NRC Generic Letter 1981-24: Difference between revisions

From kanterella
Jump to navigation Jump to search
(Created page by program invented by StriderTol)
(Created page by program invented by StriderTol)
 
(2 intermediate revisions by the same user not shown)
Line 3: Line 3:
| issue date = 06/15/1981
| issue date = 06/15/1981
| title = NRC Generic Letter 1981-024: Multi-Plant Issue B-56, Control Rods Fail to Fully Insert
| title = NRC Generic Letter 1981-024: Multi-Plant Issue B-56, Control Rods Fail to Fully Insert
| author name = Eisenhut D G
| author name = Eisenhut D
| author affiliation = NRC/NRR
| author affiliation = NRC/NRR
| addressee name =  
| addressee name =  
Line 14: Line 14:
| page count = 2
| page count = 2
}}
}}
{{#Wiki_filter:tA REG(,, kUNITED STATES-NUCLEAR REGULATORY COMMISSION< &#xa3;i WASHINGTON, D. C. 20555June 15, 1981LICENSEES OF ALL GE BWR FACILITIES (EXCEPT HUMBOLDT BAY)SUBJECT: MULTI-PLANT ISSUE B-56, CONTROL RODS FAIL TO FULLY INSERT(Generic Letter No. 81-24)Gentlemen:By letters dated August 29, 1978 and January 10, 1980, you were requestedto provide information on your experience with one or more control rodsstopping short of the fully inserted position on scram and then settlingback to notch position "02" or six inches short of full insertion.We have evaluated your responses, along with those provided by other BWRlicensees, and have concluded that the problem of control rods insertingonly to notch position "102" on scram is attributable to leakage past wornI stop and drive piston seals. We have determined that this problem is amaintenance problem, and is readily correctable by control rod drive over-haul at a subsequent outage. We have further concluded that TechnicalSpecification requirements regarding control rod operability and shutdownmargin provide adequate assurance of the capability to place and maintainthe plant in a safe shutdown condition. Consequently, the failure to fullyinsert events, as described herein, do not represent a significant safetyissue.The enclosed safety evaluation provides the basis for this determination.Sincerely,/ Darrell G. Eisenhut, rectorDivision of LicensingOffice of Nuclear Reactor RegulationEnclosure:Safety Evaluationcc w/encl:Service List,/: i10310295 610615PDR ADOCK 05000010P PDR  
{{#Wiki_filter:tA REG(,,                     k UNITED STATES
ywBOILING WATER REACTOR LICENSEESDocket No. 50-293Pilgrim Unit 1Docket No. 50-245Millstone Unit 1Docket No. 50-263MonticelloDocket No. 50-325Brunswick Unit 1/Docket No. 50-324Brunswick Unit 2-.9 04 9Docket No. 50-10 .Dresden 1Docket No. 50-277Peach Bottom Unit 2Docket No. 50-237Dresden 2Docket No. 50-278Peach Bottom Unit 3Docket No. 50-249Dresden 3Docket No. 50-333FitzPatrickDocket No. 50-254Quad-Cities Unit 1Docket No. 50-259Browns Ferry Unit 1Docket No. 50-265Quad-Cities Unit 2Docket No. 50-260Browns Ferry Unit 2Docket No. 50-155Big Rock PointDocket No. 50-296Browns Ferry Unit 3Docket No. 50-409Lacrosse Swcj.Docket No. 50-271Vermont YankeeDocket No. 50-321Edwin I. Hatch Unit 1IDocket No. 50-366Edwin I. Hatch Unit 2Docket No. 50-331Duane ArnoldDocket No. 50-219Oyster CreekDocket No. 50-220Nine Mile Point Unit 1Docket No. 50-298Cooper Station  
    -                               NUCLEAR REGULATORY COMMISSION
}}
                  < &#xa3;i                     WASHINGTON, D. C. 20555 June 15, 1981 LICENSEES OF ALL GE BWR FACILITIES (EXCEPT HUMBOLDT BAY)
            SUBJECT:     MULTI-PLANT ISSUE B-56, CONTROL RODS FAIL TO FULLY INSERT
                          (Generic Letter No. 81-24)
            Gentlemen:
            By letters dated August 29, 1978 and January 10, 1980, you were requested to provide information on your experience with one or more control rods stopping short of the fully inserted position on scram and then settling back to notch position "02" or six inches short of full insertion.
 
We have evaluated your responses, along with those provided by other BWR
            licensees, and have concluded that the problem of control rods inserting only to notch position "102" on scram is attributable to leakage past worn I            stop and drive piston seals. We have determined that this problem is a maintenance problem, and is readily correctable by control rod drive over- haul at a subsequent outage. We have further concluded that Technical Specification requirements regarding control rod operability and shutdown margin provide adequate assurance of the capability to place and maintain the plant in a safe shutdown condition. Consequently, the failure to fully insert events, as described herein, do not represent a significant safety issue.
 
The enclosed safety evaluation provides the basis for this determination.
 
Sincerely,
                                            /   Darrell G. Eisenhut,   rector Division of Licensing Office of Nuclear Reactor Regulation Enclosure:
            Safety Evaluation cc w/encl:
            Service List
                        ,/
  : i10310295 610615 PDR ADOCK 05000010
  P                    PDR
 
yw BOILING WATER REACTOR LICENSEES
Docket No. 50-293                      Docket No. 50-245 Pilgrim Unit 1                        Millstone Unit 1 Docket No. 50-325                      Docket No. 50-263 Brunswick Unit 1       /             Monticello Docket No. 50-324                          -     .9 04 9 Brunswick Unit 2 Docket No. 50-10 .                     Docket No. 50-277 Dresden 1                              Peach Bottom Unit 2 Docket No. 50-237                      Docket No. 50-278 Dresden 2                              Peach Bottom Unit 3 Docket No. 50-249                      Docket No. 50-333 Dresden 3                              FitzPatrick Docket No. 50-254                      Docket No. 50-259 Quad-Cities Unit 1                    Browns Ferry Unit 1 Docket No. 50-265                      Docket No. 50-260
Quad-Cities Unit 2                    Browns Ferry Unit 2 Docket No. 50-155                      Docket No. 50-296 Big Rock Point                        Browns Ferry Unit 3 Docket No. 50-409                      Docket No. 50-271 Lacrosse Swcj.                        Vermont Yankee Docket No. 50-321 Edwin I. Hatch Unit 1                          I
Docket No. 50-366 Edwin I. Hatch Unit 2 Docket No. 50-331 Duane Arnold Docket No. 50-219 Oyster Creek Docket No. 50-220
Nine Mile Point Unit 1 Docket No. 50-298 Cooper Station}}


{{GL-Nav}}
{{GL-Nav}}

Latest revision as of 02:10, 24 November 2019

NRC Generic Letter 1981-024: Multi-Plant Issue B-56, Control Rods Fail to Fully Insert
ML031210452
Person / Time
Issue date: 06/15/1981
From: Eisenhut D
Office of Nuclear Reactor Regulation
To:
References
GL-81-024, NUDOCS 8107310298
Download: ML031210452 (2)
v • d • e


tA REG(,, k UNITED STATES

- NUCLEAR REGULATORY COMMISSION

< £i WASHINGTON, D. C. 20555 June 15, 1981 LICENSEES OF ALL GE BWR FACILITIES (EXCEPT HUMBOLDT BAY)

SUBJECT: MULTI-PLANT ISSUE B-56, CONTROL RODS FAIL TO FULLY INSERT

(Generic Letter No. 81-24)

Gentlemen:

By letters dated August 29, 1978 and January 10, 1980, you were requested to provide information on your experience with one or more control rods stopping short of the fully inserted position on scram and then settling back to notch position "02" or six inches short of full insertion.

We have evaluated your responses, along with those provided by other BWR

licensees, and have concluded that the problem of control rods inserting only to notch position "102" on scram is attributable to leakage past worn I stop and drive piston seals. We have determined that this problem is a maintenance problem, and is readily correctable by control rod drive over- haul at a subsequent outage. We have further concluded that Technical Specification requirements regarding control rod operability and shutdown margin provide adequate assurance of the capability to place and maintain the plant in a safe shutdown condition. Consequently, the failure to fully insert events, as described herein, do not represent a significant safety issue.

The enclosed safety evaluation provides the basis for this determination.

Sincerely,

/ Darrell G. Eisenhut, rector Division of Licensing Office of Nuclear Reactor Regulation Enclosure:

Safety Evaluation cc w/encl:

Service List

,/

i10310295 610615 PDR ADOCK 05000010

P PDR

yw BOILING WATER REACTOR LICENSEES

Docket No. 50-293 Docket No. 50-245 Pilgrim Unit 1 Millstone Unit 1 Docket No. 50-325 Docket No. 50-263 Brunswick Unit 1 / Monticello Docket No. 50-324 - .9 04 9 Brunswick Unit 2 Docket No. 50-10 . Docket No. 50-277 Dresden 1 Peach Bottom Unit 2 Docket No. 50-237 Docket No. 50-278 Dresden 2 Peach Bottom Unit 3 Docket No. 50-249 Docket No. 50-333 Dresden 3 FitzPatrick Docket No. 50-254 Docket No. 50-259 Quad-Cities Unit 1 Browns Ferry Unit 1 Docket No. 50-265 Docket No. 50-260

Quad-Cities Unit 2 Browns Ferry Unit 2 Docket No. 50-155 Docket No. 50-296 Big Rock Point Browns Ferry Unit 3 Docket No. 50-409 Docket No. 50-271 Lacrosse Swcj. Vermont Yankee Docket No. 50-321 Edwin I. Hatch Unit 1 I

Docket No. 50-366 Edwin I. Hatch Unit 2 Docket No. 50-331 Duane Arnold Docket No. 50-219 Oyster Creek Docket No. 50-220

Nine Mile Point Unit 1 Docket No. 50-298 Cooper Station

Template:GL-Nav

Retrieved from "https://kanterella.com/w/index.php?title=NRC_Generic_Letter_1981-24&oldid=2200171"