Letter Sequence Other |
|---|
|
Results
Other: A00938, Forwards Haddam Neck Plant Reactor Operator Qualification & Requalification Programs & Millstone,Units 1 & 2,reactor Operator Qualification Program, A01024, Forwards Info Re Five Addl TMI-2 Related Requirements Applying to Operating Reactors Per 800507 Request.Integrated Assessment of Collective Impact of All Requirements Should Be Conducted, A01551, Provides Info & Appropriate Refs in Response to Generic Ltr 81-10 Re Emergency Response Facilities, A02477, Forwards Response to Generic Ltr 82-10 Requesting Info Re Implementation Dates for Selected TMI Action Plan Items in NUREG-0737, A05610, Responds to Generic Ltr 86-04 Re Policy Statement on Engineering Expertise on Shift.Comparison of INPO Shift Technical Advisor Guidelines W/Established Bachelors Degree Programs in Engineering Encl, B12611, Comments on NRC Evaluation of Util Program for Training & Qualifying Individuals for dual-role,senior Reactor Operator/Shift Technical Advisor Positions W/Specific Emphasis on Whether Program Meets NRC Requirements, ML19340E921, ML19344E073, ML19344E075, ML19344E083, ML19345E125, ML20004D414, ML20010A692, ML20028E427, ML20031F894, ML20041B060, ML20041B062, ML20041B064, ML20041B066, ML20041B069, ML20041B070, ML20050C507, ML20054E184, ML20077B854, ML20149L522, ML20214K567, ML20237D811, ML20244C864
|
MONTHYEARIR 05000245/19790211979-10-30030 October 1979 IE Insp Repts 50-245/79-21 & 50-336/79-22 on 790804-0901.No Noncompliance Noted.Major Areas Inspected:Plant Tours, Physical Security,Exam of Feedwater Piping Per IE Bulletin 79-13,fire Protection & Surveillance Testing Project stage: Request ML19296B2941980-02-0808 February 1980 Submits Response to NRC 800201 Request for Addl Info Re Proposed long-term Emergency Operations Ctr,Required by NUREG-0578.Ctr Would Be Located 1.5 Miles from Plant. Preliminary Maps & Drawings Encl Project stage: Request ML19296B0471980-02-0808 February 1980 RCS Asymmetric Loads Evaluation Program;Interim Rept Project stage: Request ML19309B8431980-03-28028 March 1980 Submits Info Re Direct Indication of PORV & Safety Valve Positions.Recent Discussions W/Vendor Revealed Difficulty w/800401 Completion Date.Revised Date of Completion Is 810401 Project stage: Request ML19323B1601980-04-16016 April 1980 Forwards NRC Position Re Emergency Response Facilities. Primary Technical Support Ctr That Does Not Meet Habitability Requirements Acceptable,Provided That Secondary Ctr,Meeting Requirements,Available Project stage: Meeting A01024, Forwards Info Re Five Addl TMI-2 Related Requirements Applying to Operating Reactors Per 800507 Request.Integrated Assessment of Collective Impact of All Requirements Should Be Conducted1980-06-10010 June 1980 Forwards Info Re Five Addl TMI-2 Related Requirements Applying to Operating Reactors Per 800507 Request.Integrated Assessment of Collective Impact of All Requirements Should Be Conducted Project stage: Other ML20041B0661980-07-22022 July 1980 Instructor Requalification Project stage: Other ML20041B0621980-07-23023 July 1980 To Licensed Senior Reactor Operator Replacement Training Project stage: Other ML20041B0641980-07-23023 July 1980 To CT Yankee Reactor Operator Requalification Project stage: Other ML20041B0601980-07-23023 July 1980 To Licensed Reactor Operator Replacement Training Project stage: Other ML19344E0751980-07-31031 July 1980 Operator Requalification Program Project stage: Other A00938, Forwards Haddam Neck Plant Reactor Operator Qualification & Requalification Programs & Millstone,Units 1 & 2,reactor Operator Qualification Program1980-08-15015 August 1980 Forwards Haddam Neck Plant Reactor Operator Qualification & Requalification Programs & Millstone,Units 1 & 2,reactor Operator Qualification Program Project stage: Other ML20041B0691980-08-31031 August 1980 Operator License Program Project stage: Other ML20041B0701980-08-31031 August 1980 Requalification Program for Licensed Operators Project stage: Other ML19344E0831980-08-31031 August 1980 Qualification of Reactor Operators Project stage: Other ML19344E0731980-08-31031 August 1980 Qualification of Reactor Operators Project stage: Other ML19345E1251980-12-15015 December 1980 Forwards Response to NUREG-0737 Re Implementation Status of TMI-related Requirements Project stage: Other ML19340E9211980-12-31031 December 1980 Forwards Rept on post-TMI Requirements in Response to NUREG-0737 & NRC Project stage: Other B10200, Comments on Draft NUREG-0659 Re Human Engineering Guide to Control Room Evaluation.Consideration Should Be Given to Lengthening 1-yr Review Process Due to Increased Workload on Operators Requirements Such as TMI Action Plan Items1981-04-16016 April 1981 Comments on Draft NUREG-0659 Re Human Engineering Guide to Control Room Evaluation.Consideration Should Be Given to Lengthening 1-yr Review Process Due to Increased Workload on Operators Requirements Such as TMI Action Plan Items Project stage: Draft Other ML20004D4141981-05-22022 May 1981 Forwards Response to IE Bulletin 81-03, Flow Blockage of Cooling Water to Safety Sys Components by Corbicula Sp (Asiatic Clam) & Mytilus Sp (Mussel). Mytilus Sp Is Salt Water Organism & Cannot Inhabit Freshwater Mo River Project stage: Other A01551, Provides Info & Appropriate Refs in Response to Generic Ltr 81-10 Re Emergency Response Facilities1981-06-0303 June 1981 Provides Info & Appropriate Refs in Response to Generic Ltr 81-10 Re Emergency Response Facilities Project stage: Other ML20010A6921981-08-0606 August 1981 Advises of Intended Licensing Exam Requests for Facilities for 1982.Advance Notice for NRC Support Considered Necessary Due to Limited Simulator Availability to Meet New Regulations Project stage: Other A01845, Forwards Info Re NRC Orders Confirming Licensee Commitments on post-TMI Related Issues.Issues Have Been Addressed.If NRC Does Not Allow Util to Reserve Request for Hearing,Ltr Should Be Treated as Hearing Request1981-08-10010 August 1981 Forwards Info Re NRC Orders Confirming Licensee Commitments on post-TMI Related Issues.Issues Have Been Addressed.If NRC Does Not Allow Util to Reserve Request for Hearing,Ltr Should Be Treated as Hearing Request Project stage: Request ML20031F8941981-10-14014 October 1981 Responds to NUREG-0737 Item II.K.3.5,automatic Reactor Coolant Pump Trip.Requirement for Installation of Automatic Trip Sys Is Neither Warranted Nor Desirable Project stage: Other ML20050C5071982-03-24024 March 1982 Ack Commitment in to Meet Reporting Requirement Provided in NRC Re Relief & Safety Valve Failures.Info Missing from 1981 Annual Rept.Requests That Rept Be Updated W/Errata Sheet to Correct Discrepancy Project stage: Other ML20054E1841982-04-16016 April 1982 Forwards Responses to Generic Ltr 82-05 Re post-TMI Requirements Implementation.Continued Safe Operation Assured W/Existing Implementation Status Project stage: Other A02376, Responds to 820318 Request for Addl Info Required to Complete Review of NUREG-0737,Item I.A.1.2 Re Upgraded Senior Reactor Operator & Reactor Operator Training & Item II.B.4 Re Training for Mitigating Core Damage1982-05-10010 May 1982 Responds to 820318 Request for Addl Info Required to Complete Review of NUREG-0737,Item I.A.1.2 Re Upgraded Senior Reactor Operator & Reactor Operator Training & Item II.B.4 Re Training for Mitigating Core Damage Project stage: Request A02477, Forwards Response to Generic Ltr 82-10 Requesting Info Re Implementation Dates for Selected TMI Action Plan Items in NUREG-07371982-06-0404 June 1982 Forwards Response to Generic Ltr 82-10 Requesting Info Re Implementation Dates for Selected TMI Action Plan Items in NUREG-0737 Project stage: Other ML20028E4271982-08-17017 August 1982 Improvements in Training & Requalification Programs as Required by TMI Action Items,I.A.2.1 & II.B.4, Technical Evaluation Rept Project stage: Other ML20214K5671983-04-19019 April 1983 Advises That Reporting Period Began on 800401 for All PWR Licensees Committed to Providing NRC Prompt Notification of Porv/Sv Failures & Periodic Repts.Project Managers Should Have Info Available in Records Project stage: Other ML20077B8541983-07-20020 July 1983 Operating Reactor PORV Repts (F-37) TMI Action Plan Requirements:Generic Rept - B&W Designed Units, Technical Evaluation Rept Project stage: Other ML20244C8641984-02-16016 February 1984 Amends 95 & 92 to Licenses DPR-21 & DPR-65,respectively, Changing Tech Specs to Comply W/Final Rule on Licensed Operator Staffing Project stage: Other A05610, Responds to Generic Ltr 86-04 Re Policy Statement on Engineering Expertise on Shift.Comparison of INPO Shift Technical Advisor Guidelines W/Established Bachelors Degree Programs in Engineering Encl1986-06-13013 June 1986 Responds to Generic Ltr 86-04 Re Policy Statement on Engineering Expertise on Shift.Comparison of INPO Shift Technical Advisor Guidelines W/Established Bachelors Degree Programs in Engineering Encl Project stage: Other B12611, Comments on NRC Evaluation of Util Program for Training & Qualifying Individuals for dual-role,senior Reactor Operator/Shift Technical Advisor Positions W/Specific Emphasis on Whether Program Meets NRC Requirements1987-08-0707 August 1987 Comments on NRC Evaluation of Util Program for Training & Qualifying Individuals for dual-role,senior Reactor Operator/Shift Technical Advisor Positions W/Specific Emphasis on Whether Program Meets NRC Requirements Project stage: Other ML20237D8111987-12-18018 December 1987 Informs That Util May Proceed Immediately W/Implementation of Organizational Structures Proposed in 871118 & 19 Ltrs Project stage: Other ML20149L4451988-02-17017 February 1988 Application for Amends to Licenses DPR-61,DPR-21 & DPR-65, Changing Table 6.2-1 of Tech Specs to Recognize Acceptability of Qualified Individuals in Dual Role of Senior Reactor Operator (SRO) & Shift Technical Advisor Project stage: Request ML20149L5221988-02-17017 February 1988 Proposed Tech Specs,Amending Table 6.2-1 Re Dual Role Senior Reactor Operator (SRO) & Shift Technical Advisor (STA) Project stage: Other 1981-05-22
[Table View] |
Text
.
o I
.g
'h Omaha Public Power District 1623 MARNEY 1 OMAMA, NESRASMA 66102 s TELEPHONE 536.AOOO AREA CODE A02 May 22, 1981 Mr. K. V. Seyfrit, Director U. S. Nuclear Regulatory Commission Office of Inspection and Enforcement Region IV 611 Ryan Plaza Drive, Suite 1000 Arlington. Texas 76011
Reference:
Docket No. 50-285
Dear Mr. Seyfrit:
Omaha Public Power District has evaluated the concerns detailed in IE Bulletin No. 81-03, dated April 9,1981, regarding flow blockage of cooling water to safety system ccmponents by asiatic clams and mussels. The result of the District's evaluation is attached in response to the bulletin.
Sin erely, W. C. Jones k Division Manager Production Operations WCJ/KJM/TLP/1p Attachment
'C, pc: Office of Inspection and Enforcement, Washington, D. C.
I LeBoeuf, Lamb, Leiby, and MacRae
, Gh! '
\\
e ;r
. 9.
,s q
s k '7 i
O
's 9
J C 0 3 1531
~~.
1[
/,i x:.'
/
8106090 %
In the Matter
)
)
Docket No. 50-285 OMAHA PUBLIC POWER DISTRICT
)
AFFIDAVIT
...being duly sworn, hereby deposes and says that he is the Section Manager-0perations of Omaha Public Power District; that he is duly authorized to sign and file with the Nuclear Regulatory Commission the attached response to IE Bulletin No. 81-03; that he is familiar with the content thereof; and that the matters set forth therein are true and correct to the best of his knowledge, information, and belief.
R. L. Andrews Section Manager Production Operations STATE OF NEBRASKA
)
) ss COUNTY OF DOUGLAS
)
Subscribed and sworn to before me, a Notary Public in and for the State of Nebraska, on this
_ day of May, 1981.
u i
Nntary Public I
l LT.ausson we cama. em w as, sas My Commission expires
, 19
OMAHA PUBLIC POWER DISTRICT Fort Calhoun Station Unit No. 1 Response to IE Bulletin No. 81-03 ACTIONS TO BE TAKEN BY LICENSE 1 Item No. 1 Determine whether Corbicula Sp. or Mytilus Sp. is present in the vicinity of the station (local environment) in either the source or receiving water body.
If the results of current field monitoring programs provide reasonable evidence that neither of these species is presert in the local environment, no further action is necessary except for Items 4 and 5 ln this section for holders of operating licenses.
Rescanse Fort Calhoun Station has been operating for the past seven and one-half years. The extensive environmental monitoring program carried out during this period did not show presence of any asiatic clam shalls. Also, regular inspection of the components that use river water has been conducted during each of the past five refueling outages.
These inspections did not show the presence of any clam shells in the condenser or the raw water heat exchangers.
A literature and field investigation effort was conducted to determine if the Corbicula Sp. or the Mytilus Sp. is present in the vicinity of the Fort Calhoun Station.
The Mytilus Sp.
is a salt water organism and, therefore, cannot innaoit the freshwater Missouri River. The results of a literature research effort into the presence or absence of the Corbicula Sp. near the Fort Calhoun Station indicates that there nave been none reported. This information was verified by field sampling efforts conducted in response to this bulletin upstream and downstream of the Fort Calhoun Station.
Items No. 2 and 3 Not Applicable.
o
Item No. 4 Describe methods either in use or planned (including imple-mentation date) for preventing and detecting future flow blockage or degradation due to clams or mussels or shell debris.
Include the following information in this description:
a.
Evaluation of the potential for intrusion of the organisms intu these systems due to low water level and high velocities in the intake structure expected during worst case conditions.
b.
Evaluation of effectiveness of p'revention and detection methods used in the past or present or planned for future use.
Response
It is believed that continued surveillance and inspection of the com-ponents that use river water during the refueling outage will be adequate for detecting asiatic clams at the Fort Caihoun Station.
The District also has additional non-nuclear units along the Missouri River. The condenser of these units are also inspected at regular intervals.
Fouling of the condenser at these facilities, due to Coroicula Sp. has not been detected in the past.
Should asiatic clams be detected at Fort Calhoun or any of the other units operated by the District, appropriate measures for detecting flow
- blockage or degradation will be implernented.
The worst case of low -Iver level occurs during the winter months.
During this period, river water temperature at the Fort Calhoun Station is < 45'F, and the circulating water discharge temperatuare is < 55'F. At these temperatures, the Corbicula Sp. will not spawn.
Therefore, it is highly unlikely that the asiatic clams will pose any problems for the cooling system at the Fort Calhoun Station.
Item No. 5 Describe the actions taken in Items 1 through 3 above and include the following informa!. ion:
l a.
Applicable portions of the environmental monitoring l
program including last sample date and results.
b.
Components and systems affected.
c.
Extent of fouling if any existed.
d.
Hcw and when fouling was discovered.
e.
Corrective and preventive actions.
2
Response
An environmental sampling program was conducted after receiving IE Bulletin 81-03 to determine the presence of asiatic clars.s at Fort Calhoun Station. This program consis:od of taking grab samples-of the Missouri River upstream and downstream of the Fort Calhoun Station. The results of this program showed absence of asiatic clams in the vicinity of the Fort Calhoun Station.
At present, ngr.c of the components and systems are affected and no fouling G1 the system exists.
e t
3
.. _.