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{{Adams | |||
| number = ML20236D850 | |||
| issue date = 04/15/1987 | |||
| title = Potential Condition Adverse to Quality Rept Pcaq 86-0663, Usurping Authority for Direction of Reactor Operations from Line Mgt | |||
| author name = Stephenson D | |||
| author affiliation = NRC | |||
| addressee name = | |||
| addressee affiliation = | |||
| docket = 05000346 | |||
| license number = | |||
| contact person = | |||
| case reference number = FOIA-87-687 | |||
| document report number = PCAQ-86-0663, PCAQ-86-663, NUDOCS 8710280387 | |||
| package number = ML20236D821 | |||
| document type = NRC TECHNICAL REPORT, TEXT-SAFETY REPORT | |||
| page count = 8 | |||
}} | |||
=Text= | |||
{{#Wiki_filter:- | |||
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$$$ STATUS AND RQPORJABILfTY lWkc"A. # | |||
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^ swizAnos o PCAoRB APPROVAt vta'"ED oAlt (o I hs 1S r %4.A strJ- v2. '5o-E PART 5 feee pepe 2) | |||
REMEDIAL ACTIONS I PART S feee pope 31 PPaovio e r oac'Na*1'oh ~^ WORK COMPLET)ON . . ._ | |||
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7 .s/)CUMENT R EVIEW ' | |||
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A -/8 -/1 . ,,, r- i, , - - Cr & l REVIEW $UguiTTEO TO REVIEW CONDUCTED SY | |||
. A N,2 A T 40 N INOlVIDUAL UAL ORG ANIZ ATION 50INo8tV/1).8 &, ' | |||
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0 S> f 1 SRB MurIING MINL7!ES 8 1953 2 PI2RUARY 18, 1987 | |||
'the Board reviewed REV 6 to Pr 5163.02, Reactor coolant Plow Refueling 14st . | |||
but returned it because it did not address previous spa concerns , | |||
satisfactorily. | |||
The Board reviewW Rrv 1 to PP 1101.07, Miscellaneous Operation Curves, but returned it with several ccenents to be resolved concerning whether or not , | |||
Tech Spec curves should be included in this procedure. i the Board reviewed and approved the following INR's and unanianusly recommended them for the Plant Manager's approval, unless otherwise noted: | |||
l | |||
* denotes the INR's that corrective action will be tracked by a PCno:- J l | |||
*!NR 85r-079, Inadvertent ARTS Channel 4 actuation when testini; a Main { | |||
Turbine Main Steam Stop valve during PT 5193.01 * | |||
(T.S. 3.3.2.2). - PCAQ 87-25 INR 85-102, Main Steam System | |||
*tNR 85-117, Position Indicator channels (T.S.- 3.1.3.3) - PCAQ 87-0050 INR 85-114, RPI Pump Startup Strainers (10CTR50.72(b)(2)). | |||
INR 85-142, Main Peedwater System atNR 84-155, Spent Fuel Fool (T.S. 3.9.11) PCAQ 87-0062 * | |||
*INR 86-046, Radiation Monitoring System (T.S. 3.3.3.9) PCAQ 87-0057 INR 86-089, Decay seat / Low Pressure Injection Systems (T.S. 4.5.2.)- | |||
*INR 86-091, SmCS (T.S. 3.3.2.2) PCAQ 87-0041 | |||
*INR 86-105, Waste Gas (T.S. 3.3.3.10) PCAQ 87-0071 | |||
*INR 86-108, AFW SG I4 vel Control System (T.S. 4.7.1.2.C) PCAQ 87-063 | |||
*INR 86-091, RCS Plant ceaputer System (T.S. 3.3.3.6) PCAQ 87-0074 | |||
*INR 86-113, Spent Fuel Pool Area EVS (T.S. 3.9.12) PCAQ 87-0081 | |||
*INR 85-074, Storage Pool (T.S. 3.9.11) PCAQ 87-0064 | |||
*INR 85-021, ATW pump cavitation - PCAQ 87-0083 | |||
*INR 85-046, Main Steam Line (T.S. 3.7.1.1) PCAQ 87-0079 | |||
*INR 81-077, Decay Heat / Low Pressure Injection - PCAQ 87-0088 | |||
*INR 86-056, I.PI & CS Inw Pressure Injection & Ctat Spray - PCAQ 87-0085 | |||
*!NR 86-065, CNRB (T.S. 6.5.2.2) PCAQ 87-0086 | |||
*tNa 85-171, Auxiliary FW System - PCAQ 87-0087 | |||
*INR 85-156, Control Room Emergency H&V Sys - PCAQ 87-0089 | |||
'the Board reviewed and approved the following PCAQ'S for closecut unless otherwise noted: - | |||
A PCAQ 86-0663, RrIURNED because do not concur with Corrective Action. | |||
Needs to reference ReEtart Administrative Instructions 10 | |||
& 11 and they need to be included as they corrective action. . | |||
PCAQ 87-0007, Excessive Shrinkage of Raychem Material PCAQ 87-0014, Main Feed Pump Turbine 1-1 Oil Deflector Installation l PCAO 87-0524, unauthorized Procurement Of Q Material - | |||
l PCAO 86-0351, Post Accident Sanpling System SV4637 Installed backward to ' | |||
flow PCAQ 86-0626, Door 307 Fire Watch (While Maintenance work in progress) | |||
PCAO 87-0016, unusual Event due to AFW Inoperability PCAO 87-0176, riexible Boot Seals | |||
: 1. . | |||
/ - | |||
/ | |||
SRB MZTINC,MIMHT.S 9 1976 3 APRIL .1, .1987 i r m e Board' reviewed and approved Revisions to the following procedures and unanimously.recomended them for the Plant Manager's approval unle,ss otherwise j noted: l 1 | |||
~ AB 1203.27, REV 3, toad Rejection (R-520) l SP 1105.21, REV 2, Anticipatory Reactor Trip System (ARTS) (R-732) | |||
AD 1845.03 PIV 2, Facility Change Request Implementation (R-821) l ST 5071.12, REV 1, Aux 111ary Feedwater Puup 1-1 Quarterly Test - REWPM:D ') | |||
because it needs O W C review prior to SRB ! | |||
sT 5071.22, RLY 1, Auxiliary Peedwater Pump 1-2 Quarterly Test - REWRNED j | |||
' because it needs %gc review prior to SRB | |||
. %e Board approved Test Results- to TP 851.55, MSIV stroke wat datea 3/25/87 | |||
* and unanimously recomended them for the Plant' Manager's approval. 1 m e Board reviewed and approved the following PCAQR's for closeout: , | |||
}.GQR86-0663, Usurping authority for direction of reactor operations . | |||
from line sanagement. l PCAQR 86-0369, Filler Material Issue Ticket | |||
* l PCAQR 86-0629, Station Batteries 2N & SP Fall to meet Acceptance Criteria' ) | |||
of ST 5084.03 PCAQR 87-0086, Technical Specification and CNRB Membership difference (DVR 86-0065) | |||
PCAQR 86-0577, FSK-M-HCC-89-2-H Supports 2" Quench Tank Recirc piping f rom Check Valve af ter penet. 41 to quench tank l PCAQR 87-0149, Impact Tests for Feedwater Isolation valves numbers rh'601 | |||
& FW612 (B90) l PCAQR 87-0069, C12 Detector not adequately protected (DVR 83-082) f PCAOR 86-0281, failure to Perform Procedural Requirements PCAQR 87-0108, Overdue FM Activity (3-87-1189-01, CREVS 92) ! | |||
PCAQR 86-0598,. Substitution of incompatible grease ] | |||
PCAQR 87-0139, Failure of RIG 459BAA ( | |||
PCAQR 86-0212, Lack of ASME Section XI Reviews Performed during the I design process . | |||
PCAQR 87-0087, operated Outside SAR with AF3872 Open (DVR 85-171) | |||
PCAQR 87-0054, Door # 503 while painting j PCAQR 87-0106, SFAS Rad Detector (DVR 85-067) l l | |||
h e Board approved meeting minutes numbers 1966, 1967, 1968, 1969, and 1970. - | |||
l | |||
. . ) | |||
Were were no unreviewed safety questions or concerns identified and not addressed for resolution on the items reviewed during this meeting. | |||
Adjourned: 2:50 P.M. tfdd t'(:'6a h4 WWW , | |||
Carol zi rman Station eview Board Clerk APPROVED BY: k d O w M DATE: 4/,o f 77 Station Revie'w Board Chairman . | |||
cc: Sr. Vice President, Nuclear-Stop 3080; NRC Resident Inspector - Stop 4000 SRBAGE Members; Records Management File: RR 5.3 | |||
_ _ _ - _ . _ _ _ _ _ _ _ _ _ _ - . _ . _ _ _ _ _ - _ _ _ _ _ _}} |
Latest revision as of 02:38, 5 August 2021
ML20236D850 | |
Person / Time | |
---|---|
Site: | Davis Besse |
Issue date: | 04/15/1987 |
From: | Stephenson D NRC |
To: | |
Shared Package | |
ML20236D821 | List: |
References | |
FOIA-87-687 PCAQ-86-0663, PCAQ-86-663, NUDOCS 8710280387 | |
Download: ML20236D850 (8) | |
Text
-
- P0ftPmAL CONDm0N
- Apygsts'. TO CUAUTY 4tEPOR[
c Kd8Hl19 I ei1 ecAca no 'Aot '
- n ==
wu m . na Jr4 wTiATiON n e, '
LL su e o;,,8 n %)v
. =n - -
e v-i br J.<n k of,wL wk,,s ..frn, La n .,od o E x A,,o., , . A. .. ,n .s v 1212,c h, o% A,, h o vEs e ao
. .u n m.c, Do kfaoao m g., a , _,.- , . ..
= en scairnoe. or conwn= coa.oitioa m ,,Aonatt
,,,,,,,, * , to (s. A ous%
a a l* )
Ce tilati tvt j d kt seeumid ned %, _ _ _ , ),,.df I
m m ,%
bh s e o s im W W51L A* cmu PT 5t75'.0l OW Tacest De b b c
l c .au.a.4.w
.. .o Acno., cateskk a.ht. A .n.a t ,5 s sw h gunosa a (a
- n +,.-,,f,a 3) o- H n 1 k J PiaA h % w U s navanancs5 m notaron ,
oacANaAnon can psau,Fe.ce ~> b b n y , r. O Ccs, c r- l & <r d m s I / a /.ae / u PART2 A esOof 8 REAClom rowta s c erwt
$$$ STATUS AND RQPORJABILfTY lWkc"A. #
\5l30lf6 o sv5ftM " E SYSTlW10VIPMENT No.
I LO @
F IbsMiotATE ACTION /ConsWEN15 ss 4 p tA mur .trotE*Bo . m ST% c uAs orsumro I 8710280387 871026 WE -687 PDR s uronsAwn E wa O 1 *n O 4 wa s,E cory OrnE R H ut(RINC15 e coterts tgo 3, OAft wgn. <,o PART3 w%_ ~T5\L lenA*~M A en irno DemAL REVIEW -
w conomon Ano mutcan Acisoa catcasor un p h .
cgnac'an
.=vy h, W .no .. coo, I fl-O&.
- v M '
l 12-3D-$
dg PART 4 N MTnAL RIMEW A ev4UAnoN AS$eGNulNT Eva Q ()( ghESPONSIBILITY P.C. M h.bcowdV ONE REQUIRED I 8 PasoRifY c.tV40Af ton out GAtt
^ swizAnos o PCAoRB APPROVAt vta'"ED oAlt (o I hs 1S r %4.A strJ- v2. '5o-E PART 5 feee pepe 2)
REMEDIAL ACTIONS I PART S feee pope 31 PPaovio e r oac'Na*1'oh ~^ WORK COMPLET)ON . . ._
m 1 a ecAone nPrnovu t:30isfe'~
_ _j o*"
l PART7 /
_ 2_- A f 7 0*Es Do '
l E~5'#7 I A sas Arraove COMPLET)ON REVIEW Ar*=cvu oArt usi n~c auweta g vEs Owo).U EAd*-lA/ g / p l M7 to i O NOT REQUIRED 1 8 Oc sNSP1CTCB b"I 1AG5 AtMovto SY O#II 0 N/k e(L c Atitwongao sucts AR INEPlCIoR fcode hwns oa*,i l ']- IS-t 7 l Nk W \%VD DATI NA 4g l 4-15-r7 e aA . , ,,, ~, o . ,
. (c s /
yoz
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Jct I )I 2
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(SciT fk th4. Oh . fDAC#hdA A A letIR t
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)
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.s , y
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f .
I D. MONCONFORwiNG fit M PMoe0580 PSPOSITON O U$f AS-Is O U$( AS fS TEMPORARILYJa- OatPria O AswoaK 0 atleci
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M. ASStGNED 10 *panesetent
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0 S> f 1 SRB MurIING MINL7!ES 8 1953 2 PI2RUARY 18, 1987
'the Board reviewed REV 6 to Pr 5163.02, Reactor coolant Plow Refueling 14st .
but returned it because it did not address previous spa concerns ,
satisfactorily.
The Board reviewW Rrv 1 to PP 1101.07, Miscellaneous Operation Curves, but returned it with several ccenents to be resolved concerning whether or not ,
Tech Spec curves should be included in this procedure. i the Board reviewed and approved the following INR's and unanianusly recommended them for the Plant Manager's approval, unless otherwise noted:
l
- denotes the INR's that corrective action will be tracked by a PCno:- J l
Turbine Main Steam Stop valve during PT 5193.01 *
(T.S. 3.3.2.2). - PCAQ 87-25 INR 85-102, Main Steam System
- tNR 85-117, Position Indicator channels (T.S.- 3.1.3.3) - PCAQ 87-0050 INR 85-114, RPI Pump Startup Strainers (10CTR50.72(b)(2)).
INR 85-142, Main Peedwater System atNR 84-155, Spent Fuel Fool (T.S. 3.9.11) PCAQ 87-0062 *
- INR 86-046, Radiation Monitoring System (T.S. 3.3.3.9) PCAQ 87-0057 INR 86-089, Decay seat / Low Pressure Injection Systems (T.S. 4.5.2.)-
- INR 86-091, SmCS (T.S. 3.3.2.2) PCAQ 87-0041
- INR 86-105, Waste Gas (T.S. 3.3.3.10) PCAQ 87-0071
- INR 86-091, RCS Plant ceaputer System (T.S. 3.3.3.6) PCAQ 87-0074
- INR 86-113, Spent Fuel Pool Area EVS (T.S. 3.9.12) PCAQ 87-0081
- INR 85-074, Storage Pool (T.S. 3.9.11) PCAQ 87-0064
- INR 85-021, ATW pump cavitation - PCAQ 87-0083
- INR 85-046, Main Steam Line (T.S. 3.7.1.1) PCAQ 87-0079
- INR 81-077, Decay Heat / Low Pressure Injection - PCAQ 87-0088
- !NR 86-065, CNRB (T.S. 6.5.2.2) PCAQ 87-0086
- tNa 85-171, Auxiliary FW System - PCAQ 87-0087
- INR 85-156, Control Room Emergency H&V Sys - PCAQ 87-0089
'the Board reviewed and approved the following PCAQ'S for closecut unless otherwise noted: -
A PCAQ 86-0663, RrIURNED because do not concur with Corrective Action.
Needs to reference ReEtart Administrative Instructions 10
& 11 and they need to be included as they corrective action. .
PCAQ 87-0007, Excessive Shrinkage of Raychem Material PCAQ 87-0014, Main Feed Pump Turbine 1-1 Oil Deflector Installation l PCAO 87-0524, unauthorized Procurement Of Q Material -
l PCAO 86-0351, Post Accident Sanpling System SV4637 Installed backward to '
flow PCAQ 86-0626, Door 307 Fire Watch (While Maintenance work in progress)
PCAO 87-0016, unusual Event due to AFW Inoperability PCAO 87-0176, riexible Boot Seals
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SRB MZTINC,MIMHT.S 9 1976 3 APRIL .1, .1987 i r m e Board' reviewed and approved Revisions to the following procedures and unanimously.recomended them for the Plant Manager's approval unle,ss otherwise j noted: l 1
~ AB 1203.27, REV 3, toad Rejection (R-520) l SP 1105.21, REV 2, Anticipatory Reactor Trip System (ARTS) (R-732)
AD 1845.03 PIV 2, Facility Change Request Implementation (R-821) l ST 5071.12, REV 1, Aux 111ary Feedwater Puup 1-1 Quarterly Test - REWPM:D ')
because it needs O W C review prior to SRB !
sT 5071.22, RLY 1, Auxiliary Peedwater Pump 1-2 Quarterly Test - REWRNED j
' because it needs %gc review prior to SRB
. %e Board approved Test Results- to TP 851.55, MSIV stroke wat datea 3/25/87
- and unanimously recomended them for the Plant' Manager's approval. 1 m e Board reviewed and approved the following PCAQR's for closeout: ,
}.GQR86-0663, Usurping authority for direction of reactor operations .
from line sanagement. l PCAQR 86-0369, Filler Material Issue Ticket
- l PCAQR 86-0629, Station Batteries 2N & SP Fall to meet Acceptance Criteria' )
of ST 5084.03 PCAQR 87-0086, Technical Specification and CNRB Membership difference (DVR 86-0065)
PCAQR 86-0577, FSK-M-HCC-89-2-H Supports 2" Quench Tank Recirc piping f rom Check Valve af ter penet. 41 to quench tank l PCAQR 87-0149, Impact Tests for Feedwater Isolation valves numbers rh'601
& FW612 (B90) l PCAQR 87-0069, C12 Detector not adequately protected (DVR 83-082) f PCAOR 86-0281, failure to Perform Procedural Requirements PCAQR 87-0108, Overdue FM Activity (3-87-1189-01, CREVS 92) !
PCAQR 86-0598,. Substitution of incompatible grease ]
PCAQR 87-0139, Failure of RIG 459BAA (
PCAQR 86-0212, Lack of ASME Section XI Reviews Performed during the I design process .
PCAQR 87-0087, operated Outside SAR with AF3872 Open (DVR 85-171)
PCAQR 87-0054, Door # 503 while painting j PCAQR 87-0106, SFAS Rad Detector (DVR 85-067) l l
h e Board approved meeting minutes numbers 1966, 1967, 1968, 1969, and 1970. -
l
. . )
Were were no unreviewed safety questions or concerns identified and not addressed for resolution on the items reviewed during this meeting.
Adjourned: 2:50 P.M. tfdd t'(:'6a h4 WWW ,
Carol zi rman Station eview Board Clerk APPROVED BY: k d O w M DATE: 4/,o f 77 Station Revie'w Board Chairman .
cc: Sr. Vice President, Nuclear-Stop 3080; NRC Resident Inspector - Stop 4000 SRBAGE Members; Records Management File: RR 5.3
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