit inclusion in TSs and could be relocated to a licensee-controlled document.
The equipment qualification requirements for MPS3 are contained in the Dominion Fleet EQ Program Description and the MPS3 Final Safety Analysis Report (FSAR)
Section 3.11B.1. The EQ program is based on the requirements and guidelines of 10 CFR 50.49, "Environmental Qualification of Electric Equipment Important to Safety for
.Nuclear Power Plants," and NUREG-0588, Revision 1, "Interim Staff Position on Environmental Qualification of Safety Related Electrical Equipment," as endorsed by Regulatory Guide 1.89, Revision 1. Additionally, the environmental requirements of 10 CFR Part 50, Appendix A, General Design Criterion 4, "Environmental and Missile Design Bases," are addressed in FSAR Section 3.11B.1. Electrical equipment within the scope of the EQ program meets the requirements of IEEE Standard 323-1974, "Standards for Qualifying Class 1 E Equipment for Nuclear Power Generating Stations."
Adherence to the TRM, FSAR and regulatory documents is controlled by ensuring that any changes to the EQ program, including the affected equipment or changes in the plant environment, are documented through Millstone's Design Change Request (DCR) and Minor Modification (MMOD) process. In compliance with the DCR/MMOD process, changes to the EQ program or engineering evaluations that affect the EQ program are reviewed pursuant to the requirements of 10 CFR 50.59. In addition, DNC's policies and procedures ensure that other processes such as corrective and preventative maintenance activities, as well as new procedures and procedure changes, are reviewed for equipment qualification technical accuracy. Therefore, relocating TS 3/4.7.14 to the TRM will still provide adequate controls for area temperature monitoring in those areas designated in TS Table 3.7-6. Changes to the TRM require a 10 CFR 50.59 evaluation and are reviewed and approved by the Facility Safety Review Committee prior to implementation.
In summary, the requirements for area temperature monitoring do not need to be controlled by TS because (1) their inclusion in TSs is not required by 10 CFR 50.36 and (2) changes to the requirements will be adequately controlled under the provisions of 10 CFR 50.59. Additionally, the proposed change would make the MPS3 TSs consistent with the guidance provided in the NRC's Standard Technical Specifications, Westinghouse Plants (NUREG-1431), in that the Westinghouse Standard Technical Specifications do not include an LCO for area temperature monitoring.
Serial No.10-367 Docket No. 50-423 Relocate TS 3/4.7.14, Page 4 of 6
5.0 REGULATORY ANALYSIS
5.1 NO SIGNIFICANT HAZARDS CONSIDERATION The NRC has provided standards for determining whether a significant hazards consideration (SHC) exists as stated in 10 CFR 50.92(c). A proposed amendment to an operating' license for a facility does not involve a SHC if operation of the facility in accordance with a proposed amendment would not: 1) involve a significant increase in the probability or consequences of an accident previously evaluated; or 2) create the possibility of a new or different kind of accident from any accident previously evaluated; or 3) involve a significant reduction in a margin of safety.
In accordance with the standards set forth in 10 CFR 50.92(c), DNC has concluded that the proposed change does not represent a SHC. A discussion of these standards as they relate to this change, and the basis for the conclusion, is provided below.
Criterion 1
/
Will operation of the facility in accordance with the proposed change involve a significant increase in the probability or consequences of an accident previously evaluated?
Response: No.
The provisions of TS 3/4.7.14 for area temperature monitoring of the TS specified or selected areas are neither part of an initial condition of a design basis accident or transient that either assumes the failure of or presents a challenge to the integrity of a fission product barrier, nor are they relied upon as a primary success path to mitigate such events. The provisions for area temperature monitoring are not related to events which are considered frequent or dominant contributors to plant risk. Area temperature monitoring is not considered a designfeature or an operating restriction which is an initial condition of a design basis accident or transient analysis, nor does it provide a function or actuate any accident mitigation feature in order to mitigate the consequences of a design basis accident or transient.
The environmental qualification and operability of the safety-related equipment will not be adversely affected by the proposed changes to the area temperature monitoring program. The relocation of the TS to the TRM will not increase the probability that the area temperature design limits will be exceeded or result in a loss of qualified life of safety-related equipment. In addition, the consequences of exceeding the temperature limits will not significantly differ from the existing program since an evaluation of qualified life and operability will continue to be performed as part of the EQ program in accordance with the requirements of 10 CFR 50.49.
Serial No.10-367 Docket No. 50-423 Relocate TS 3/4.7.14, Page 5 of 6 Relocating TS 3/4.7.14 to the TRM will still provide adequate controls for area temperature monitoring in those areas designated in TS Table 3.7-6. Changes to the TRM require 10 CFR 50.59 safety evaluations and are reviewed and approved by the Facility Safety Review Committee prior to implementation.
Based on the reasons presented above, operation of the facility in accordance with the proposed amendment would not involve a significant increase in -the probability or consequences of an accident previously evaluated.
Criterion 2 Will operation of'the facility in accordance with this proposed change create the possibility of a new or different kind of accident from any accident previously evaluated?
Response: No.
The proposed change will not create the possibility of a new or different kind of accident from any accident previously evaluated. No new accident will be created as a result of relocating TS 3/4.7.14 to the TRM. This change is administrative in nature and does not change the level of programmatic and procedural control necessary to assure operation of the facility in a safe manner. Plant operation will not be affected by the proposed change and no new failure modes will be created. Therefore, the proposed change does not create the possibility of a new or different kind of accident from any previously evaluated.
Criterion 3 Will operation of the facility in accordance with this proposed change involve a significant reduction in the margin of safety?
Response: No.
There is no adverse impact on equipment design or operation and there are no changes being made to the TS required safety limits or safety system settings that would adversely affect plant safety. The proposed change is administrative in nature and does not change the level of programmatic and procedural control necessary to ensure that environmentally qualified equipment will not be exposed to temperatures beyond that which they were originally qualified. The relocated requirements will continue to ensure that environmental qualification temperature limits of safety-related equipment will not be exceeded without an evaluation of equipment operability; therefore, the margin of safety is unchanged.
Serial No.10-367 Docket No. 50-423 Relocate TS 3/4.7.14,, Page 6 of 6 5.2 APPLICABLE REGULATORY REQUIREMENTS/CRITERIA The equipment qualification requirements for MPS3 are contained in the Dominion Fleet EQ Program Description and the MPS3 Final Safety Analysis Report (FSAR)
Section 3.11B.1. The EQ program is based on the requirements and guidelines of 10 CFR 50.49, "Environmental Qualification of Electric Equipment Important to Safety for Nuclear Power Plants," and NUREG-0588, Revision 1, "Interim Staff Position on Environmental Qualification of Safety Related Electrical Equipment," as endorsed by Regulatory Guide 1.89, Revision 1. Additionally, the environmental requirements of 10 CFR Part 50, Appendix A, General Design Criterion 4, "Environmental and Missile Design Bases," are addressed in FSAR Section 3.11B.1. Electrical equipment within the scope of the EQ program meets the requirements of IEEE Standard 323-1974, "Standards for Qualifying Class 1 E Equipment for Nuclear Power Generating Stations."
6.0 ENVIRONMENTAL CONSIDERATION
DNC has determined that the proposed amendment would change requirements with respect to use of a facility component located within the restricted area, as defined by 10 CFR 20, or an inspection or surveillance requirement. DNC has evaluated the proposed change and has determined that the change does not involve (i) a significant hazards consideration, (ii) a significant change in the types or significant increase in the amounts of any effluent that may be released off site, or (iii) a significant increase in individual or cumulative occupational radiation exposure. Accordingly, the propose amendment meets the eligibility criterion for categorical exclusion set forth in 10 CFR 51.22(c)(9). Therefore, pursuant to 10 CFR 51.22(b), no environmental impact statement or environmental assessment need to be prepared in connection with the proposed amendment.
'I
Serial No.10-367 Docket No. 50-423 ATTACHMENT 2 LICENSE AMENDMENT REQUEST TO RELOCATE TS 314.7.14, "AREA TEMPERATURE MONITORING" MARKED-UP TECHNICAL SPECIFICATION PAGES DOMINION NUCLEAR CONNECTICUT, INC.
MILLSTONE POWER STATION UNIT 3
'o k,
PLANTSYLSTEMS DTX
.3/4.7. 14Cý2ATEMPEZ MONIýTORING
~4,199~7~
'-9 LIMITING CONDITION FOR OPERATION 3.7.14 The temperature limit of each area shown in Table 3.7-6 shall not be exceeded.
APPLICABILITY:
Whenever the equipment in an affected area is required to be OPERABLE.
ACTION:
With one or more areas exceeding the temperature limit(s) Shown in Table3.7-6:
- a.
By less than 20*F and for less than 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />, record the cumulative time and the amount by which the temperature in the affected area(s) exceeded the limit(s)..
- b.
By less than 20'F and for greater than or equal to 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />, prepare and submit to the Commission within'30 days, pursuant to Specification 6.9.2, a Special Report that provides a record of the cumulative time and the-amount by which the temperature in the affected area(s) -exceeded the limit(s) and an analysis to demonstrate the continued OPERABILITY of the affected equipment. The provisions of Specification 3.0.3 are not applicable.
C.
With one or more areas exceeding the temperature limit(s) shown in Table 3.7-6 by greater than or equal to 20*F, prepare and 'submit a Special Report as required by ACTION b. above and within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> either restore the area(s) to within the temperature limit(s) or declare the equipment in the affected area(s) inoperable.
SURVEILLANCE REQUIREMENTS 4.7.14 The temperature in each of the ari within its limits:
- a.
At least once per seven days w.
- b.
At least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> whe as shown in Table 3.7-6 shall be determined to be hen the alarm is OPERABLE,;and; n the alarm is inoperable.
MILLSTONE - UNIT 3 3/4 7-32 Amendment No.
9-5, 400, 444-
TABLE 3.7-6
..AREA TEMPERATURE MONITORING rURE LIMIT (-F)
AREA TEMPERA]
AB-02, AB-03, AB-04, AB-06, AB-07, AB-08, AB-09,,
AB-10, AB-11, AB-13, AB-16, AB-19, AB-21, AB-22, AB-25, AB-26, AB-29, AB-33, AB-35,.
AB-39.
AUXILTARY BIJTLDNG AAUXELIARY BUILDING VCT and Boric Acid Transfer Pump Area, El 43' 6" Charging Pump Area, El 24' 6" General Area, El 66' 6" General Area, El 43' 6" General Area, El4' 6" General Area (East), El 4' 6" General Area (South), El4' 6" General Area, El 4"6" General Area, El 43' 6" General Area (North), El 4' 6" Supplemental Leak Collection Filter Area, El 66' 6" MCC/Rod Drive Area, El 24' 6" MCC Air Conditioning Room, El 66' 6" Rod Drive Area, El 43' 6" Charging Pump Area, El 24' 6" RPCOW Pump Area, El 24' 6" General Area (Southeast), El 24' 6" Boric Acid Tank Area, El 43'6" Boric Acid Tank Area, El 43' 6" Fuel Building and Auxiliary Building Filter Area, El 66' 6"
_ 120
_* 110 I i20
< 120
< 120 120
< 120
< 120
< 120 1
120
- 9 120
- 120
_< 120
< 120
!9 110
<.110
_ 120
< 120
< 120 AB-39
- 120 I
f7LAA)K, MILLSTONE - UNIT 3 3/4 7-33 Amendment No. 4Q@-
TABLE 3.7-6 (Continued)
AREA TEMPERATURE MONITORING 2_.
CB-0I, CB-02, CB-03, CB-04, CB-05, 3.
CS-01, CS-02, CS-03, CS-04, 4.
CW-01, 5.
.AREA CONTROL BUILDING Switchgear and Battery Rooms, El 4'6" Cable Spreading Room, E124' 6" Control and Computer Rooms, El 47' 6" Chiller Room, El 64' 6" Mechanical Equipment Room, El 64-6" CONTAINMENT Inside Crane Wall, El all except CS-03 and CS-04 Outside Crane Wall, El all Pressurizer Cubicle, El all Inside Crane wall, El-51' 4" except CS-03 and steam generator enclosures INTAKE STRUCTURE Entire Building DIESEL GENERATOR BUILDING TEMPERATURE LIMIT (-F)
< 104
< 110
.95 5 104
- !9 104
< 120
< 1.20
_* 130
<- 120
< 110
< 120
-!5 110
< 110
< 110
- 110 29 110
< 110
< 110 DG-01, Entire Building
- 6.
.ESF BUILDING ES-01, HVAC and MCC Area, El 36' 6" ES-02, SIH Pump Area, El 21' 6" ES-03, Pipe Tunnel Area, El 4' 6" ES-04, RHS Cubicles, El all ES-05, RSS Cubicles, El all ES-06, Motor Driven Auxiliary Feedwater Pump Area, El 24'-6" ES-07, Turbine Driven Auxiliary Feedwater Pump Area, El 24' 6" It MILLSTONE - UNIT 3 3/4 7-34 Amendment No..,-*-
August 12, 2008*
r
.TABLE 3.7-6 (Continued)
AREA TEMPERATURE MONITORING AREA TEMPERATURE LIMIT 1(F) 7.
FV-01, 9.
HR-01, HR-02, HR-03, HR-04, 10.
MS-01, MS-02, 11.
12.
TN-02, 13.
YD-01, FUELBUILDING Fuel Pool Pump Cubicles, El 24' 6" General Area, El 52' 4" FUEL OIL VAULT Diesel Fuel Oil Vault HYDROGEN RECOMBINER BUILDING Recombiner Skid Area, El 24' 6" Controls Area, El 24' 6" Sampling Area, El 24' 6" HVAC Area, El 37' 6" MAIN STEAM VALVE BUILDING Areas above El. 58' 0" Areas below El. 58' 0" DELETED TUNNEL Pipe Tunnel-Auxiliary, Fuel and ESF Building YARD Yard 119
ý9108
< 95
< 1.25
<_ 110
<_ 110
- 110
_5 140
< 140 I
I ~
I J~4 115 1Ti*6 Pfi-~t IKf~AJT'TjNAW-LY T
u T3'L AtNOI NfILLSTONE - UNIT 3 3/4 7-35 Amendment No. 9-2,400, 2,'42
Serial No.10-367 Docket No. 50-423 ATTACHMENT 3 LICENSE AMENDMENT REQUEST TO RELOCATE TS 3/4.7.14 "AREA TEMPERATURE MONITORING" MARKED-UP TECHNICAL SPECIFICATION BASES PAGES (FOR INFORMATION ONLY)
DOMINION NUCLEAR CONNECTICUT, INC.
MILLSTONE POWER STATION UNIT 3
E~~i~~
IP1MYT1 C PLANT SYSTEMS BASES
.3/47.10 SNUBBERS (Continued)
-figure 4.7-1 was developed using "Wald's Sequential Probability Ratio Plan" as described in "Quality Control and Industrial Statistics" by Acheson J. Duncan.
Permanent or other exemptions from the surveillance program for individual snubbers may be granted by the Commission ifa justifiable basis for exemption is presented and, if applicable, snubber life destructive testing was performed to qualify the snubbers for the applicable design conditions at either the completion of their fabrication or at a subsequent date.
Snubbers so exempted shall be listed in the list of individual snubbers indicatin the extent of the exemptions.
The service life of a snubber is established via manufacturer input and information through consideration of the snubber -service conditions and associated installation and maintenance records (newly installed snubbers, seal replaced, spring replaced, in high radiation area, in high temperature area, etc.). The requirement to monitor the snubber service life is included to ensure that the snubbers periodically undergo a performance evaluation in view of their age and operating conditions. These records will provide statistical bases for future consideration of snubber service life.
3/4.7.11 DELETED
.J 0
D
,3/4.7. 4'AREA TE PERATURE MONITORING The area temperature limitations ensure that safety-related equipment will not be subjected to temperatures in excess of their environmental qualification temperatures. Exposure to excessive temperatures may degrade equipment and can cause a loss of its OPERABILITY.
.The temperature limits include an allowance for instrument error of +/- 2,2F..
MILLSTONE - UNIT 3 B 3/4 7-25 Amendment Nos. :&,-84, 00, 44--9,.
4-36,