ML20236D850

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Potential Condition Adverse to Quality Rept Pcaq 86-0663, Usurping Authority for Direction of Reactor Operations from Line Mgt
ML20236D850
Person / Time
Site: Davis Besse Cleveland Electric icon.png
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)


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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:

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  • 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 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. .

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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. -

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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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