Letter Sequence Other |
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Results
Other: 05000344/LER-1980-006, Forwards LER 80-006/01T-0, 05000344/LER-1980-006-01, /01T-0:on 800425,during Preplanned Fuel Insp Program,Two Fuel Assemblies Found to Have Abnormal Clad Degradation.Caused by water-jet Impingement on Fuel Pins Via Enlarged Baffle Plate Joint Gap, ML19309C391, ML19323C628, ML19323C633, ML19341A169, ML19341A172, ML19341A175, ML19345F215, ML19345F217, ML19347F033, ML19347F037, ML20003D352, ML20005A518
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MONTHYEARML19309C3911980-04-0404 April 1980 Provides Schedule for 800426-0505 Fuel Insps During Cycle 2 Refueling Outage.Insps Will Be Performed by Westinghouse & Util in Spent Fuel Pool Area.Preliminary Oral Rept Will Be Made Prior to Return to Operation Project stage: Other 05000344/LER-1980-006-01, /01T-0:on 800425,during Preplanned Fuel Insp Program,Two Fuel Assemblies Found to Have Abnormal Clad Degradation.Caused by water-jet Impingement on Fuel Pins Via Enlarged Baffle Plate Joint Gap1980-05-0808 May 1980 /01T-0:on 800425,during Preplanned Fuel Insp Program,Two Fuel Assemblies Found to Have Abnormal Clad Degradation.Caused by water-jet Impingement on Fuel Pins Via Enlarged Baffle Plate Joint Gap Project stage: Other 05000344/LER-1980-006, Forwards LER 80-006/01T-01980-05-0808 May 1980 Forwards LER 80-006/01T-0 Project stage: Other ML19323C6281980-05-12012 May 1980 Forwards License Change Application 61 Requesting Amend to License NPF-1 Project stage: Other ML19323C6331980-05-12012 May 1980 License Change Application 61 Requesting Amend to License NPF-1,adding License Condition Re Fuel Assemblies.Waives Requirement That Each Fuel Assembly Contain 264 Fuel Rods. Outer Zircaloy-4 Clad Fuel Rods May Be Replaced Project stage: Other ML19320C1701980-06-27027 June 1980 Forwards Amend 45 to License NPF-1,safety Evaluation & Notice of Issuance & Availability Project stage: Approval ML19341A1751981-01-0707 January 1981 Requests That Util Startup & Power Escalation Testing Rept Be Withheld from Public Disclosure Per 10CFR2.790.Original Affidavit AW-76-31 Encl Project stage: Other ML19341A1691981-01-13013 January 1981 Forwards Proprietary & Nonproprietary Versions of Improved Bol,Hzp,Power Distribution Prediction, Per 801118 Request. Requests Withholding (Ref 10CFR2.790) Project stage: Other ML19341A1721981-01-13013 January 1981 Nonproprietary Version of Improved Bol,Hzp Power Distribution Prediction Project stage: Other ML19345F2151981-02-0505 February 1981 Forwards License Change Application 70,amending License NPF-1 to Waive Requirement Re Fuel Assembly Rods.Fuel Assemblies in Core Contain Three Stainless Steel Dummy Fuel Rods.W/Class III Amend Fee & Certificate of Svc Project stage: Other ML19345F2171981-02-0505 February 1981 License Change Application 70,amending License NPF-1 to Waive Tech Spec 5.3.1 Requirement Re Fuel Assembly Rods.Fuel Assemblies in Core Contain Three Stainless Steel Dummy Fuel Rods.Westinghouse Evaluation Encl Project stage: Other ML20003D3521981-03-20020 March 1981 Responds to NRC 810310 Telcon Requesting Addl Info Re License Change Application 70.Updated Table 2 Reflecting Final Cycle 4 Design Encl.Prompt Approval Requested to Avoid Impacting Spring Refueling Outage Project stage: Other ML19347F0331981-05-0808 May 1981 Amend 60 to License NPF-1,approving Use of Two Modified Fuel Assemblies Containing Three Stainless Steel Rods for Fuel Cycle 4 & One Subsequent Fuel Cycle Project stage: Other ML19347F0371981-05-0808 May 1981 Notice of Issuance & Availability of Amend 60 to License NPF-1 Project stage: Other ML19347F0361981-05-0808 May 1981 Safety Evaluation Supporting Amend 60 to License NPF-1 Project stage: Approval ML19347F0311981-05-0808 May 1981 Forwards Amend 60 to License NPF-1,safety Evaluation & Notice of Issuance & Availability Project stage: Approval ML20005A5181981-06-25025 June 1981 Forwards Preliminary Results of Insp of Fuel Assemblies Subj to cross-flow Baffle Jetting Per Paragraph 2.C(11) of License NPF-1 & FSAR Project stage: Other 1981-01-13
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l March 20, 1981 Trojan Nuclear Plant Docket 50-344 License NPF-1 Director of Nuclear Reactor Regulation ATTN:
Mr. Robert A. Clark, Chief Operating Reactors Branch No. 3 Division of Operating Reactors U. S. Nuclear Regulatory Commission Washington, DC 20555
Dear Sir:
On February 5,1981 License Change Application (LCA) 70 was submitted requesting permission to use two dummy stainless-steel-rodded fuel assemblies for two additional fuel cycles at the Trojan Nuclear Plant.
A telephone conversation was held on March 10, 1981 with M. Chatterton of the NRC to discuss this LCA.
In response to an NRC request made during that conversation, Table 2 of the typical evaluation contained in LCA 70 has been updated to reflect the final Cycle 4 design and is attached to this letter. Only minor changes were necessary as a result of the final design. Table 3 of LCA 70 was also reviewed; however, no changes to this table were necessary.
The remaining NRC questions were resolved during the telephone conver-sation. However, it was noted that the NRC reviewer was reluctant to approve the LCA for an additional core cycle beyoad Cycle 4 without having first reviewed the modified fuel assembly locations and the corresponding impact on the core design. We would be receptive to an amendment that would allow use of the two modified assemblies in the Cycle 4 core and also require submittal of an update of the information contained in LCA 70 in letter form (as opposed to the form of a new LCA) prior to use of the modified assemblies in a core cycle after Cycle 4.
This type of approach would eliminate the need for a redundant LCA and would eliminate needless paper work and delays, but it would not eliminate the submittal of the appropriate data to the NRC. We would be happy to discuss this matter further with members of your staff.
8103 26 oS9a
Mr. Robert A. Clark March 20, 1981 Page two However, prompt approval of LCA 70 for Cycle 4 is still required in order to avoid impacting the spring refueling outage at Trojan.
Sincerely, Attachment c: Lynn Frank, Director State of Oregon Department of Energy i
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3L WESTINGHOUSE PROPRIETARY CLASS 3 TABLE 2 TROJAN CYCLE 4
SUMMARY
DESIGN 1 LOADING PATTERN
- 150 MWD /MTU Burnup Cycle 4 Nominal Cycle 3 Burnup Core Condition EOC3=9600 MWD /MTU HFP CB = 1012 ppm FAH @ Location **
ARO 1.361 (3,1)
D In 1.392 (2,7)
D+C In 1.615 (4,7)
HZP CB = 1150 ppm F4H @ Location l
ARO 1.408 (4,2)
D In 1.426 (7,2)
D+C In 1.779 (4,7)
- BOL ARO HFP: CB =-1319 ppa & FAH = 1.350 @ (4,5)
- Locations are designated in quartercore notation GAZ/LSP/4 caw!B6
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