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=Text=
=Text=
{{#Wiki_filter:VIRGINIA EI.ECTRIC AND Pow .. CO31PANY
{{#Wiki_filter:VIRGINIA EI.ECTRIC AND Pow.. CO31PANY Ric113t OND.VI Ro r x1 A C3GC1 October 20, 1976 Mr. Norman C. Moseley, Director Serial No. 292 Office of Inspection and Enforcement P0&M/ALH:clw U.S. Nuclear Regulatory Cocsission Region II - Suite 818 Docket Fo. 50-280 230 Peachtree Street, Northwest License No. DPR-32 Atlanta, Georgia 30303
    . .                              Ric113t OND .VI Ro r x1 A C3GC1 October 20, 1976 Mr. Norman C. Moseley, Director                               Serial No. 292 Office of Inspection and Enforcement                           P0&M/ALH:clw U.S. Nuclear Regulatory Cocsission Region II - Suite 818                                         Docket Fo. 50-280 230 Peachtree Street, Northwest                               License No. DPR-32 Atlanta, Georgia     30303


==Dear Mr. Moseley:==
==Dear Mr. Moseley:==
Pursuant to Surry Power Station Technical Specification 6.6.B.2, the Virginia Electric and Power Company hereby submits a copy of Licensee Event Report USRE-SI-76-13.
Pursuant to Surry Power Station Technical Specification 6.6.B.2, the Virginia Electric and Power Company hereby submits a copy of Licensee Event Report USRE-SI-76-13.
The substance of this report has been reviewed by the Station Nuclear Safety and Operating Co=:nittee and will be placed on the agenda for the next meeting of the System Nuclear Safety and Operating Co=mittee.
The substance of this report has been reviewed by the Station Nuclear Safety and Operating Co=:nittee and will be placed on the agenda for the next meeting of the System Nuclear Safety and Operating Co=mittee.
Very truly yours, C. M. Stallings                         {
Very truly yours, C. M. Stallings
Vice President-Power upply                     (
{
and Production Operations Enclosure cc:   Mr. Robert W. Reid, Chief Operating Reactors Branch 4 (40 copies USRE-S1-76-13) l l
Vice President-Power upply
(
and Production Operations Enclosure cc:
Mr. Robert W. Reid, Chief Operating Reactors Branch 4 (40 copies USRE-S1-76-13) l l
l
l
    /6 8212290075 821130                                                           7       .
/6 8212290075 821130 7
                                                                                            " G. ("
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PDR FOIA SCHLIsss2-534 PDR l
PDR FOIA SCHLIsss2-534 PDR l


                                                        --....------...t                   i     e   t   i   t   f-1                        8                        (PLEASE PRINT ALL LEQUIRED INF%3
--....------...t i
                                                                                                                                              ,s
e t
    ~                                                    N ME                                           LCENSE NUMBER Q j vl Al SlP lS l t l                                               l0l0l~l0l0l0l0l0l-l0l0l 7 89                                                           14   15 25 l4 26 l1 l1l1l0l l0l3l                ,1 30   31   32 CATEGORY                             pf N E                       00CxET NUMBER 01 CGN'T l p l ol 7 8                  57                58 M59          60      61 EVENT DATE l 0l 5l 0l-l 0l 2l 8l 0 l l 0l 9l Il 6l 7l 6l [ t l 0REPORT                l 1l DAK 5ll 68     69 -                   74   75 EVENT DESCRIPTION o2 7 ,8 9    lDuring normal operations, it was discovered that normal boric acid cakeup to the vs 03 7 89 l control tank could not be accomplished due to an apparent plugging of CVCS line 1"c
i t
                @ ]56-152. In order to clear the line, recirculation between the boric acid tanks anj 7 8
f-(PLEASE PRINT ALL LEQUIRED INF%3 1
              @9l boron injection tank was secured for five (5) minutes to permit installation of a 7 89 RE l blank flange in the line.
8
7 89                                                                                Since Technical Specification 3.2.C.6 requires con- (cos coy                       $oE                       COMPONENT CODE
,s N ME LCENSE NUMBER Q j vl Al SlP lS l t l l0l0l~l0l0l0l0l0l-l0l0l l4 l1 l1l1l0l l0l3l
              @ lP l Cl lF l                                               lX lX lX l Xl Xl Xl                 ]43 VoLAToM 7 89 10                                   11             12                           17 lz l9 l9 l9 l 44             47 W48 CAUSE DESCRIPTION 0
~
7 89 l         Boric acid is transferred through line 1"-CH-56-152 on a regular basis for volume G 09      ltroltankmake-up. This routine usage, coupled with the fact that no malfunctionia 7 89
7 89 14 15 25 26 30 31 32
      ' 10 l heat tracing was found either in the pipe in question or any upctream pipe (con't) 7 89 FACUTY STATUS                                   % POWEA                                       METHOD OF
,1 CATEGORY pf N E 00CxET NUMBER 01 CGN'T l p l ol M l 0l 5l 0l-l 0l 2l 8l 0 l l 0l 9l Il 6l 7l 6l
* OTHER STATUS I
[ t l 0 l 1l 5ll EVENT DATE REPORT DAK 7 8 57 58 59 60 61 68 69 -
7 8 1
74 75 EVENT DESCRIPTION lDuring normal operations, it was discovered that normal boric acid cakeup to the vs o2 7,8 9 l control tank could not be accomplished due to an apparent plugging of CVCS line 1"c 03 7 89
9 W                           10 l_1_ l 0 l 0 l             l N/A                   l OtSCOVERY
@ ]56-152.
                                                                                                                        @        l'   N/A OtSCoVERY CESCRIPTON 12 13                         44   45     48 ACTMTV                       CCATENT RELEASED AMOUNT OF ACTMTY 12                                            l,z,jRELEASE l N/A 7 8                  9 l_z_,l                   OF                                                        l       l N/A LOCATCN OF RELEASE 10           11 44     45 PERSONNEL EXPOSURES NUMBER                         TYPE             DESCRIPTION Q l0l0l0l Wl 7 89                                           11       12           13 N/A PERSONNEL INJURIES NUMBER                           CESCRtPTON
In order to clear the line, recirculation between the boric acid tanks anj 7 8
        @ l0l0l0l 7 89 l             N/A 11 12 OFFSITE CONSEQUENCES DE l                   N/A                                                                                                                     -
@9l boron injection tank was secured for five (5) minutes to permit installation of a 7 89 RE l blank flange in the line.
7 89 LOSS OR DAMAGE TO FAC1UTY                                                                                                     '
Since Technical Specification 3.2.C.6 requires con- (cos 7 89 coy
TYPE
$oE COMPONENT CODE
      @W 7 89                        10 lDESCPSTON       N/A PUBUCITY Ql 7 89 N/A ADQtTIONAL FACTORS 18          l Since the capabilities of the safety injection system were not impaired by this eveg 7 89 Q l the health and safety of the general public were not affected.
@ lP l Cl lF l lX lX lX l Xl Xl Xl
7 89 NAME:                           Tyndall L. Baucon PHONE, (804) 337-3184 p                                   %
]
lz l9 l9 l9 l W
VoLAToM 7 89 10 11 12 17 43 44 47 48 CAUSE DESCRIPTION l Boric acid is transferred through line 1"-CH-56-152 on a regular basis for volume G 0
7 89 ltroltankmake-up.
This routine usage, coupled with the fact that no malfunctionia 09 7 89
' 10 l heat tracing was found either in the pipe in question or any upctream pipe (con't) 7 89 FACUTY METHOD OF STATUS
% POWEA OTHER STATUS OtSCOVERY I
W l_1_ l 0 l 0 l l
N/A l @
l' N/A OtSCoVERY CESCRIPTON 1
7 8 9
10 12 13 44 45 48 ACTMTV CCATENT RELEASED OF RELEASE l N/A l
l N/A AMOUNT OF ACTMTY 12 l_z_,l l,z,j LOCATCN OF RELEASE 7 8 9
10 11 44 45 PERSONNEL EXPOSURES NUMBER TYPE DESCRIPTION Q l0l0l0l Wl N/A 7 89 11 12 13 PERSONNEL INJURIES NUMBER CESCRtPTON
@ l0l0l0l l
N/A 7 89 11 12 OFFSITE CONSEQUENCES DE l N/A 7 89 LOSS OR DAMAGE TO FAC1UTY TYPE
@ W lDESCPSTON N/A 7 89 10 PUBUCITY Ql N/A 7 89 ADQtTIONAL FACTORS l Since the capabilities of the safety injection system were not 18 impaired by this eveg 7 89 Q l the health and safety of the general public were not affected.
7 89 NAME:
Tyndall L. Baucon PHONE, (804) 337-3184 p


    .*    EVENT DESCRI~ ' ION (c::n't) tinuous recirculation, an immediate reactor rampdown was initiated until boron injection tank recirculation was returned to normal.       Once the line was cleared of the obstruction, boron recirculation was again secured while the blank flangG was removed. A reactor rampdown was performed during this operation which lastG for approximately three (3) minutes.       (USRE-S1-76-13)
EVENT DESCRI~ ' ION (c::n't) tinuous recirculation, an immediate reactor rampdown was initiated until boron injection tank recirculation was returned to normal.
CAUSE DESCRIPTION (con't) leaves the cause of the obstruction as an unknown factor. The line was inspectG for potential " cold" spots which could cause isolated solidification of boric acid, but none were found in the area of the obstruction. The line will be in-spected for indications of solidification during the next refueling shutdown.
Once the line was cleared of the obstruction, boron recirculation was again secured while the blank flangG was removed. A reactor rampdown was performed during this operation which lastG for approximately three (3) minutes.
  ,            During the period of obstruction, the capability to add boric acid to the reactor coolant system was maintained.       In addition, the boron injection tank was capable of performing its intended function.
(USRE-S1-76-13)
l l
CAUSE DESCRIPTION (con't) leaves the cause of the obstruction as an unknown factor. The line was inspectG for potential " cold" spots which could cause isolated solidification of boric acid, but none were found in the area of the obstruction.
l
The line will be in-spected for indications of solidification during the next refueling shutdown.
[                     - - -                    -                          m,             cs a
During the period of obstruction, the capability to add boric acid to the reactor coolant system was maintained.
In addition, the boron injection tank was capable of performing its intended function.
l l l
[
m, cs a


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Distribution Code PDR COORDINATOR ONLY Report sent to HQs and hold copies reproduced                                   Date                     l 1
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Initials j               ...._..._____........._..____....____....__................____.......__..____
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: 1. Licensee Response to Non-Enforcement Report
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: 2. Licensee Response to Enforcement Report
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: c. Document Date /d M O M                 d. Date Received /d 'M-7d
Licensee Response to Non-Enforcement Report 2.
: e. Section Chief                       f. Principal Inspector                 J 9
Licensee Response to Enforcement Report 3.
: g. Document transferred to                                                         Branch l                                   Date                       Initials                                           j
Licensee Response to IE Bulletins 4
: h. Licensee Response to Enforcetsnt Report Only l
General Licensee Correspondence Licensee Event Reports Licensee / Facility //((M IMa
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Should the attached and related correspondence be placed in the PDR7 YES   Y~       NO                 Initials I
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Principal Inspector J
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Document transferred to Branch l
Date Initials j
h.
Licensee Response to Enforcetsnt Report Only l
Acceptable Not-Acceptable Initials 3
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Initials kib NorE: If Yes, mark necessary documents to delete 2.790 Information and return with this form along with acknowledgement letter F
to the PDR Coordinator.
Should the attached and related correspondence be placed in the PDR7 YES Y~
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I PDR COPRDINATOR ONLY Incoming Licensee Correspondence and related documents sent to HQs i
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1 l
1 Vircinia Electric and Pover Co.mpany Eochet No.
Vircinia Electric and Pover Co.mpany Eochet No. 50-280 Surry Unit 1 License No. DPR-32 REPORTABLE OCCURRENCE REPORT 30:
50-280 Surry Unit 1 License No.
DPR-32 REPORTABLE OCCURRENCE REPORT 30:
Ro-280/76-07 DISTRIBUTION:
Ro-280/76-07 DISTRIBUTION:
Don Lanham, ADM cc With Fnclosures
Don Lanham, ADM cc With Fnclosures Region II Docket Files 280 Rettion II Inspector with enclosures i
    !                Region II Docket Files 280 Rettion II Inspector with enclosures i
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                                                                                                                                                    .i.
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Farue AIC.31e (Erv. 9 53) AsCM 0240
Farue AIC.31e (Erv. 9 53) AsCM 0240
* u. en sovsamu sar rainvine oreics, sete.ese.see N     m
* u. en sovsamu sar rainvine oreics, sete.ese.see N
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l                                                                                                       .-
l Form TE-1/76 (6/76)
Form TE-1/76     (6/76) W Inspection / Investigation neports Only Distribution Code PDR COORDINATOR O';LY                                             .
W Inspection / Investigation neports Only Distribution Code PDR COORDINATOR O';LY
                                                /
/
Report sent to HQs and hold copics reproduced                                           Date_
Report sent to HQs and hold copics reproduced Date_
Initials Incoming Licensee Correspondence
Initials Incoming Licensee Correspondence 1.
: 1. Licensee Response to Non-Enforcement Report
Licensee Response to Non-Enforcement Report 2.
: 2. Licensee Response to Enforcement Report
Licensee Response to Enforcement Report 3.
: 3. Licensee Response to IE Eulletins
Licensee Response to IE Eulletins 4.
: 4. General Licensee Correspondence h Licensee Event Reports
General Licensee Correspondence h Licensee Event Reports Licensce/ Facility l Y [ d C Mut./
: a. Licensce/ Facility l Y [ d C                       Mut./           u    /
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: b. Report No.         OM8             7[-O [
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: c. Document      Date    [t?h M                   d. Date Received h id7'7 ~7 [
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: e. Section Chief M442,                         f. Principal Inspector         M/<
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: h. Licensea Response to Enforcement Report Only Accepteble                       Not-Teceptable                     Initials 2.790 Information                 YES                   NO   /           ~
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Initials   kNb NOTE:     If Yes, mark necessary documents to delete 2.790 Information and return with this form along with acknowledgement letter to the PDR Coordinator.
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Document Date Section Chief M442, f.
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Document transferred to Branch Date Initials h.
Licensea Response to Enforcement Report Only Accepteble Not-Teceptable Initials 2.790 Information YES NO
/
Initials kNb
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h Should the attached and related correspondence be placed in the PDR?
h Should the attached and related correspondence be placed in the PDR?
YES                 NO                     Initials fh.
YES NO Initials fh.
PDR COORDINATOR CNLY Incoming Licensee Correspondence and related documents sent to HQs and PDR.
PDR COORDINATOR CNLY Incoming Licensee Correspondence and related documents sent to HQs and PDR.
Date [ ['                         Initials         ' //
' /
Date [ ['
Initials
/
f
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                                .-                                  -                                _            _}}
_}}

Latest revision as of 09:33, 16 December 2024

RO 76-13:on 760916,normal Boric Acid Makeup to Vol Control Tank Could Not Be Accomplished Due to Plugging of Chemical & Vol Control Sys Line 1-inch-CH-56-152.Cause Unknown.Line Will Be Inspected for Indications of Solidification
ML20070J868
Person / Time
Site: Surry, 05000000
Issue date: 10/20/1976
From: Stallings C
VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
To: Moseley N
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
Shared Package
ML20070J834 List:
References
FOIA-82-534 292, RO-76-13, NUDOCS 8212290075
Download: ML20070J868 (5)


Text

VIRGINIA EI.ECTRIC AND Pow.. CO31PANY Ric113t OND.VI Ro r x1 A C3GC1 October 20, 1976 Mr. Norman C. Moseley, Director Serial No. 292 Office of Inspection and Enforcement P0&M/ALH:clw U.S. Nuclear Regulatory Cocsission Region II - Suite 818 Docket Fo. 50-280 230 Peachtree Street, Northwest License No. DPR-32 Atlanta, Georgia 30303

Dear Mr. Moseley:

Pursuant to Surry Power Station Technical Specification 6.6.B.2, the Virginia Electric and Power Company hereby submits a copy of Licensee Event Report USRE-SI-76-13.

The substance of this report has been reviewed by the Station Nuclear Safety and Operating Co=:nittee and will be placed on the agenda for the next meeting of the System Nuclear Safety and Operating Co=mittee.

Very truly yours, C. M. Stallings

{

Vice President-Power upply

(

and Production Operations Enclosure cc:

Mr. Robert W. Reid, Chief Operating Reactors Branch 4 (40 copies USRE-S1-76-13) l l

l

/6 8212290075 821130 7

("

" G.

PDR FOIA SCHLIsss2-534 PDR l

--....------...t i

e t

i t

f-(PLEASE PRINT ALL LEQUIRED INF%3 1

8

,s N ME LCENSE NUMBER Q j vl Al SlP lS l t l l0l0l~l0l0l0l0l0l-l0l0l l4 l1 l1l1l0l l0l3l

~

7 89 14 15 25 26 30 31 32

,1 CATEGORY pf N E 00CxET NUMBER 01 CGN'T l p l ol M l 0l 5l 0l-l 0l 2l 8l 0 l l 0l 9l Il 6l 7l 6l

[ t l 0 l 1l 5ll EVENT DATE REPORT DAK 7 8 57 58 59 60 61 68 69 -

74 75 EVENT DESCRIPTION lDuring normal operations, it was discovered that normal boric acid cakeup to the vs o2 7,8 9 l control tank could not be accomplished due to an apparent plugging of CVCS line 1"c 03 7 89

@ ]56-152.

In order to clear the line, recirculation between the boric acid tanks anj 7 8

@9l boron injection tank was secured for five (5) minutes to permit installation of a 7 89 RE l blank flange in the line.

Since Technical Specification 3.2.C.6 requires con- (cos 7 89 coy

$oE COMPONENT CODE

@ lP l Cl lF l lX lX lX l Xl Xl Xl

]

lz l9 l9 l9 l W

VoLAToM 7 89 10 11 12 17 43 44 47 48 CAUSE DESCRIPTION l Boric acid is transferred through line 1"-CH-56-152 on a regular basis for volume G 0

7 89 ltroltankmake-up.

This routine usage, coupled with the fact that no malfunctionia 09 7 89

' 10 l heat tracing was found either in the pipe in question or any upctream pipe (con't) 7 89 FACUTY METHOD OF STATUS

% POWEA OTHER STATUS OtSCOVERY I

W l_1_ l 0 l 0 l l

N/A l @

l' N/A OtSCoVERY CESCRIPTON 1

7 8 9

10 12 13 44 45 48 ACTMTV CCATENT RELEASED OF RELEASE l N/A l

l N/A AMOUNT OF ACTMTY 12 l_z_,l l,z,j LOCATCN OF RELEASE 7 8 9

10 11 44 45 PERSONNEL EXPOSURES NUMBER TYPE DESCRIPTION Q l0l0l0l Wl N/A 7 89 11 12 13 PERSONNEL INJURIES NUMBER CESCRtPTON

@ l0l0l0l l

N/A 7 89 11 12 OFFSITE CONSEQUENCES DE l N/A 7 89 LOSS OR DAMAGE TO FAC1UTY TYPE

@ W lDESCPSTON N/A 7 89 10 PUBUCITY Ql N/A 7 89 ADQtTIONAL FACTORS l Since the capabilities of the safety injection system were not 18 impaired by this eveg 7 89 Q l the health and safety of the general public were not affected.

7 89 NAME:

Tyndall L. Baucon PHONE, (804) 337-3184 p

EVENT DESCRI~ ' ION (c::n't) tinuous recirculation, an immediate reactor rampdown was initiated until boron injection tank recirculation was returned to normal.

Once the line was cleared of the obstruction, boron recirculation was again secured while the blank flangG was removed. A reactor rampdown was performed during this operation which lastG for approximately three (3) minutes.

(USRE-S1-76-13)

CAUSE DESCRIPTION (con't) leaves the cause of the obstruction as an unknown factor. The line was inspectG for potential " cold" spots which could cause isolated solidification of boric acid, but none were found in the area of the obstruction.

The line will be in-spected for indications of solidification during the next refueling shutdown.

During the period of obstruction, the capability to add boric acid to the reactor coolant system was maintained.

In addition, the boron injection tank was capable of performing its intended function.

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Licensee Response to Non-Enforcement Report 2.

Licensee Response to Enforcement Report 3.

Licensee Response to IE Bulletins 4

General Licensee Correspondence Licensee Event Reports Licensee / Facility //((M IMa

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Licensee Response to Enforcetsnt Report Only l

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1 Vircinia Electric and Pover Co.mpany Eochet No.

50-280 Surry Unit 1 License No.

DPR-32 REPORTABLE OCCURRENCE REPORT 30:

Ro-280/76-07 DISTRIBUTION:

Don Lanham, ADM cc With Fnclosures Region II Docket Files 280 Rettion II Inspector with enclosures i

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Licensee Response to Non-Enforcement Report 2.

Licensee Response to Enforcement Report 3.

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General Licensee Correspondence h Licensee Event Reports Licensce/ Facility l Y [ d C Mut./

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PDR COORDINATOR CNLY Incoming Licensee Correspondence and related documents sent to HQs and PDR.

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