Letter Sequence Other |
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Results
Other: GO2-86-677, Provides Addl Info Re How Specific Valve/Generation Retest Criteria Established,Per 860131 & 0411 Requests for Exemptions & Tech Spec Changes Concerning App J,Type B & C Leak Rate Testing, GO2-87-007, Advises That Util Will Commit to Performing 10CFR50,App J Type B & C Leak Rate Testing in Accordance w/860131,870109 & 0211 Requests for Exemption/Tech Spec Change, GO2-87-120, Requests one-time Exemption from App J Type C Leak Rate Test Schedule.Proposed Exemption within Intent of App J Does Not Pose Undue Risk to Public Health & Safety & Allows More Efficient Allocation of Resources, ML17278A592, ML17278B168, ML17278B185, ML17278B192, ML17279A250
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MONTHYEARGO2-86-119, Application to Amend License NPF-21,requesting Exemption from App J Type B & C Leak Rate Test Schedules (NUREG/CR-4398) & Revising Tech Spec Section 4.6.1.2.d.Fee Paid1986-01-31031 January 1986
Application to Amend License NPF-21,requesting Exemption from App J Type B & C Leak Rate Test Schedules (NUREG/CR-4398) & Revising Tech Spec Section 4.6.1.2.d.Fee Paid
Project stage: Request
ML17278A5921986-01-31031 January 1986
Proposed Tech Specs,Revising Section 4.6.1.2.d Re App J Type B & C Leak Rate Test Schedules
Project stage: Other
GO2-86-338, Requests That Second Portion of 860131 Request for Extension of Interval for Leak Rate Testing Be Delayed Until Exemption to App J Processed So as Not to Impact Present Outage Schedule1986-04-11011 April 1986
Requests That Second Portion of 860131 Request for Extension of Interval for Leak Rate Testing Be Delayed Until Exemption to App J Processed So as Not to Impact Present Outage Schedule
Project stage: Request
GO2-86-677, Provides Addl Info Re How Specific Valve/Generation Retest Criteria Established,Per 860131 & 0411 Requests for Exemptions & Tech Spec Changes Concerning App J,Type B & C Leak Rate Testing1986-07-22022 July 1986
Provides Addl Info Re How Specific Valve/Generation Retest Criteria Established,Per 860131 & 0411 Requests for Exemptions & Tech Spec Changes Concerning App J,Type B & C Leak Rate Testing
Project stage: Other
ML17278B1681987-01-0909 January 1987
Forwards Addl Info Re Proposed Type C Testing Program,Per Telcon
Project stage: Other
ML17278B1891987-02-11011 February 1987
Provides Supplemental Info on Request for Exemption & Tech Spec Change Re App J Type B & C Leak Rate Testing.Type C Containment Isolation Valves Will Be Tested at Intervals Not Greater than 27 Months
Project stage: Supplement
ML17278B1851987-02-11011 February 1987
Informs That Washington State Energy Facility Site Evaluation Council Has No Comments on Proposed Amends to License NPF-21 Re Exemption & Changes to App J & Section 4.6.1.2.d & B & C Leak Rate Testing
Project stage: Other
ML17278B1921987-02-19019 February 1987
Corrected Ltr Expressing Appreciation for Opportunity to Review Util 860131,0822 & 870109 Requests for Amend to Tech Specs Re B&C Leak Rate Testing & 860710 Request Concerning Safety/Relief Valve Tolerances.No Comments Offered
Project stage: Other
GO2-87-007, Advises That Util Will Commit to Performing 10CFR50,App J Type B & C Leak Rate Testing in Accordance w/860131,870109 & 0211 Requests for Exemption/Tech Spec Change1987-03-0404 March 1987
Advises That Util Will Commit to Performing 10CFR50,App J Type B & C Leak Rate Testing in Accordance w/860131,870109 & 0211 Requests for Exemption/Tech Spec Change
Project stage: Other
GO2-87-120, Requests one-time Exemption from App J Type C Leak Rate Test Schedule.Proposed Exemption within Intent of App J Does Not Pose Undue Risk to Public Health & Safety & Allows More Efficient Allocation of Resources1987-04-0707 April 1987
Requests one-time Exemption from App J Type C Leak Rate Test Schedule.Proposed Exemption within Intent of App J Does Not Pose Undue Risk to Public Health & Safety & Allows More Efficient Allocation of Resources
Project stage: Other
ML17279A2481987-04-29029 April 1987
Exemption from Requirements of 10CFR50,App J,Extending Interval Between Type B & C Testing of Containment Valves from 24 to 27 Months
Project stage: Approval
ML17279A2501987-04-29029 April 1987
Amend 41 to License NPF-21,extending Interval Between Type B & C Testing of Containment Valves from 24 to 27 Months
Project stage: Other
ML17279A2511987-04-29029 April 1987
Safety Evaluation Supporting Amend 41 to License NPF-21
Project stage: Approval
1987-02-11
[Table View] |
Text
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0 CONTAINMENT SYSTEMS SURVEILLANCE REQUIREMENTS Continued d.
Type B and C tests shall be conducted with gas at P
, 34.7 psig," at intervals no greater than 24<months except for testP involving:
l.
Air locks, 2.
Main steam line isolation valves, 3.
Valves pressurized with fluid from a seal
- system, 4.
ECCS and RCIC containment isolation valves in hydrostatically
. tested lines which penetrate th'e primary containment, and e.
h.
J ~
5.
Purge supply and exhaust isolation valves with resilient seals.
Air locks shall be tes ed and demonstrated OPERABLE per Surveillance Requi r ement 4. 6.1. 3.
Main steam line isolation valise shall be leak tested at least once per 18 months.
~V Leakage from isolation yal'ves that are sealed with fluid from a seal system may be excluded~suhject to the provisions of Appendix J,Section III.C. 3, when4determining the combined leakage rate, provided the seal system and",'valves are pressurized to at least 1. 10 P
a 38.2 psig, and the'eal system capacity is adequate to maintain system pressure for. at least 30 days.
ECCS and RCIC contain'ment isolation valves in hydrostatically tested lines which pentrate the primary containment shall, be leak tested at least once per 18 months.
Purge supply and exhaust isolation valves with resilient material seals shall be tested and demonstrated OPERABLE per Surveillance Requirements 4, 6. l. 8. 2 and 4. 6. 1. 8. 3.
The provisions of Specification 4.0.2.are not applicable to 24-month or 40 + 10 month surveillance intervals.
"Unless a hydrostatic test is required per Table 3.6.3-1.
- 'Forthose tests conducted during refueling outages, the 24 month interval
'may be exceeded by no more than 3 months.
8602100231 860131 P
j WASHINGTON NUCLEAR - UNIT 2 3/4 6-4
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