ML20236D850

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
Issue date:	04/15/1987
From:	Stephenson D NRC
To:
Shared Package
ML20236D821	List: IA-87-687, Potential Condition Adverse to Quality Rept Pcaq 86-0663, Usurping Authority for Direction of Reactor Operations from Line Mgt ML20236D819 ML20236D850
References
FOIA-87-687 PCAQ-86-0663, PCAQ-86-663, NUDOCS 8710280387
Download: ML20236D850 (8)

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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:-

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• !NR 85r-079, Inadvertent ARTS Channel 4 actuation when testini; a Main

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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:

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~ 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

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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

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PCAQR 87-0139, Failure of RIG 459BAA

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PCAQR 86-0212, Lack of ASME Section XI Reviews Performed during the 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) h e Board approved meeting minutes numbers 1966, 1967, 1968, 1969, and 1970.

)

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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