ML20137X563
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| ML20137X563 | |
| Person / Time | |
|---|---|
| Site: | South Texas, 05000000 |
| Issue date: | 04/29/1982 |
| From: | Jay Collins NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| To: | Fortuna R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE) |
| Shared Package | |
| ML20137X502 | List: |
| References | |
| FOIA-85-519 NUDOCS 8603100197 | |
| Download: ML20137X563 (116) | |
See also: IR 05000498/1982002
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NUCLE AR REGULATORY COMMISSION
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April 29, 1982 i
MEMORANDUM FOR: Roger Fortuna, Chief Investigation Branch, El
Office of Inspection and Enforcement, HQ l
FROM: John T. Collins, Regional Administrator, Region IV
$UBJECT: INVESTIGATION CONCERNING THE QUADREX REPORT (50 498/82-02;
50-499/82-02)
1. In accordance with TI 2150/2, the subject investigation report is bein
forwarded to you for referral to CIA and/or other appropriate action. g
In view of the potential criminality on part of HL&P management, we
recommend referral to O!A. I
2. Enclosed in a sealed envelope attached to the investigation report is '
supporting documentation, including signed statements concerning this
matter,
j
3. We will hold any further enforcement action and the dissemination of ,
this report in abeyance pending notification from your of fice of the l
disposition of this matter.
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(flu.'/ 6 M u b
John T. Collins l
Regional Administrator
Enclosure: As Stated
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- Brown f5 Root,Inc. Post Office Box Three, Houston, Texas 77001
A minunon company
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May 8,1981
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Houston Lighting & Power Company
P.O. Box 1700 #4@
Houston, Texas 77001 g
Attention: J. H. Goldberg
Subject: South Texas Project, Quadrex Engineering Review, dated May 8,1981
Dear Mr. Goldberg:
In response to your letter of May 6,1981, Brown & Root has reviewed the
"most serious" items identified in the subject report to. advise on whether
these constitute a potential reportable problem in accordance with 10CFR50.55fe).
All items have been judged by Brown & Root to be not reportable under 50.55(e)
exceptfor4.4.2.1(a)/(b). This is sumarized in Enclosure (1). Brown & Root
is also evaluating potential reportability pursuant to 10CFR21.
C The results of the review of all other items, including the rationale for
judgement of non-reportability, is attached as Enclosure (2).
In reviewing the report prepared by Quadrex, Brown & Root had already taken
action on the significant concerns before the Design Review comenced. Brown
& Root also has technical disagreement with some of the findings and will
respond accordingly. In general, Brown & Root has no disagreement with most
of the findings since they serve to provide verification of concerns we had
already identified in the course of our Design Review program. Brown & Root
wishes to emphasize that we have made and will continue to make every effort
to provide a well engineered design which meets all licensing requirements,
as well as those requirements which will result in a plant that meets good
power plant engineering practices from an operation and maintenance point
of view.
In response to your requests on item 2 of your letter of May 6,1981, Brown
& Root will submit a plan of action and schedule for responding to each of
the items in the Quadren report by May 15, 1931. Based upon our initial
review, Brown & Root has not found any problems which would justify issuing
a stop work order in any construction area. This will be evaluated further
when these items are reviewed in greater detail.
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imC mV QUA0rX PtVIEW
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May 8,1981
s
It is clear that if we concentrate our resources to respond to all these
concerns on a first priority basis, there. will be an impact on cost and
schedule in Engineering. Attempting to quantify this cost and schedule
impact is difficult because our experience in these matters shows that the
t '
ultimate resolution could require many iterations. We also question the
I rationale for responding to all of these items on a first priority basis
to the exclusion of proceeding with an orderly design process.
We are caught in a situation where the majority of the issues will be
judgenental while others are of little significance. We reconnend we
l discuss this in greater depth before proceeding toomuch further to ensure l ,
that the program is in the best interests of HL&P.
Sincerely
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. . Saltare111
Senior Vice President &
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Chief Engineer
Power Group
i ! EAS/rj l l cc: G.W.Oprea,Jr.(HL&P) l
W. B. Pieper
"
l . u ts NRC RIV QUADREX REVIEW
sgrrrcrce DOCUMENT
l K. M. Broom l C. L. Buck no, Y ! J. L. Hawks
J.R. Sumpter (HL&P)
i C. Robertson(HL&P) l D. G. Barker (HL&P)
J.W.Briskin(HL&P)
i J.L.Blau(HL&P) l J. A. Signorelli
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ENCLOSURE (2)
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SUPMARY OF BROWN AND ROOT FINDINGS ON
SOUTH TEXAS PROJECT QUADREX ENGINEERING REVIEW (May 1981)
! TEM 4.4.2.1(a)/(b)
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NRC filV QUADREX REVIEW
REFER;f40E DOCUMENT
NO. Y
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( SUBJECT
Inadequacy of the following STP HVAC Systems:
- MAB
- Fuel Handling Building
- EAB
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DESCRIPTION OF p0TENTiAL PROBLEM
On April 7,1980. Houston Lighting & Power (HL&P) informed Brown & Root
of a potential problem of cooling the Radwaste Control Room in the MAB.
A BAR study group was formed (Special Problem #16) with representation
from the (B&R) Mechanical, Electrical. I&C, Structural Nuclear Analysis
and HVAC Disciplines. On wpterter 18, 1980 a preliminary assessment
concerviing candidate areas for additional study was released. The candi-
date areas included: the electrical penetration space in the EAB; the
radwaste control room, which contains the hot shutdown panel, the reactor
~
make-up water pump cubicle, the boric acid transfer pump cubicle, the
CVCS valve cubicle at elevation 41'-0" and 10'-0" in the MAB: the spent
fuel pool cooling pump cubicles in the fuel handling building (FHB) and
the valve cubicles in the FHB where containment isolation valves in dis-
charge lines from the High Head Safety injection, Low Head Safety In-
, jection and Containment Spray pumps are located. At this time a possible
need for supplemental, air cooled chillers to handle additional antici-
pated (based on engineering judgement) HVAC loads were discussed.
' From January 7,1981 thru January 27, 1981, calculations were informally
received from the HVAC grcup confirming the need for additional HVAC
- cooling capacity. On March 12, 1981, a draft report was issued by the
B&R Special Priblems Grenp which surunarized the thermal environmental
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data which had been recetred and confirmed the need for supplemental
cooling of the equipment' described in Table 1 (Attached).
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On March 19, 1981, representatives of QUADREX, under contract to HL&P,
- conducted a technical audit of B&R's HVAC System design and in a report
received by B&R on May 7,1981, confirmed B&R's earlier assessment that
there may be insufficient HVAC cooling capacity for equipment located
in the MAB and FHB.
Although we do not yet have actual heat load data, including maximum
,
allowable operating temperature information, for all potentially affected
systems, we believe that there is currently sufficient uncertainty con-
cerning the adequacy of the HVAC Systems designed for the MAB, FHB and
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EA8 to consider the matter to be potentially reportable at this time.
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NRC RIV QUADR 2X REVIEW
REFERCNOE DOOUMENT
no. Y
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Brown & Root.hc.
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APPROACH TO RESOLUTION
A supplemental HVAC system composed of in-room fan-coil units and air
cooled chillers is curmntly being considered for incorporation into the
STP Units. Sketches showing proposed physical arrangements are currently
being prepared for candidate locations and additional thennal operating
data is being sought from all equipment vendors.
OSED RESOLUTION
STATUS OF Mi ,
A final determination concerning the need for additional safety grade HVAC
capacity will be completed upon receipt of the following evaluations: pipe
bmaks outside containment (QUADREX Audit Question 4.4.4.1.a); and, special
problem 15 (QUADREX Audit Question 4.4.4.1.b). These evaluations will con-
sider the equipment and piping heat losses and the maximum environment for
which the safety related components are qualified. Without perfonning
these evaluations we cannot determine the exact magnitude of the impact
on plant safety.
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Based on these uncertainties, we feel that this problem is potentially re-
portable under 10CFR50.55(e) 'and is currently being investigated as a
potential 10CFR21.
( REASONS FOR FINAL REPORTABILITY DELAY
Project Engineering had not completed sufficient thennal calculations to
indicate a clear need for a supplemental HVAC System.
PROJECTED COMPLETION OF CORRECTIVE ACTION
The projected completion date for the following Special Problem #16 acti-
vities is currently June 15, 1981 to have a definition of design qualification
temperatures for safety related equipment, a preliminary assessment of heat
losses and area temperatures and a conceptual design and preliminary lay-
out for a supplemental HVAC system.
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NRC RIV QUADREX REVIEW
( REFEREt CE DOCUMENT
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TABt.F-
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. CANDIDATES FOR Nt AC SERVICE l
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EQUIPMENT REQUIRING- EQUIP. QUALIF. POST-ACCIDENT POST-ACCIDENT EQUIP'.DfT-
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LOCATION
TEMP. F TEMPERATURE w/o HVAC, HEAT LOAD STATUS'
TEMP CONTROL
, 1 F (1) Btu /hr .i i Radwaste Control Room, H2 M nit ring Equip. 104 184 270,000 ON SITE p MAB
"
Class IE Cables 120 1st Fl: 193 '211,260(3)
. Elcctrical Penetration 2nd F.: 204 251,940 (3)
Space, EAB (2) 255,620(3)
3rd Fl.: 185
"
Reactor make-up 120 195 61,000
Reactor make-up water
Pumps Cubicle. MAB Water Pumps
] 66,300 "
Spent Fuel Pool SFPCCS Pumps 120 268
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Pump Cubicles. FHB
"
120 197 42,000
Boric Acid Transfer Boric Acid. Transfer
Pumps Cubicle, MAB Pumps (4)
=
120 (later) 31,800
Cont. Iso. Valve Cont. Iso. Valves (5)
Cubicles. FHB B&R Valve Nos.:
(3 cubicles) XS! 004A, B C
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XSI Ol8A, B C
XCS 001A, B, C
=
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120 El . 10'-0": 150 33,400
j Valve Cubicles in MAS CVCS Valves used for 38,400 j (3 cubicles) boration(4) El. 41'-0": 150 '
BAR Valve Nos.: -
XCV 218
! XCV ll2C
XCV 1138
XCV 1128
XCV ll3A
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Elect. Aux. Bldg. EAB Chillers (later) (later) (later)
4
Chiller Area
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(located in MAB) .
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Footnotes (see Page 2) NRC RIV QUADREX REVIEW '
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REFERENCE DOCUMENT
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FOOTNOTES - TABLE 1 - CANDIDATES FOR NEW HVAC SERVICE
- Page 2
1. Calcualted environmental temperature in the cubicle or area when only safety
related equipment is operating, and with no HVAC service.
2. HVAC for this area has been identified as critical concern No. 11-5 (1979).
The equipment listed requires environmental temperature control during operating
conditions.
3. During nonnal operation, heat loads are:
1st Floor 81.200 Btu /hr. '
2nd Floor 123.350 Btu /hr.
3rd Floor 121.400 Btu /hr.
'4. Capacity for cooling this area should be included when sizing the chiller.
However, since alternative methods of boration are available, no further design
toward adding coolers should be performed until Westinghouse is appraised of the
calculated cubicle temperatures, and the preferred boration method is identified.
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5. Requalification or replacement of the valve actuators are possible alternatives
to adding HVAC Coolers. Capacity for cooling these cubicles should be included
when sizing the chillers. .:u
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NRC RIV QUADREX REVIEW
REFEREf4CE DOCUMENT
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ENCLOSURE (1)
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BROWN & ROOT REVIEW OF
SOUTH TEXAS PROJECT QUADREX ENGINEERING REVIEW (May 1981)
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NRC RIV QUADREX REVIEW
REFEREf4CE DOCUMENT ~
NO.
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ITEM NUPEER: 4.1.2.1(a)
P=
DISCIPLINE: Civil / Structural
AGREE WITH FINDIN3: C
DISAGREE WITH FINDING: b
THIS ITEM IS CONSIDERED TO BE:
REPORTABLE _ ... . _ _ _.D
POTENTIALLY REPORTABLE._ _ _D
INSUFFICIENT DATA FOR ASSESSMENTQ
NOT REPORTABLE- a _ _ _. D
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BASISFORAB0VEASSESSMkNT:
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We have on many occasions rejected design inputs as unreasonable'. No re-
quimment exists for forinal documentation of evaluation of other discipline's
input.-
NRC RIV QUADREX REVIEW
REFERENCE DOCUMENT
NO.
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ITEM NUPSER: 4.1.2.1(b)
DISCIPLINE: Civil / Structural
AGREE WITH FINDING: @
DISAGREE WITH FINDING: C
THIS ITEM IS CONSIDERED TO BE:
REPORTABLE .. _ _ _ _ _.D
POTENTIALLY REPORTA8LE_ _ D
INSUFFICIENT DATA FOR ASSESSMEhiQ
NOT REPORTABLE _ _ _ ____ . D
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BASIS,FDRAB0VEASSES!MkNT:
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Generally agree with observation. However, disagree that Civil / Structural
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is required to do the evaluation. Currently, no data on internal missiles
have been rtceived. Criteria for development of internal missile parameters
is now being inclemented under a controlled program in conjunction with the
hazards analysis program.
NRC RIV QUADREX REVIEW
. RCFERENCE DOCUMENT
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ITEM NUMBER: 4.1.2.1 (c)
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(x DISCIPLINE: Civil / Structural
AGREE WITH FINDING: C
DISAGREE WITH FINDING: b
THIS ITEM IS CONSIDERED TO BE: ,
REPORTABLE. . _ _ _ _.O
POTENTIALLY REPORTABLE __ _ _ _D
INSUFFICIENT DATA FOR ASSESSMENTgl
NOT REPORTABLE _ - . .. G
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BASIS FOR AB0VE ASSESSMkNT:
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Civil / Structural Discipline have met the interaction requirements by doing
static ilBC analysis for earthquake and analysis for tornado loading, showing
T.G. Building sustains without impact on safety related items. Tomado loads
are the controlling ones for the interaction evaluation.
NRC RIV QUADREX REVIEW
REFERENCE DOCUMENT
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ITEM NUMBER: 4.1.2.1(d)
. DISCIPLINE: Civil / Structural
AGREE WITH FINDING: C ,
DISAGREE WITH FINDING: b
THIS ITEM IS CONSIDERED TO BE:
REPORTABLE. .._.. . ..D
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POTENTIALLY REFORTABLE._ __ _ D
INSUFFICIENT DATA FOR ASSESSMENTQ
NOT REPORTABLE.- . .U
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BASISFORABOYEASSESSMhMT:
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We are unable to substantiate QUADREX statement that we are not in compliance
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with SAR Comitments and approved NRC Criteria.
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NRC RIV QUADRO Rgyggy
REFEREf4CE DOCUMENT
No. _ V
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ITEM NUMBER: 4.1.2.1(e)
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'k; DISCIPLINE: Civil / Structural
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AGREE WITH FINDING: @
i DISAGREE WITH FINDING:
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THIS ITEM IS CONSIDEPID TO SE:
REPORTABLE. ._ _ _ _ _ _.D
POTENTIALLY REPORTABLE . _. _D .
INSUFFICIENT DATA FOR ASSESSMENT
NOT REPORTABLE._ _ . UQ
8 ASIS FOR ABOVE ASSESSMkNT:
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. The mcent NUREG's are not incorporated in design until they become project
cri teria. The 1.4 factor used for RCB intemal design is conservative and
based standard myiew plan.
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NRC RIV QUADREX REVIEW
REFERENCE DOOUMENT
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ITEM NUPSER: 4.1.2.1 (f)
DISCIPLINE: Civil / Structural
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AGREE WITH FINDING:
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DISA&REE WITH FINDING: b -
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THIS ITEM IS CDNSIDERED TO BE:
REPORTABLE __ .. _ _ _.D
POTENTIALLY REPORTABLE . C
INSUFFICIENT DATA FOR ASSESSMENTQ .
NOT REPORTABLE - .G .
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BASIS FOR ABOVE ASSESSMENT:
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B&R is currently working on pipe rupture outside containment. B&R use of in-
put data from EDS for pipe rupture load is adequate.
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NRC filV QUADREX REVIEW
REFERENCE DOCUMENT
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ITEM NUMBER: 4.1.2.1 (g)
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DISCIPLINE: Civil / Structural
AGREE WITH FINDING: C
DISAGREE WITH FINDING: O '
THIS ITEM IS CONSIDERED TO BE:
REPORTABLE .. _ _ . .O
POTENTIALLY REPORTABLE ._ D
INSUFFICIENT DATA FOR ASSESSMENT
NOT REPORTABLE - . .. QW
BASISFORABOVEASSESSMkNT:
.
MAB dead loads am representative based on Engineering Judgement. Also,
these loads will be verified when all hangers are designed.
The amplification factors used in MAB floors has not yet been updated based
on the latest MAB seismic analysis.
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NRC RIV QUADREX REVIEW
REFERIfJCE QOCUMENT
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ITEM NuteER: 4.1.2.1 (h)
DISCIPLINE: Civil / Structural
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AGREE WITH FINDING: C
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DISASREE WITH FINDING:
THIS ITEM IS CONSIDERED TO BE:
REPORTABLE. .. . _ _ ..O
POTENTIALLY REPORTABLE _. . _D
INSUFFICIENTDATAFORASSESSMENTQ
NOT REPORTABLE.- .. U
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BASIS FOR ABOVE ASSESSMbMT:
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The loads on structural elements are preliminary. Final verification cannot
be done until all loads are available at this time. +-
NRC RIV QUADREX REVIEW
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REFERENCE DOCUMENT
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ITEM NUMLER: 4.2.2.1
DISCIPLINE: Com,.ute r
AGREE WITH FINDING: C
O
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DISAGREE WITH FINDING: .
THIS ITEM IS CONSIDERED TO BE:
REPORTABLE _ . _ _ _ _ _.O
POTENTIALLY REPORTABLE _ D
INSUFFICIENT DATA FOR ASSES $ MENT
NOT REPORTABLE- - - -u_ _ .. Q
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BASIS FOR AB0VE ASSESSkNT:
.
. Taken'as a whole, the issue of verification of computer programs addressed
by QUADREX does not present a pmblem of " breakdown of the system" but rather
an exhibition of " weakness" in adherence to the verification procedures.
We concur, in the main, with the findings of the auditors which are very
similar to the observations made by the B&R audit team. The ongoing B&R
program in response to the audit findings requires timely response to the
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findings and will provide a much more thorough review of the status of the
individual computer codes used on STP.
NRC RIV QUADREX REVIEW
REFERENCE DOCUMENT
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ITEM NUMBER: 4.2.2.1 (a)
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DISCIPLINE: Computer .
AGREE WITH FINDING: h
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DISAGREE WITH FINDING:
THIS ITEM IS CONSIDERED TO BE:
REPORTABLE _ _ .. - - - _ _.O
POTENTIALLY REPORTABLE _. . _ _ D
INSUFFICIENT DATA FOR ASSESSMENT
NOT EPORTABLE- - . .. Q
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JASIS FOR ABOVE ASSESSMENT:
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Programs used on STP Design / Engineering should be verified. The ongoing
B&R Nuclear Analysis Program is addressing CPVR Status in risponse to an
,
internal B&R audit. The schedule for review is available. The preliminary
assessment is finding procedural problems only.
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NRC RIV QUADREX REVIEW
REFERENCE DOCUMENT
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ITEM NtMLER: 4.2.2.1(b)
DISCIPLINE: Computer
AGREE WITH FINDING: 3
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DISAGREE WITH FINDING:
THIS ITEM IS CONSIERED TO BE:
REPORTABLE. .._ _ _ ..O
POTENTIALLY REPORTABLE._ ._ D
INSUFFICIENTDATAFORASSESSMENTQ
NOT REPORTABLE - .. G
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BASIS FOR ABOVE ASSESSkNT:
. .
Verification of computer programs used on the project should occur regardless
of designation (" safety vs non-safety related"). By maintaining a distinction,
the possibility exists such that the radiological environnent "seen" by safety
classified systems could be calculated by non-safety-related computer codes ---
and hence not verified codes---- with subsequent " safety related" impact.
The definition / distinction should be addressed and resolved.
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NRC RIV QUADREX REVIEW
REFERENOE DOQUMENT
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ITEM NUPSER: 4.2.2.1 (c)
DISCIPLINE: Cog uter
AGREE WITH FINDING: C
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DISASREE WITH FINDING:
THIS ITEM IS CONSIDERED TO BE:
REPORTABLE. ._ . ..O
POTENTIALLY REPORTABLE D
INSUFFICIENT DATA FOR ASSESSMENT
NOT REPORTA8LE.- . .. Q
G
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BASIS FOR ABOYE ASSESSMENT:
*
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It is not sufficient to test only one of a codes features / options to attest
to the adequacy of the capability of the whole computer code. If a particu-
lar option is to be used, that option should be " qualified". The procedure .
could be mori specific.
NRC RIV QUADREX REV!EW
RCFEREt;CE DO MErtT
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ITEM NUPSER: 4.2.2.1 (d)
( DISCIPLINE: Computer
AGREE WITH FINDING: C
DISAGREE WITH FINDING: O 7
THIS ITEM IS CONSIDERED TO BE:
REPORTABLE. ... . _ _.D
POTENTIALLY REPORTABLE _D
INSUFFICIENT DATA FOR ASSESSMENT
NOT REPORTABLE _ . .QU
SASISFORABOVEASSESSMhMT:
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The primary licensing document (FSAR) and the program status sumary (PSS)
should reflect actual code usage. The itemization of the codes in use re-
quires- further review.
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NRC RIV QUADREX REVIEW
REFCREldCE DOCUMEtlT
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ITEM NUMBER: 4.2.2.1 (e) -
DISCIPLINE: Computer e
AGREE WITH FINDING: @
-
DISASREE WITH FINDING: O
THIS ITEM IS CONSIDERED TO BE:
REPORTABLE. .. . _ _ ..O
POTENTIALLY REPORTABLE._ _ ._ D
INSUFFICIENT DATA FOR ASSESSMENTQ
NOT REPORTABLE- - .. U
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BASIS FOR ABOYE ASSESSMENT:
. .
Errors in the verification process can reflect the perceived importance of
the verification by the reviewer and also the quality of the verifying pro-
gram in general. Subsequent intemal review " caught" the error, however,
the process at applied to computer programs needs more stringent adherence.
The impact should be judged on a case by case basis.
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NRC RIV QUADREX REVIEW
FtEFEREldOE DOCUMENT
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ITEM NUPSEP.: 4.2.2.1 (f)
DISCIPLINE: Computer
AGREE WITH FINDING: b In part, see below.
. -
'
DISA&REE WITH FINDING: - -
.
THIS ITEM 15 CONSIDERED TO BE:
REPORTABLE _ .. . . .D
POTENTIALLY kEPORTABLE _ .D
INSUFFICIENT DATA FOR ASSESSMENTQ
NOT REPORTABLE _ _. .. G
'
BASIS FOR ABOVE ASSESSMkNT:
-
.
" Engineering judgement" on interpretation of "significant" changes is too
easily abused. Because of the coglexity of computer programs, even "cos-
metic" changes should require reverification. A case by case assessment
is required for impact. Five options are given for verification. An ordered
priority may be desirable. As it stands, the procedur1 does not limit the
'
process, but allows for more flexible application if needed.
NRC RIV QUADREX REVIEW
REFERINCE DOCUMENT
NO.
.
f
p.# 4
W
*,
- As\
-
_ - . __ -.
.
. . . . . . .
.
'
ITEM NUPBER: 4.3.2.1(a)(R-6)
DISCIPLINE: Electrical /I&C
AGREE WITH FINDING: @ Note 1. . . . . _
DISAGREE WITH FINDING: O
THIS ITEM IS CONSIDERED TO RE:
REPORTABLE _ ... . _ _ _ . .O
POTENTIALLY REPORTABLE . _D
INSUFFICIENT DATA FOR ASSESSMENT Q
NOT REPORTABLE _ _ .. W .
.
~
'
BASIS FOR AB0VE ASSESSMENT:
e -
*
Installation details are not prepared, hence design is incomplete and not
-
1ssued for construction. See 50-55(e) (1) (ii).
NRC RIV QUADREX REVIEW
REFEREf4CE DOCUMEtiT
NO.
!
.
. .
,9 e
'
%) .-_ _ - - . - - . _ - - .
- ._ _ _- - _ _________- _ ________________- ___________________ ______ _______________ _. _____-________ __________-___ ____
. . . . . . . . . - . .
.
. ITEM NUPSER: 4.3.2.1 (b)
N.. .
DISCIPLINE: Electrical /I&C
AGREE WITH FINDING: C -e-
~ ~
1
DISAGREE WITH FINDING: b
THIS ITEM IS CONSIDERED TO BE:
REPORTABLE. ._ _ _ _ _ _.D
POTENTIALLY REPORTABLE _ D
INSUFFICIENT DATA FOR ASSES $MENTQ
NOT REPORTA8LE _ _ . .. W
-
BASIS FOR ABOVE ASSESSMENT:
Requirements are included in separation requirements TRD and safety hazards
analysis TRD. Other documents which addruss separation criteria are 20003
and PE.005.
NRC RIV QUADREX REVIEW
REFERENCE 0000 MENT
tJO.
.
w
.
.
~..~o....
1
.
ITEM NUPSER: 4.3.2.1(c)
DISCIPLINE: Electrical /18C
,
AGIEE WITH FINDING: C .
'
[
DISAGREE WITH FINDING:
THIS ITEM IS CONSIDERED TO BE:
REPORTABLE. .._ _ . _.O
POTENTIALLY REPORTABLE _ . ._ _ D
INSUFFICIENT DATA FOR ASSESSMENT
NOT REPORTABLE.- .WQ
. -
EASIS FOR ABOVE ASSESSMENT:
.
Listings of recuired TRD's for the project appeared in early versions of PRAME
and other project scheduling and planning tools. This listing is dynamic in
nature in that additions and/or modifications to the listing are made depend-
ing on changing project requirements.
-
It is agmed that, in any large design effort, design decisions will be made
for which no documentation exists.
.
NRC RIV QUADREX REVIEW
REFERENCE DOCUMEtiT
NO. V
.
e
**
-
(W+.
b h\
~ . . -.. -. .
.
e
ITEM NUPSER: 4.3.2.1(d)
4
DISCIPLINE: Electrical /I&C
i
AGREE WITH FINDING: C ..
*
~_
,
DISAGREE WITH FINDING: b
THIS ITEM IS CONSIDERED TO SE:
REPORTABLE. _ ._ _ _ . ..D
POTENTIALLY REPORTA8LE _D
INSUFFICIENT DATA FOR ASSESSMENT
NOT REPORTABLE _. . _. QW
BASIS FOR ABOYE ASSESSMENT:
1. Cr[teria document ZQ-003 dees contain separation criteria.
2. Single failure criterion is identified in W P.I.P. for safety systems
provided by W;
3. DC-015 provides methodology for design verification process.
4. SD-005 provides methodology for design assurance review.
_
NRC RIV QUADREX REVIEW
atrtatactyuutt4T
NO. -
.
e
0
*
A61
.
. - ~ ~ - , .
.
.
ITEM NUPSER: 4.3.2,I(e)
DISCIPLINE: Electrical /I AC
AGREE WITH FINDING: C .
2
DISAGREE WITH FINDING:
THIS ITEM IS CONSIDERED TO SE:
-
.
REPORTABLE. .. . _ _ _ ..D
POTENTIALLY REPORTABLE . .
INSUFFICIENT DATA FOR A55E55 MENT
NOT REPORTABLE- - _ _ ..
-
BASIS FOR A80VE ASSESSMENT:
. ..
Separation barrier design requimments appear in the separation requirwents
TRD's EQ-006, ZQ-003, and the safety ha:aros analysis TRD for use by intamal
8&R disignees.
( Separation requirements for vendor-supplied components are included in the
specification by referring appropriate NRC and IEEE guidelines and standards.
Adequacy is assured by the B&R review and approval process.
NRC RIV QUADREX REVIEW
REFCRINCE DOOUMENT
'V
NO.
.
og
...
. _ _ _ _ _ _ _ - _ _ _ _ _ _ _ _ _ _ _ _ _ _
...s...
.
C' ITEM NUMER: 4.3.2.1(f)
(.
D15CIPLINE: Electrical /!AC
:
q AGREE WITH FINDING: C . . . .
DISAGREE WITH FINDIM: b
THIS ITEM IS CONSIDERED TO BE:
REPORTABLE _ . . .O
POTENTIALLY REPORTABLE-
INSUFFICIENT DATA FOR ASSESSMENT
NOT REPORTABLE- -- .
. BAS!$ FOR AB0VE ASSESSENT:
.
Equipment clarification requirements and identification methods appear in
procedure DC-010. TRD ZQ-007 and pmcedure PE-005.
.
NRC RIV QUADREX REVJEW
I;EFER;*NOC DOCUMEf4T
f40.
fbv
(6,
%1
..
.
. . . . . ~ . . . .
.
ff ITEM NUPSER: 4.3.2.1(g)
(.-
DISCIPLINE: Electrical /I&C
O
- ' '
AGREE WITH FINDINE: ~I' *
DISAEREE WITH FINDINE: O
THIS ITEM IS CONSIDERED TO BE:
REPORTABLE _..... _ _ _ _.D
POTENTIALLY REPORTABLE . .D
INSUFFICIENT DATA FOR ASSESSMENT
NOT REPORTA8LE.- . _ _. WQ
-
BASIS FOR ABOVE ASSESSMENT:
. -
Project procedures; SD-005 - Design Assurance
*
SD-004 - Design Review
DC-010 - Codification
DC-015 - Design verification
PE-005 - Electrical Cabling Scheduling
provide a systematic approach to implementation of FSAR comitments and design
changes.
NRC RIV QUADREX REVIEW
REFERENCE DOCUMENT
NO.
.
e
e
b
wi
.
_
_
s .- ~ .- m ... .
.
ITEM NUPSER: 4.3.2.1 (h) ,
DISCIPLINE: Electrical /I&C
AGREE WITH FINDING: C - -
_.
DISAGREE WITH FINDING: b
THIS ITEM IS CONSIDERED TO BE:
PEPORTABLE. ... . _ _ ..O
POTENTIALLY REPORTABLE _ __D
INSUFFICIENT DATA FOR ASSESSMENTD
NOT REPORTA8LE- . _. . 5
-
BASIS FOR ABOVE ASSESSMENT:
.
*
SD-005 (design assurance) and system design dese-iptions identify support
systems.
NRC RIV QUADREX REVIEW
REFERENOE DOCUMENT
-
N O. -
.
e
s .
A6I
. . . . . . , _ . .
.
'
,
'
v , f
/' ITEM MIMER: 4.3.2.1(1)
k.
DISCIPLINE: Electrical /I&C
4
1 AGREE WITH FINDING: h . . .
~
1
DISAGREE WITH FINDING: O
THIS ITEM 15 CONSIDERED TO BE:
REPORTABLE . . ..O
POTENTIALLY REPORTABLE . _D
INSUFFICIENT DATA FOR ASSESSMENT
NOT REP 0RTABLE ' - _ _. WQ
~
BASIS FOR ABOVE ASSES 9ENT:
'
,
,
PQ-005 and EQ-004 provided project-wide basis for environmental conditions
with the exception of p1r.e break analysis. Program for identification and
impact assessment for hign ecergy line breaks outside containment is in pro-
gress. Review program for high energy line breaks will be accelerated.
.
,
i
NRC RIV QUfiOREX REVIEW
telFIR;nCE Do;UMENT
,, NO.
V
<
>
0
9 $
,.'..,
!
*> ,-' f -
~
~
! A6) l ,
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, , , , - - - , .
~ . - . . . . . . , !
.
t >
.
I
ITEM NLMLER: 4.3.2.1 (j)
DISCIPLINE: Electrical /I&C
AGREE WITH FINDING: D -
'
1
'
I
DISAGREE WITH FINDING: ,
' '
THIS ITEM IS CONSIDERED TO BE:
'
< ,
REPORTABLE ...- - _ _ _ _O
POTENTIALLY REPORTABLE ._ .D
INSUFFICIENT DATA FOR ASSESSMENTQ
NOT REPORTABLE _ _ . G
-
BASIS FOR ABO'!E ASSESSMENT:
'
,
Certain engineering specification provisions and requirements grant the vendor
the latitude to adhere to, applicable portions of regulations and standards.
All such vendor actions and decisions are, however, subject to find B&R engineer-
ing review and approval and documented in accordance with D0;004,'" Foreign
Document Processing and Control."
"
N. C RIV QU.^DREX REVIEW
ht.FCRINCE DOCUMEllT
!
NO.
.
e
! ,
-!
l
A61
L
.
. . . . . . .
.
ITEM NUMBER: 4.3.2.1 (k)
DISCIPLINE: Electrical /I&C
,
AGREE WITH FINDING: C
1 -
DISAGREE WITH FINDING:
THIS ITEM IS CONSIDERED TO BE:
REPORTABLE. .._ _ . . .O
POTENTIALLY REPORTABt r ,__D
-
INSUFFICIENT DATA FOR ASSESSMENTD
NOT REPORTABLE._ _. E
'
BASIS FOR ABOVE ASSESSMENT:
.
Licensing, both HL&P and B&R, felt that IEEE 344-1971 plus the Branch Tech.
Position was equivalent to 344-1975, which is the FSAR comitment.
.
NRC RIV QUADREX REVIEW
REFERENCE DOCUMEllT
NO.
.
1.
** YP
AL.)
.
- . . . . . .. .
.
ITEM NUMBER: 4.3.2.1(1)
(c
(j DISCIPLINE: Electrical /I&C
AGREE WITH FINDING: C
' "'
DISAGREE WITH FINDING:
THIS ITEM IS CONSIDERED TO BE:
REPORTABLE _ _ .. . .O
POTENTIALLY REPORTABLE._ D
INSUFFICIENT DATA FOR ASSESSMENT
NOT REPORTABLE- .WQ
*
BASISFORAB0VEASSESSMkNT:
-
.
SDD's contain operations section as a basis for operating-testing procedures.
Design Assurance group reviews all pre.op tes: procedures and B&R has a
nepresentative on the J.T.G.
NT'C RIV QU.5D3EX REVIIW
nLrIttcNCE 000UMs..T
rn. Y
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ITEM NUPEER: 4.3.2.1 (m)
- '
.
..
.
? DISCIPLINE: Electrical /I&C
-
AGREE WITH FINDING: C
DISAGREE WITH FINDING: b *
THIS ITEM IS CONSI E RED TO BE:
REPORTABLE _ _ . . _ _ _ _.D
POTENTIALLY REPORTABLE._ _ ._ _ D
INSUFFICIENT DATA FOR ASSESSMENTQ
*
NOT REPORTABLE- -- _ _ _ .. U
. .
* *
BASIS FOR ABOVE ASSESSMkNT:
-
.
SDD's, Design Assurance, Safety Systems Hazard's Analysis will address access
. for all manual operations under accident conditions.
.
.
.
NRC RW QUADREX REVIEW
HEFERENCE DOOutAEi:T
NO.
.
e
; , b
.,' 40
ALi
.
. ... ..-.
.
ITEM NUMBER: 4.3.2.1(n)
DISCIPLINE: Electrical /I&C
AGREE WITH FINDING: 3
< -
- *
DISABREE WITH FINDING:
THIS ITEM IS CONSIDERED TO BE:
REPORTABLE. .. . ..O
POTENTIALLY REPORTABLE _ _D
INSUFFICIENT DATA FOR ASSESSMENT
NOT REPORTABLE._ ._ .mQ
.
BASISFORABOVEASSESSMhMT:
.
This portion of the electrical design is still in the development stages.
As isolation device design becomes finalized, specific instructions will
be transmitted to designersby project design procedures.
.
NRC Riv QUADREX REVIEW
REF r::;40t DOCUMEIIT
N O.
.
i
'
', l,
.c /
86\
! !
_ _ _ _ _ . . _ _ .
. .
_ , . . . . , . . ....
.
ITEM NUPEER: 4.3.2.1 (o)
DISCIPLINE: Electrical /I&C
ASREE WITH FINDING: C
DISASREE WITH FINDING: b '
THIS ITEM IS CONSIDERED TO BE:
REPORTABLE. ... _.D
POTENTI ALLY REPORTABLE._ ._ _ D
INSUFFICIENT DATA FOR ASSESSMENTQ *
NOT REPORTABLE _ .IB
'
BASISFORABOVEASSESSMkNT:
.
Project procedures do not prohibit one individual from perfortning both check-
ing and design verification actions on a design document, as long as other
personnel selection requirements are met. Refer to procedure DC-015. " Pro-
cedure for Design Verification."
,
NRC Riv QUADREX REVIEW
REFERENCE DOCUMEr4T
f40.
.
w
. . _. . __ .. -_ _ . .
-.
. . _ _ . . . .
.
ITEM NUISER: 4.4.2.1 (a)/(b)
.
DISCIPLIE: . Mechanical /HVAC
,
AGREE WITH FINDING: @
O
-
-
DISASREE WITH FINDING:
THIS ITEM IS CONSIDERED TO BE:
REPORTABLE _ _.._ _ . ..O
POTUTIALLY REPORTABLE._ _ .El
INSUFFICIDT DATA FOR ASSESSMENTD
NOT REPORTABLE . . .D
.
*
BASIS FOR ABOVE ASSES $kNT:
.
-
_
This item is addressed in enclosure 2.
.
4
.
.
NRC RIV QUADREX REVIEW
REFERENCE DOCUMENT
N O.
i
*
!
.
* *
I i
- _
-_--_~__-. _ . - . , , _ . _ . --. . _ - . . _ _ - . . . . . . - _ _ . , _ _ _ _ _ _ _ _ - .
.
7 _ .. ..
ITEM NUptER: 4.4.2.1 (c)
DISCIPLINE: Mechanical /HVAC
AGREE WITH FINDING: h
.
'
'
DISAGREE WITH FINDING: b
THIS ITEM IS CONSIDERED TO BE:
RFIRTABLE .. . . _ _ _ ..D
PC'lINTIALLY REPORTABLE . .D
.
INSUFFICIENT DATA FOR ASSESSMENTQ
NOT REPORTABLE- - ..D
.
'
BASISFORABOYEASSESSMkNT:
.
.
.
Pockets In RCB:
. . , , .
Curmntly, the NRC does not requim other than a homogeneous hydrogen genera-
tion model. Because of the large volume of the STP containment and considering
. the TMI experience B&R does not feel that pocket accumulations of hydrogen
pose a potentially mportable concem.
Battery Room Concentrations: .
The QUADREX concem was an apparent inconsistency between B&R disciplines.
B&R has perfonned a design verified calculation (7A079NC786A) detennining
the hydrogen contantration in the battery rooms. This calculation shows we
are under a 27, concentration.
NRC RIV QUADREX REVIEW
REFERENCE 000uMENT
NO. - ,
.
d
AL)
.wJ - -
9
.
. . . - . .
.
ITEM NLMIER: 4.4.2.1(d)
.-
(
s.. DISCIPLINE: .kchanical/HVAC
AGREE WITH FINDING: @
i
O
__
'
DISAEREE WITH FINDING:
THIS ITEM IS CONSIDERED TO BE:
REPORTABLE. .... ., . . ..D
POTENTIALLY REPORTABLE _ _ __ D
INSUFFICIENT DATA FOR ASSESSMENTQ
NOT REPORTA8LE - .. U
.
* *
SASIS FOR ABOVE ASSESSMkNT:
-
.
.
B&R does not consider this to be reportable as there is a program underway
to study this concem and no significant deficiencies have been detected
5
thus far.
[
(
/
! NRC RIV QUADREX REVIEW
REFEREf40E DOOUMEt4T
f 40.
,
b
46l
l ! k
.
.
ITEM NtMIER: 4.4.2.1(e)
.
.. DISCIPLINE: Mechanical /HVAC
AGREE WITH FINDING: @
i '
.
~ '
__
*
DISAGREE WITH FINDING:
THIS ITEM IS CONSIDERED TO BE:
REPORTABLE. . . . _ . ..O
POTENTIALLY REPORTABLE . _D
INSUFFICIENT DATA FOR ASSESSMENTQ
NOT REPORTABLE - - - - - .U .
'
~
BASIS FOR ABOVE ASSE55MkNT:
.
Proper administrative control on the part of HL&P operations should alleviate
this problem. .,
"Pmgram To Be Established"
A review of the floor drain system will be undertaken. It is not felt that
such leakage could go undetected long enough to cause a significant safety
a
hazard.
.
f1RC RIV QUADREX REVIEW
MFERE!JCE DOCUMEliT
g/
tio. .
.
4 I
5,3 '
.
.
. . . . .
!
.
ITEM NUPSER: 4.4.2.1 (f)
_
EISCIPLINE: Mechanical /HVAC
AGREE WITH FINDING: D _
<
_
DISAGREE WITH FINDING:
THIS ITEM IS CONSIDERED TO BE:
REPORTABLE., .. . _ _ ..O
POTENTIALLY REPORTABLE _. __D
INSUFFICIENT DATA FOR ASSESSMENTD
NOT REPORTABLE _ . D
.
'
BAS!$ FOR ABOVE ASSESSPkNT:
'
No evil $ence that inconsistencies address reportable design deficient items.
B&R Licensing has confirmed that FSAR Change Notice mquests submitted
mcently are of a " component parameter correction" naturi.
r
.
NRC RIV QUADREX REVIEW
REFERNCE DOOUMENT
NO.
.
't,
#
9 ,' * ' e
%\
. _ _ _ _ - . - _ _ . .
. .. . . . . _ . .
.
ITEM NUPSER: 4.4.2.1(g)
C. -
.
Q. DISCIPLINE: Mechanical /HVAC
AGREE WITH FINDING: C
~
DISAGREE WITH FINDING: b '
THIS ITEM IS CONSIDERED TO BE:
REPORTABLE _..._ _ . ..O
POTENTIALLY REPORTABLE .D
INSUFFICIENT DATA FOR ASSESSMENTQ
NOT REPORTABLE .U
*
BASISFORABOVEASSES$PhMT:
.
Written criteria does not establish the adequacy of a design verifier. B&R
,
design verification procedure STP-DC-015, does meet all regulatory requirements.
.
NRC RIV QUADREX REVIEW
REFERENCE DOCUf.iENT
no.
"V
.
O
l
w
*
hM
..
.. . - . . _ _ _ - .- __ - ._ _ -
F
. . , _ _ . . . .
.
ITEM NUPSER: 4.5.2.1(a)
*
DISCIPLINE: Stress Analysis (Piping)
AGREE WITH FINDING: C
DISAGREE WITH FINDING: O -
~
THIS ITEM IS CONSIDERED TD BE:
REPORTABLE _ _ .. . _ ..O
POTENTI ALLY REPORTABLE._ _ _D
INSUFFICIENT DATA FOR ASSESSMENT
NOT REPORTABLE .Q
ID
'
BASIS FOR ABOVE ASSESSMENT:
.
The change in ANSI N176 between 1978 and 1979 changed the angle of jet im-
. pingement effects. This may be cause for re-analysis. This is not a
.
reportable oeficiency since the requirements changed subsequent to design.
Nr.C Riv QUADREX REVIEW
RtrtRENet oo UMEt:T
NO. -
.
k
u . 'il
ALI
.
. . . . . . . . .
.
ITEM NUPSER: 4.5.2.1(b)
(( DISCIPLINE: Stress Analysis (Piping) '
AGREE WITH FINDING: C ,
O
-
-
DISAGREE WITH FINDING:
THIS ITEM IS CONSIDERED TO BE:
REPORTABLE. - .. _ - _ ..D
POTENTIALLY REPORTABLI._ . .D
INSUFFICIENT DATA FOR ASSESSMENT Q
NOT REPORTABLE.- . . .. W .
*
BASIS FOR ABOVE ASSESSMENT:
'
As indicated in the QUADREX assessment to M-8, the approach used by EDS is
conservative.
.
"The simplified approach, but is probably not unreasonable since support from
,
restraints was included".
s.
NRC RIV QUADREX REVIEW
REFERENCE DOCUMENT
no. 7
.
,
4
AW
.
.... --.. ..
.
ITEM NUISER: 4.5.2.1 (c)
e
,
l( DISCIPLINE: Stmss Analysis (Piping)
AGREE WITH FINDING: C .
DISAGREE WITH FINDING: b ' ~
THIS ITEM IS CON 51DE E D TO M:
MPORTABLE. . .. . . ..
POTENTIALLY MPORTABLE . .
INSUFFICIENT DATA FOR ASSESSMENT
NOT EPORTABLE- - - . ..
.
*
SAS!$ FOR AB0VE ASSESSMENT:
.
~
We assumed that the condition whom a pipe loses a support is less severe
than the condition whom a pipe sustains an igact due to rupture of a
-
pipe of equal or smaller size.
NRC RI\* QUADREX REVIEW
REFERENOI 000UMEt?T
NO. 7'
.
e
A to)
.
. . . ... .
ITEM NUPSER: 4.5.2.1(d)
e-
DISCIPLINE: Stress Analysis (Piping)
AGREE WITH FINDING: C
-
_
. -.
{ .
-
,
*
DISAGEE WITH FINDING:
THIS ITEM 15 CDNSIDERED TO BE:
REPORTABLE. ._ _ _ _ _ _.O
POTENTIALLY REPORTABLE .D
INSUFFICIENT DATA FOR ASSES $ MENT
NOT REPORTABLE - --. . . QW
.
'
SASIS FOR ABOVE ASSESSMENT:
'
. .
Verification of the penetrations and much of the high energy piping is still
,
under evaluation.
NRC RIV QUADREX REVIEW
REFEREfJOE DOOUMENT
NO.
.
'
o
) .
au
._
..
.
ITEM NUPSER: 4.5.3.1 (a)
(. N
\,, DISCIPLINE: Piping Stress Analysis -
AGREE WITH FINDING: h .
; . . ..
.
" " ~
D!$ASREE WITH FINDING:
THIS ITEM IS CONSIDERED TO M :
MPORTABLE. - .. . . ..D
POTENTI ALLY REPORTABLE ._ .
INSUFFICIENT DATA. FOR ASSES $ MENT
NOT REPORTABLE .
.
'
BASIS mR ABOVE ASSES $MhMT:
~
.
This effort is presently under way. TRD addressing these co,ncems is being
developed.
l
,
.
NRC RI\* QU.S.DREX REVIEW
h'CFCREf.CE DOCUMENT
ttO. Y
.
q
. .j ( .-
*M
%i
.
. . . . - - .
.
ITEM NUPSER: 4.5.3.1(b)
(,
( DISCIPLINE: Pip 16g Stress Analysis
, AGREE WITH FINDING: @
~
' ~
'
-
DISAGRFE WITH FINDING:
THIS ITEM IS CONSI E RED TO SE:
REPORTABLE. ... . . ..O
POTENTIALLY REPORTABLE._ _ _ _
INSUFFICIENT DATA FOR ASSESSMENT
NOT ACPORTABLE ..
.
*
SASIS FOR ABOVE ASSESSMkNT:
.
No requirement exists for showing Mstraint locations on isoaatrics.
NRC RIV QUADREX REVIEW
ntFEREHOE DOCUMENT
No.
.
a
g 9 0
0
h6\
.
. . . . . . . , .
.
.
ITEM NUPSER: 4.5.3.1(c)
ir**
\
* DISCIPLINE: Piping Stress Analysis 4
AGREE WITH FINDING: C
i .
.
; -
_
' - -
DISAGREE WITH FINDING:
TN15 ITEM IS CONSIDERED 70 SE:
REPORTABLE. .. _ _ ..
POTENTIALLY REPORTABLE . _ _
INSUFFICIENT DATA FOR ASSESSMENT
NOT REPORTABLE ..
.
"
.
SASISFORAB0VEA55E55MkNT:
,
Formalization of analysis methods t.nd procedures is undenvay.
.
.
NRC RIY QUADREX REVIEW
FiEFtREtiCE DOCUV.EfJT
fiO.
.
e
Au
.-
.
_ . . . . . . - - . . .
-
.
ITEM NUMER: 4.5.3.1(d),(e)
<--
1
DISCIPLINE: Piping Stress Analysis
AG EE WITH FINDING: $
< . -
' '
DISAGREE WITH FINDING:
THIS ITEM IS CONSIDERED TO SE:
REPORTABLE . .. . . . ..
POTENTIALLY REPORTABLE .
INSUFFICIENT DATA FOR ASSESSMENT
-
NOT EPORTA8LE . . ..
.
*
SASISFORABOVEASSESSMhMT:
. .
Formalization of analysis methods and procedures is underway.
.
.
.
. NRC RW QUADREX REVIEW
REFERENCE D00VMEtiT
No. Y
,
- e
g P $
.'~ /
b!
.
. . . . . . .
.
ITEM NUPSER: 4.5.3.1 (f)
'
DISCIPLINE: Piping Stress Analysis
AGREE WITH FINDING: C ,
l ~"
OkSAGEE WITH FINDING: b *
THIS ITEM IS CONSIDERED TO BE:
MPORTABLE ..._ _ _ _.
POTENTIALLY REPORTABLE._
INSUFFICIENT DATA FOR ASSESSMENT
NOT REPORTABLE- - .
.
'
SAS!$ FOR AB0VE ASSE55fkNT:
.
In 'our response to M-6 we will consider using dynamic analysis on a " case-
by-case" basis.
v
.
NRC RIV QUADREX REVIEW
REFERENCE OUVENT
N O.
.
q+
G
/n.i
-
1
. . . . . . . . , . .
,
ITEM NUPSER: 4.5.3.1(g)
DISCIPLINE: Fiping Stress Analysis
AMEE WITH FINDING: C ..
-
, . .
*
DISASREE WITH FINDING:
THIS ITEM IS CONSIDERED TO K :
MPORTABLE . .. . ..
POTUTIALLY REPORTABLE . _
INSUFFICIENT DATA FOR A55E55MDT
NOT KPORTABLE ..
,
'
BASIS FOR ABOVE ASSESSMENT:
'
.
Criteria is being developed in a formal docunent to provide consistency.
NP.C RIV QUAD' LEX REVIEW
RCFERCf40E 000VMEt4T
t10,
.
l
A 6l
_
.
.,.. ... ..
.
ITEM NUPSER: 4.5.3.1 (h)
'
,
DISCIPLINE: Piping Stress Analysis
AMEE WITH FINDING: C ,,,
, . . . . . . . __
* *
D!$AGEE WITH FINDING:
THIS ITEM !$ COMs!KED TO M:
EPORTABLE. .. . _ . ..
POTENTIALLY REPORTABLE._ . ._ .
INSUFFICIENT DATA FOR ASSESSMENT
NOT EPORTABLE _ ..
'
BASIS FOR A80VE A55E55fdNT:
.
The EDS criteria is generic.has been appropriately applied to the specific
STP design. -
,
.
NRC RIV QUADREX REVIEW
F.EFER;NOE DOOUMENT
NO.
.
*
*
I
r;-
$bl
,
- ~ '~ -
-
.
. ~ . . ~ . . . .
.
*
l ! !
ITEM NUMER: 4.5.3.1(1)
! DISCIPLINE: Piping St mss Analysis l t
O
'
, AGREE WITH TINDING: ..
, .. .. .. .. .. . . ... .
*
DISASREE WITH FINDING:
l THIS ITEM !$ CONSIDERED TO K: l l
kDORTABLE. . .. .
,
POTENTIALLY REPORTABLE., .
I INSUFFICIENT DATA FOR ASSESSMENT
NOT MPORTABLE .
.
'
BASISFORAB0VEASSESSMkNT:
. .
,
l All system and/or cogonents essential for safe shutdown will be considered '
in the interaction matrix for pipe whip outside containment.
l l \ l ! i '
NRC RIV QUADREX REVIEW
( REFERENCC DCOUMEf4T
t40. Y
! i
.
I I i . ,
,- - - - - - - - - _ _ - - - - - _ - - - - - - ------ ---__ - - - _ - -
. . . .
.
ITEM NUptER: 4.5.3.1 (j)
..
..
DISCIPLINE: Piping Stress Analysis
. ASKE WITH FINDING: C
~
- -
.... .
DISASKE WITH FINDING: -
THIS ITEM !$ CON 51DE E D TO K :
MPORTABLE. . . . ..
POTENTIALLY MPORTABLL. . .
INSUTFICIENT DATA FOR ASSES 5 MENT
NOT MPORTABLE ..
.
"
BA515 FOR ABOVE A15ES$MkNT:
*
.
.
S&R will expand on its response to the bl. linear stiffness question in the
- fernal msponse.
.
C
NRC RIV QUADREX REVIEW
REFERENOE DOCUMENT
*
NO. W
.
e
0
w
.
. . . . . . - ,
.
ITEM NUDGER: 4.5.3.1(k)
.....
[[,
, DISCIPLINE: Piping Stress Analysis
. AGEE WITH FINDING: $
O
'
-
- -
h15ASEE WITH FINDING:
THIS ITEM 15 CONSI M MED *0 K:
EPORTABLE. .. _ _ _.
POTENTIALLY
INSUFFICIENT DATA FORMPORTABLE_
A55E55 _ iiEff
NOT m PORTasLE_ _ _ _ _ _ _ ..
.
'
BA515 FOR ABOVE ASSESSENT:
*
-
. .
Forinalization of analysis methods and procedures are undenvay.
.
.
NRC RIV QUADT!EX REVIEW
REFERENOE 0000 met 1T
N O.
.
e
'
*
r
G
l
w
l l .
.
. . . . . . . .
.
ITEM NUISER: 4.5.5.1 (a)
,..
I
DISCIPLINE: Mechanical /HVAC
w.
:
AGREE WITN FINDING: C
,
t DISAGREE s!TH FIND!d:
-
. . . . .
"" ' '
-
.
THIS ITEM IS CONSIDERED TO BE:
REPORTABLE.. .. _ .. ..D
POTENTIALLY REPORTABLE _
INSUFFICIENT DATA FOR ASSESSMENT
NOT REPORTABLE .
*
BASIS FOR ABOVE ASSESSMENT:
'
.
,
Review of SRP 3.9.3.1.2.f. which deals with operability assurance of active
components, indicates analysis may be used in lieu of testing.
i
NRC RIV QUADREX REVIEW
REFERENCE DOCU?. TENT
NO. V
t .
.
e
%
% $ g
bM
.- _ .. - ._______.- - - - . . - - - _ _ . _. .
.__ -_. - - _ - _ - .-
... . . . . . .
'* ;,- c
.
'
ITEM NUPSER: 4.5.L.1(b)
.
,,
*
j 1 DISCIN..tdE:, Mechanical /HVAC
s
-
>
AGREE WITH FINDING: @ _
. . . -
.
a ,
l -
DISAGREE WITH FINDING:
THIS ITEM IS CONSIDERED TO SE:
REPORTABLE . . . . . . . .O
POTENTIALLY REPORTABLE . .
i INSUFFICIENT DATA FOR ASSES 3 MENT
NOT REPORTABLE- .
.
'
SASISFORABOVEASSESSMbMT:
.
.
~
This situacion will be reviewed as time permits. In our opinion the current
design basis is conservative.
'
B&R does not consider this reportable as the NRC has accepted the STP PSAR.
Changes in their mquimments relative to STP can be addressed. The current
design considering ECCS operation to service level "0" limits meets the
regulatory requirements and is considered to adequately protect the safety
of the public. We consider this to be consistent with other plants near STP
in Licensing status.
NRC RIV QUADREX REVIEW
REFERENCE DOCUMEtli
NO.
,
*
I
.
1
/
/*
.
I
. . . . . . . . ..-
.
ITEM NtPEER: 4.5.5.1(c)
.
DISCIPLINE: Mechanical /HVAC
,
AGREE WITH FINDING: C
j '- .
.-- . .. . We need to perforin our analysis prior to agreeing ~
DISAGREE WITH FINDING: or disagreeing with QUADREX's conclusions,
. .
THIS ITEM IS CDNSIDERED TO BE:
REPORTABLE . _ _ _ ,O
POTENTIALLY REPORTABLE D
INSUFFICIENT DATA FOR ASSESSMENTG
NOT REPORTABLE - . . .. D
*
BASISFORABOVEASSESSMkNT:
-
.
,
B&R sees no evidence that this concem incacts the safety of the public and
therefore, considers it not reportable. There are programs established
which are verifying the seismic and 1E qualification report adequacy.
NRC RIV QUAD?.EX REVIEW
REFERENCE COOUMENT
N O.
.
'e
< A61 l l l
- - - . _ _ _ . ___ ___ _ _
- . . , , . . , . . .
. 4
?
...
ITEM NUMBER: 4.5.5.1(d)
.
C.7~-
_
DISCIPLINE: Mechanical /HVAC
. AGREE WITH FINDING: C ,
. . . ~ .. , . .t >
.. ~ . . . . . .. _
:,
- * *
DISAGREE WITH FINDING:
THIS ITEM IS CONSIDERED TO BE:
REPORTABLE _ .._ _ _ _ _ _ . O
POTENTI ALLY REPORT;GLE . _. _ D
INSUFFICIENT DATA FOR ASSESSMEhiQ *
NOT REPORTABLE _. _ . G
.
*
BASISFORABOVEASSESSMkNT:
-
.
.
The vent piping is non-safety rtlated. In any event the safety classification
of the calculation will not be reportable. QUADREX' assessment of the calcu-
lation shows the calculation to be adequate.
NRC RIV QUADREX REVIEW
REFERENCE DOCUMENT
NO.
.
.
'/J
.
'
~ k,E -
.
,
-
, - - .
m. w .. . ~ . . .
ITEM NUPSER: 4.5.5.1 (e)
DISCIPLINE: Mechanical /HVAC
{r - ,
AGREE WITH FINDINE: C ..
, . : .- - .
.
. . . . . .- . -
"
DISASREE WITH FINDING:
THIS ITEM IS CONSIDERED TO BE:
REPORTABLE., .. _ _ _ _.D
POTENTIALLY REPORTABLE._ _. D
INSUFFICIENTDATAFORASSES$MENTp .
NOT REPORTABLE _ . U
*
BASIS FOR ABOVE ASSESSMkNT:
~
We disagree that there was even confusion here. Personnel training, in any
,
event is not a reportable deficiency.
.
NRC P.lv QUADREX REVIEW
REFERENCE DOOUV.ENT
"
. NO.
.
5
e
2.
v,M7C
%I
.
_ _
..s-. .
ITEM NUMBER: 4.5.5.1(f)
,e .
( DISCIPLINE: Mechanical /HVAC
AGREE WITH FINDING: C ..
-
.
. ,. . u. . , . .~. .-
.
- '
' ,.
DISAGREE WITH FINDING:
THIS ITEM IS CONSIDERED TO BE:
REPORTABLE. ..._ _ _ _ _ . O
POTENTIALLY REPORTABLE._ ._ _D
.
INSUFFICIENT DATA FOR ASSESSMENTQ
NOT REPORTABLE- -_ _ _.D
BASIS FOR ABOVE ASSESSMhMT:
-
Qualification of equipment will be subject to independent audit by NRC re-
viewers. This concem is not considered reportable because while NRC has
not officially sanctioned this document, they are not expected to have signi-
ficant problems with its procedures.
NRC RIV QUADREX REVIEW
REFERENCE DOCUMEliT
NO.
.
T
,
-
,-
- -
--
. . .. . . . . .
.
ITEM NUMBER: 4.5.5.1(g)
r -
% DISCIPLINE: 2
Mechanical /HVAC
.
AGREE WITH FINDING: C _.
-
. . . -
* - "-
DISAGREE WITH FINDING:
THIS ITEM IS CONSIDERED TO BE:
REPORTABLE _ _ .. . . . O
POTENTIALLY REPORTA8LE _ ._ D
INSUFFICIENT DATA FOR ASSESSMENT
NOT REPORTABLE _ ~ .n
Q
.
'
BASIS FOR ABOVE ASSESSMENT:
-
.
This was the subject of an IRC meeting and has already been found not reportable.
NRC RIV QUADREX REV:EW
RIFERENCE DOCUMENT
'
NO.
.
p
1 !
I l' ,
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. - , , , , - . . .
-
r-- - - - - - - - - - - - - n--.w -
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ITEM NUPBER: 4.6.2.1 (a) Item 1
i f'
DISCIPLINE: Nuclear Analysis
AGREE WITH FINDING: h -
. -: -
.
.
.. . .. .
. . . ,- ..
~~
DISAGREE WITH FINDING:
THIS ITEM IS CONSIDERED TO BE:
REPORTABLE _ ._ _ _ _ . . D
POTENTIALLY REPORTAB1F _ D
INSUFFICIENT DATA FOR ASSESSMENTQ
NOT REPORTABLE _ _ .W
.
*
BASIS FOR ABOVE ASSESSMhMT:
-
.
Nuclear Analysis has not reviewed as to hu other disciplines use trans-
mitted information in their design. te-
.
NRC RIV QUADREX REVIEW
REFERENCE DOCUMENT
NO. _
I
.
.
.
#
A6l
.
- - - - - - - - - .
-- -- - --- - - - , - - , --...,-.p.-, ,, y,---- . - . , ,,-...c- -- , - - . , - - - . -
.
,....,.. ..
ITEM NUMBER: 4.6.2.1 (a) Item 2
DISCIPLINE: Nuclear Analysis
AGREE WITH FINDING: O _
.
.. . .
.
_
-
DISAGREE WITH FINDING:
THIS ITEM IS CONSIDERED TO BE:
*
REPORTABLE ._ _ _ _ _ . D
POTENTIALLY REPORTABLE._ D
INSUFFICIENT DATA FOR ASSESSMENT D
NOT REPORTABLE _. _. 5
.
*
BASIS FOR ABOVE ASSESSMENT:
*
.
Saturation temperatures are used if applicable. Otherwise, actual temperature
to evaluate the equipment / structure response. Se example provided in response.
See QUADREX question N-1, Figures N-1-F and N-1-H.
s
NRC RIV QU/,DP.EX REVIEW'
I:EFERE!CE C00UMEl:T
NO.
.
! !
l l
;:. a
,
i j AW i
_
+ , - , - ----e., -- ___,n-w-_ ,. ., , -
___
v ,ww - 4
, . . . . . - ~ . .
.
ITEM NUMBER: 4.6.2.1 (b) ltem 1
,e
DISCIPLINE: Nuclear Analysis
4
AGREE WITH FINDING: C
* *
'
'*
g, r . .. . .. .
THIS ITEM IS CONSIDERED TO BE:
REPORTABLE ..._ _ _ _ _ _.O
POTENTIALLY REPORTABLE _ _. D
INSUFFICIENT DATA FOR ASSESSMENTQ
NOT REPORTABLE- - . .. W
*
BASISFORABOVEASSESSMkNT:
.
Agreew'ith respect to Question N-13. Disagree with response to Question N-1,
. because, NUS model is correct but developed to produce conservative results.
.
NRC RIV QUADREX REVIEW
REFEREt40E DOCUMEtiT
. NO.
.
t
.?
A Li
. , . ~ . . . - . .
ITEM NUPEER: 4.6.2.1 (b) Item 2
( DISCIPLINE: Nuclear Analysis
v,
AGREE WITH FINDING: $
sj . . .
.
- -
._
DISAGREE WITH FINDING:
THIS ITEM IS CONSIDERED TO BE:
REPORTABLE . ._ _ _ _ .O
POTENTIALLY REPORTABLE._ __ _ D
INSUFFICIENTDATAFORASSESSMENTQ
NOT REPORTABLE - .U
*
BASISFORABOVEASSESSMkNT:
-
.~
Analyses outside containment for environment are currently being performed.
No reportable deficiency because of lack of adequate information.
.
.
NRC RIV QUADREX REVIEW
RZFCRIf40 DOOUMENT
tio.
'
.
m
S
g
]
Au
..
,. - , . - - - . - , _ - . --.9, -
- . , - - - _ .---------,----% .- -% .
, -,.m ,, .,-,w---_,m-- y,
. -
7 o.wo. .. ..
ITEM NUPSER: 4.6.2.1 (b) Item 3
DISCIPLINE: Nuclear Analysis -
,
AGREE WITH FINDING: C ..
~
- . -
I .. r . . . . .
.-
' * *
DISAGREE WITH FINDING: .
.
THIS ITEM IS CONSIDERED TO SE:
REPORTABLE .._ _ _ . .D
POTENTIALLY REPORTABLE . D
INSUFFICIENT DATA FOR ASSESSMENTQ
NOT REPORTABLE _ - - .U
.
*
BASISFORAB0VEASSESSMkNT:
- Agree to the extent that some calculations have deficiencies reported in the
, question above. But no adverse impact on the design of safety structures
or systems have been identified.
'
NRC RIV QUADREX REVIEW
REFEREr40E DOCUMENT
t40. S
.
a
*
A L,\
_-
-m , ---,-m- - - , - . _ , - ,
.
, . ~ . .. .
ITEM NUMBER: 4.6.2.1(c)
,-
*
DISCIPLINE: Nuclear Analysis
AGREE WITH FINDING: C .
' ' " '^
O
'
- -
DISAGREE WITH FINDING:
THIS ITEM IS CONSIDERED TO BE:
REPORTABLE .. _ _ _ _ ..D
. ._ _ D
'
POTENTIALLY REPORT 4BLE
INSUFFICIENT DATA FOR ASSES $ MENT
NOT REFORTABLE - ..Q p
BASISFORABOVEASSESSMkNT:
'
Disagree, except for environmental qualification data. Other analysis have
been scoped and perfonned on a reasonable project schedule calculations are
being revised to alleviate deficiencies.
NRC RIV QUADREX REVIEW
F1CFERENCE DOCUMCf.T
NO.
.
9
' ,
AM .e
... ....
.
ITEM NUPEER: 4.6.2.1 (d)
%
DISCIPLINE: Nuclear Analysis
B
AGREE WITH FINDING: C .
l - - ' . ~ ~v aan. .- r-
.
-
-
THIS ITEM IS CONSIDERED TO BE:
REPORTABLE .. . . .O
POTENTIALLY REPORTABLE _ _ _ D
-
INSUFFICIENT DATA FOR ASSESSMENTD
NOT REPORTABLE _ _ .G
.
*
BASIS FOR AB0VE ASSESSMkNT:
.
Example is provided in response to question.N-I figure N-I-G and N-I-H.
are the evidence of support other disciplines . n
.
NRC RIV QUAD.'i2X REVIEW
REFERE'lCE Docuygtgy
tIO. il
.
-
AM
_
.
. . . . . . .
.
ITEM NUMBER: 4.6.2.1 (e)
g
(; - DISCIPLINE: Nuclear Analysis
AGREE WITH FINDING: @
.
, . . . , . . . _
" '
DISAGREE WITH FINDING:
THIS ITEM IS CONSIDERED TO BE:
REPORTABLE. .._ _ _ _ .O
POTENTIALLY REPORTABLE _ _. D
INSUFFICIENT DATA FOR ASSESSMENTE
-
NOT REPORTABLE.- _ _.6
*
BASISFORABOVEASSESSMkNT:
.
For the sake of consistency with analysis perforned at early FSAR stage the
usage of RELAP3 was continued. Current analyses are performed using C0t@ARE
for subcompartnent analysis. No reportable deficiency.
,
NRC RIV QUADREX REVIEW
REFEREr4CE DOCUMENT .
f40.
.
.n'.
}k
%I
.-
__.
.
. . . . . . . . ..
,
ITEM NUPSER: 4.6.2.1 (f)
f'i'
(:, DISCIPLINE: Nuclear Analysis
AGREE WITH FINDING: C
- . . .
. - , .._
' '
DISAGREE WITH FINDING:
THIS ITEM IS CONSIDERED TO SE:
REPORTABLE. .._ _ _.O
POTENTIALLY REPORTABLE _. D
INSUFFICIENT DATA FOR ASSESSMENTQ
NOT REPORTABLE _.W
.
'
BASIS FOR ABOVE ASSESSMENT:~
Please review the response to the question N-8.
.
C
NRC RIV QUADREX REVIEW
REFEREf4 DOCUMEf1T
NO.
.
/
#
A
- [.'le
h L,l
_.
._. . .
- - _ . .. -- _ ._ -. . ._
.
. .. .... .
O
ITEM NUMBER: 4.6.2.1 (g)
s
: DISCIPLINE: Nuclear Analysis -
a:.
AGREE WITH FINDING: @ _,
- . . ..
- . ,, ,. _
' DISAGREE WITH FINDING:
THIS ITEM IS CONSIDERED TO BE:
REPORTABLE .._ _ . _ _.D
POTENTIALLY REPORTABLE._ D
INSUFFICIENT DATA FOR ASSESSMENTQ
NOT REPORTABLE- .W
'
BASIS FOR ABOVE ASSESSMENT:
.
No long term environ-?. ital analysis have been done outside containment. Any
impact of the make-L/ water supply will be evaluated.
NRC RIV QUADREX REVIEW
REFERENCE DOOUMENT
N O.
.
.
.
.
. . ~ . ~ . .
-
.
ITEM NtHIER: 4.6.2.1 (h)
,...
DISCIPLINE: Nuclear Analysis
AGREE WITH FINDING: C ,
DISAGREE WITH FINDING: b
THIS ITEM IS CDNSIDERED TO SE:
REPORTABLE. ._ _ _ _ _ _.O
POTENTIALLY REPORTABLE._ _D
INSUFFICIENT DATA FOR ASSESSMENT
NOT REPORTABLE .. Q
W
.
*
BASIS FOR ABOVE ASSESSMkNT:
.
. Disagree. However, we take the statement under advice.
NRC RIV QUADREX REVIEW
REFERENCE DOCUMENT
no. V
.
w
._ _
. __
.
. . . . . . _ - .
ITEM NUMBER: 4.6.2.1(1)
( '- Nuclear Analysis
( ", DISCIPLINE:
AGREE WITH FINDING: C
' ' ' "
DISAEREE WITH FINDING: O - - -
THIS ITEM IS CONSIDERED TO BE:
REPORTA8LE. ... . _ _ _ _.O
POTENTI ALLY REPORTABLE._ _ _ _D
INSUFFICIENT DATA FOR ASSESSMENT
NOT REPORTA8LE- _ _ _ _ .. Q
U
.
'
BASIS FOR ABOVE ASSESSMkNT:
'
. .
I
See response to the question h, above.
,
NRC RIV QUADREX REVIEW
REFERENCE DOCUMENT
NO.
.
9
.
. , .
%l
.
r - ,-- -..r,--- -- r- --
- , , . - - - - - - - - - - - - - .
- -, , , ,- - . - - - - -
m._.... ..
ITEM NUMBER: 4.6.2.1 (j)
-
DISCIPLINE: Nuclear Analysis
AGREE WITH FINDING: @ ..
; - _
-
-
,
DISAGREE WITH FINDING:
THIS ITEM IS CONSIDERED TO BE:
REPORTABLE .._ _ _ _ _ .D
POTENTIALLY REPORTABtr , ,_ ,, p
INSUFFICIENT DATA FDR ASSESSMENTD
NOT REPORTABLE _. . _, E
'
BASIS FOR ABOYE ASSESSMkNT:
~
.
~
. Agtte, however double ended break was used for short tem subcompartment
analysis for conservative pressure differential evaluation. cCalculations
are being revised using split type of breaks. .
NRC RIV QUADREX REVIEW
, REFERENCE DOCUMENT
V
NO. -
.
e
's.;t.)
kU
.
_ , , _ _ __
. - - - _ ---
.
. . . . . ~ . . . .
O
ITEM NUPSER: 4.6.2.I (k)
'
,,
DISCIPLINE: Nuclear Analysis
AGREE WITH FINDING: $ ,_.
.
, . . .
. -
DISAGREE WITH FINDING:
.
THIS ITEM IS CONSIDERED TO BE:
REPORTABLE. .. . _ _ .O
POTENTIALLY REPORTABLE._ _ D
INSUFFICIENT DATA FOR ASSESSMENTQ
NOT REPORTABLE._ - _ . E
.
'
BASIS FOR AB0VE ASSESSMkNT:
~
- See response to question b.
.
7
NRC RIV QUADREX REVIEW
l REFCRINCE DOCUMENT
NO.
! l l ! ! 1 = l i l ! l
.
; .-
l l
b
1 I !
. -. _ .- .- - _. ___- . . __
.-
. . . . . . . . . .
.
ITEM NIABER: 4.6.2.1 (1)
,.-
k DISCIPLINE: Nuclear Analysis
AGREE WITH FINDING: C .
j . .. . ... .... _
.,
_
DISASREE WITH FINDING: .b
THIS ITEM IS CONSIDERED TO BE:
REPORTABLE ..._ _ _ _ _ _.O
POTENTIALLY REPORTABLE _. _D
INSUFFICIENT DATA FOR ASSESSMENTQ
NOT REPORTABLE . _. D
.
'
BASIS FOR AB0VE ASSESSMENT:
~
The da'ta reported in SDD 4E010EQOO4-A is based on analytical results.
. As regards the usage of data for design of equipment, Nuclear Analysis
was not directly involved.
.
NRC RIV QUADREX REVIEW
REFERENCE DOCUMENT
N O. Y
.
t
&
P
.
_... ... .
ITEM Nt#EER: 4.6.2.1(m)
DISCIPLINE: Nuclear Analysis
AGREE WITil FINDING: $ _.
; . .
. .- . .
-
DISA&REE WITH FINDING: .. O
THIS ITEM IS CONSIDERED TO BE:
REPORTABLE. .. _ _ _ . .O
POTENTIALLY REPORTABLE._ _ _D
INSUFFICIENT DATA FOR ASSESSMENTQ
NOT REPORTABLE- - - _ - _ _ .. G
*
BASIS FOR ABOVE ASSESSMkNT:
Initial conditions for the accident analysis of the ECP are conservative in
all cases and may not reflect anticipated nomal operating conditions. ECP
-
temperatures as calculated by the CP217CM/SAFEC00L compoter codes are 30%
conservative when compared to the CW519 computer code. The LOCA case and
the simultaneous safe shutdown of both units has been analyzed as requirtd
by Regulatory Guide' 1.27. The worst I-day and worst 30-day periods of me-
teorological record in the region resulting in minimum heat transfer to the
atmosphere were applied. These analysis are in the process of being finalized.
NRC illV QUADREX REVIEW
REFEREtiCE COCUMEt;T
NO.
W
.
.
e
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ITEM NUPSER: 4.6.2.1(n)
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DISCIPLINE: Nuclear Analysis j
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AGREE WITH FINDING: $ ,,
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DISAGREE WITH FINDING:
THIS ITEM IS CONSIDERED TD BE:
REPORTABLE. ._ _ _ _ _.O
POTENTIALLY REPORTABLE._ _ _ D
INSUFFICIENT DATA FOR ASSESSMENTQ
NOT REPORTABLE- .W
.
BASISFORABOYEASSESSMkNT:
-
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*
.
.
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NRC RIV QUADREX REVIEW
REFERENCE DOCUMENT
NO. 7/
.
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. . . . - . . . . .
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ITEM NUMBER: 4.6.2.1 (o)
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( DISCIPLINE: Nuclear Analysis
AGREE WITH FINDING: h
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-
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DISA&REE WITH FINDING: .O -
THIS ITEM IS CONSIDERED TO BE:
REPORTABLE.- . . ..D
F3TENTIALLY REPORTABLE . _ D
INSUFFICIENT DATA FOR ASSESSMENT D
NOT REPORTABLE .. E
BASIS FOR ABOYE ASSESSMkNT:
-
Agree.-however we are in a process of developing a technique for analyzing
localized consentration of hydrogen inside the battery room and other areas.
_
NRC RIV QUADREX REVIEW
REFERINCE DOCUMENT
NO.
.
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4
ITEM NUPEER: 4.6.4.1(a)
.-
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DISCIPLINE: Mechanical /HVAC
...
.
AGREE WITH FINDING: @
DISASREE WITH FIN 0!NG: O - - - - - -
T'
THIS ITEM 15 (XRSIDERED TO BE:
REPORTABLE _ _ .. _ _ _ . O
POTENTIALLY REPORTABLE._ _ D
INSUFFICIENT DATA FOR ASSESSMENTQ
NOT REPORTABLE- .G
. .
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BASIS FOR ABOVE ASSESSMkNT:
.
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We appreciate the compliment. The requested FIEA will be developed as part
of the review described in 5D-005. .s
NRC RIV QUADREX REVIEW
REFERCNCE DOCUMENT
NO. 1'
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ITEM Nt#BER: 4.6.4.1(b)
-
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DISCIPLINE: Mechanical /HVAC
AGitEE WITH FINDING: b- .
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DISA&REE WITH FINDING:.. O
THIS ITEM IS CONSIDERED TO BE:
REPORTABLE. ... . _ _ _ _.D
POTENTIALLY REPORTABLE._ _ _ _ D
INSUFFICIENT DATA FOR ASSESSMENTQ
NOT REPORTABLE- _._ _ _ _ _ ..I3
.
BASISFORABOVEASSESSMkNT:
. .
The classification of the calculation will not affect results. QUADREX has
,
confirmed the adequacy of the design so this is not mportable.
NRC RIV QUADREX REVIEW
REFERINCE 03CUMENT
no. V
.
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ITEM NUER: 4.6.4.1 (c)
DISCIPLINE: Mechanical /HVAC
AGREE WITH FINDING: C _
DISAGREE WITH FINDING: b ~
THIS ITEM 15 CONSIDERED TO BE:
REPORTABLE _ . . _ _ _ .O
POTENTIALLY REPORTABLE _ _ D
INSUFFICIENT DATA FOR ASSESSMENTQ
NOT REPORTABLE- - _._ _ . U
.
BASIS FOR ABOVE ASSESSMkNT:
-
.
We will prepare requisite FEMA's. SD-005 describes the B&R program which
.
will establish the FMEAs. Establishment of FMEA will not impact the safety
of the plant.
.
.
NRC RW QUADREX REVIEW
REFEREf<CE DOCUMEflT
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ITEM NUMBER: 4.7.2.1 (a)
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DISCIPLINE: Piping Stress Analysis
AGREE WITH FINDING: C .
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DISAGREE WITH FINDING:
THIS ITEM IS CONSIDERED TO BE:
REPORTABLE ... _ ..D
POTENTIALLY REPORTABLE._ _ _D
INSUFFICIENT DATA FOR ASSESSMENT
NOT REPORTABLE _ - ..Q Eu
.
'
BASIS FOR ABOVE ASSESSMENT:
,
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FSAR will be corrected.
.
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NRC RIV QUAD?EX REVIEW
REFER;r;0E COCUME!!T
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DISCIPLINE: Piping Stress Analysis
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AGREE WITH FINDING: C
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THIS ITEM IS CONSIDERED TO BE:
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REPORTABLE _ .._ _ - _ .D
POTENTIALLY REPORTAgt r ,, _ _ D
INSUFFICIENT DATA FOR ASSES $MENTQ
NOT REPORTABLE - - - - - _. U
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BASIS FOR ABOVE ASSESSMENT:
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It is B&R's responsibility to change the FSAR. Changes affecting the EDS
scope of work are brought to their attention as requirid.
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REFERENCE DOCUMEf4T
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ITEM NUMBER: 4.7.2.1 (c)
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.[ DISCIPLINE: Piping Stress Analysis
AGREE WITH FINDING: C See Below. , , ,
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DISAGREE WITH FINDING:
THIS ITEM IS CONSIDERED TO BE:
REPORTABLE ..._ _ _ _ _ _.D
POTENTI ALLY REPORTASLE _ _ _ D
INSUFFICIENT DATA FOR ASSESSMENTD
NOT REPORTABLE _. _ _ _ .. D
'
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84R will evaluate the need for revising the FSAR. k
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ITEM NUMBER: 4.7.2.1 (d)
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DISCIPLINE: Piping Stress Analysis
+
AGREE WITH FINDING: C .
. . .a. ' ,- -
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.
'
'
DISAGREE WITH FINDING: .b
' '
THIS ITEM IS CONSIDERED'TO BE:
REPORTABLE _ _ . _ _ _ _ _ _.D
'
POTENTIALLY REPORTABLE._ _ _._ D
INSUFFICIENT DATA FOR ASSESSMENTQ
NOT REPORTABLE._ _ - _ _._ _ .. D
*
BASIS FOR ABOYE ASSESSMkNT:
.
The threshold stiffness valves supplied by B&R are minimum valves above
wnich piping analysis risults will not be significantly afficted.
.
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ITEM NLMIER: 4.7.2.1(e)
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AGREE WITH FINDING: )
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DISAGREE WITH FINDING:
THIS ITEM IS CONSI ERED TO BE:
REPORTABLE _ .. . ..D
POTENTIALLY REPORTABLE._ ._ D
INSUFFICIENT DATA FOR ASSESSMENTQ
NOT REPORTABLE- ._ . U -
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BASIS FOR ABOVE ASSESSMENT:
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Applicability of MEB-6 to the STP is under discussion.
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ITEM NUMBER: 4.7.2.1(f)
DISCIPLINE: Piping Stress Analysis
AGREE WITH FINDING: C ~See Below. .
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._
DISAGREE WITH FINDING:
THIS ITEM IS CONSIDERED TO BE:
REPORTABLE. ._ _ . . . O
POTENTIALLY REPORTABtF _ _. D
INSUFFICIENT DATA FOR ASSESSMENTQ
NOT REPORTABLE.- -.- - .X3
.
BASIS FOR ABOVE ASSESSMhMT:
B&R will evaluate the need for revising the FSAR.
.
7
NRC Rty QUADREX REVIEW
REFERENCE DOCUf/,ENT
7,/ _
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_ _ - -.. _ _ - . - - . - .
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ITEM NUPSER: 4.7.3.1 (a)
DISCIPLINE: Piping Stress Analysis
AGREE WITH FINDING: @ ,
O
' --
DISAGREE h!TH FINDING:
-
THIS ITEM IS CONSIDERED TO BE:
REPORTABLE _ .._ _ _ _ _ _ . O
POTENTI ALLY REPORTABLE._ _ _. _ D
INSUFFICIENT DATA FOR ASSESSMENTD
NOT REPORTABLE- . _ _ _ _ _. 5
.
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BASIS FOR ABOVE ASSESSMkNT:
.
Fonnalization of analysis methods and procedures are under development.
.
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NRC Rty QUADREX REVIEW
RC7gagn0E DOCWENT
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ITEM NUMBER: 4.7.3.1(b)
DISCIPLINE: Piping Stress Analysis i
AGREE WITH FINDING: @ _
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-.
O
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DISAGREE WITH FINDING: .
THIS ITEM IS CONSIDERED TO BE:
REPORTABLE ..._ _ _ _ _ _.D
POTENTIALLY REPORTABLE _ D
INSUFFICIENT DATA FOR ASSESSMENT
NOT REPORTABLE _. . .. QU
* *
BASIS FOR ABOVE ASSESSMENT:
.
-
In those instances where operating temperatures cannot be detemined from the
500, the infomation is formally requested from the system engineer.
-
9
i
NRC RIV QUgongx REV EW
REFERINCE DOCUMENT
no. -
Y- ~
L-
.
9
7
'
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ITEM NLDBER: 4.7.3.1 (c)
.. ,
; DISCIPLINE: Piping Stress Analysis
AGREE WITH FINDING: C ,,
.. . . ,
. . . . . _
' '~ ~ '
DISASREE WITH FINDING:
THIS ITEM IS CONSIE RED TO SE:
REPORTABLE _ .. . _ _ _ .O
POTENTIALLY REPORTAgtr ,__g
INSUFFICIENT DATA FOR ASSESSMENTQ
NOT REPORTABLE- .. G
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BASISFORABOVEASSESSNNT:
.
B&R procedums agree with the FSAR and provide more detailed information.
1
NRC RW Q DOCUfAUIT
REFER
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. . . . _ _ . -. . _ -- - -
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ITEM NUISER: 4.7.3.1 (d)
.c .
'b DISCIPLINE: Piping Stress Analysis
AGitEE WITH FINDING: C See Below.
< .. ., . ,. . . . . . - .
* * '
DISAGitEE WITH FINDING:
THIS ITEM IS CONSIDERED TO BE:
REPORTABLE _.... . _ . .O
POTENTIALLY REPORTABLE._ _ D
~ INSUFFICIENT DATA FOR ASSESSMENTQ
NOT REPORTABLE ..M
.
*
BASISFORAB0VEASSESSNNT:
.
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There exists new procedures to review the overall system designs.
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ITEM NUMBER: 4.7.3.1 (e)
DISCIPLINE: Licensing
AGREE WITH FINDING: C No position .
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DISAGREE WITH FINDING: .
THIS ITEM IS CONSIDERED TO BE:
REPORTABLE _ . . _ _ _ _ ..O
POTENTI ALLY REPORTABL*_ __ _D
INSUFFICIENT DATA FOR ASSESSMENTQ
NOT REPORTABLE .U
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BASIS FOR ABOVE ASSESSMkNT:
.
.
E qualifies equipment to " umbrella" parameters. B&R confirins that plant-
specifit calculated parameters for adverse environments do not exceed the
E "uerella" qualification parameters.
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ITEM NUMBER: 4.7.3.1 (f)
_
. .. DISCIPLINE: Piping Stress Analysis
:
AGREE WITH FINDING: $ _
. . . . . . . . ., .
.. _
4. * * *
DISAGREE WITH FINDING:
THIS ITEM IS CONSIDERED TO BE:
REPORTABLE _ .._ _ . .D
POTENTIALLY REPORTABLE._
INSUFFICIENT DATA FOR ASSESSMENT
NOT REPORTABLE- .
.
SASIS FOR ABOVE ASSESSMENT:
-
.
FSAR will be corrected.
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ITEM NIMIER: 4.7.3.1(g)
, DISCIPLINE: Pipe Support Design ' '
. AGREE WITH FINDING: C ,,_
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- . . : .. .. .-
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DISAGREE WITH FINDING:
THIS ITEM IS CONSIDERED TO BE:
REPORTABLE _ _ ._ _ _ _ _.O
POTENTIALLY REPORTABLE __D
INSUFFICIENTDATAFORASSESSMENTD
NOT REPORTABLE - .. U
'
BASIS FOR ABOVE ASSESSMhMT:
. -
Decision to ignort SEE SAM loads as primary loads is in accordance with cur-
rent ASME philosophy.
.
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ITEM NUPSER: 4.7.3.1(h)
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AGREE WITH FINDING: C .
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DISAGREE WITH FINDING:
THIS ITEM IS CONSIDERED 70 SE:
REPORTABLE .._ _ _ ..D
POTENTIALLY REPORTABLE _. _ _ D
INSUFFICIENTDATAFORASSESSMENTQ
NOT REPORTABLE - .U
.
SASIS FOR ABOYE ASSESSMENT:
-
.
Response to F-21 indicates that B&R is considering FW hansner.
.
.
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NF.C RI'l QUACI' X R
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ITEM NUPSER: 4.7.3.1(1)
. .s
C$ DISCIPLINE: Piping Stress Analysis
. AGREE WITH FINDING: C -
-
- -
,, y , ,7,,,,,,. 3 . . . .
THIS ITEM IS CONSIDERED TO BE:
REPORTABLE _ .... . . ..D
POTENTIALLY REPORTABLE._ _ .D
INSUFFICIENT DATA FOR ASSESSMENTD
NOT REPORTABLE - - --. .. U
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BASIS FOR ABOVE ASSESSMENT:
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ITEM NUPSER: 4.7.3.1 (j )
..
DISCIPLINE: Pipe Suppor*. Design
.
AGREE WITH FINDING: C ,,
-
, . . . . .
.. .
-' ~
DISAGREE WITH FINDING: .
THIS ITEM IS CONSIDERED TO BE:
REPORTABLE _ .. ..O
POTENTIALLY REPORTABLE._ D
- INSUFFICIENT DATA FOR ASSES $ MENT
NOT REPORTABLE.- - .QD
.
*
BASIS FOR ABOVE ASSES $MhMT:
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Methods and procedures are consistent with industry practice.
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ITEM NLMIER: 4.7.3.1(k)
'
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DISCIPLINE: Pipe Support Design
AGREE WITH FINDING: C ,.
.
, ., ._
- -'
DISAGREE WITH FINDING:
THIS ITEM IS CONSIDERED TO BE:
REPORTABLE _ _ .. . _ ..O
PDTENTIALLY REPORTABLE._ _
INSUFFICIENT DATA FOR ASSESSMENT
NOT REPORTABLE - _ .
.
*
BASIS FOR ABOVE ASSESSMkNT:
~
Methods and procedures are consistent with industry practice. -
.
.
NRC RW QUADREX REVIEW
RtrtRINCg COCUMENT
d
No. __
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ITEM NUMBER: 4.8.2.1(a)
s
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,
DISCIPLINE: Electrical /I&C
'
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AGREE WITH FINDING: C _.
~-- .. ..
... . _. ;. , , . -;. .
DISAGREE WITH FINDING: O
THIS ITEM IS CONSIDERED TO BE:
REPORTABLE. .. . _ .D
POTENTIALLY REPORTABLE _ _ D
INSUFFICIENT DATA FOR ASSESSMENTQ
NOT REPORTABLE- .U
.
*
BASIS FOR AB0VE ASSESSMENT:
~
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See 4.3.2.1 (a)
-
.
-
NRC RIV QU.*,DREX REVIEW
REFERE!40E DOOUMENT
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ITEM MLSSER: 4.8.2.1-(b)
-
i
' DISCIPLINEi Nuclear Shielding Discipline ..
l ' "'
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--
-
' .- '
MREE WITH YINDING: . . .
-
see below
DISAGREE WITH FINDING:
TH15 ITEM 15 CONSIDERED TO BE:
REPORTABLE ._.-. _ . .
POTENTIALLY REPORTABLE .
INSUFFICIENT DATA FOR ASSESSMENT
NOT REPORTABLE _. --
. .
'
,
BASIS FOR AB0VE ASSES $ POT:
,
.
.
; This statement is partially correct. Procedure DC-016 states in Section 2.2.1,
"The EPM.....who is qualified.....to conduct the ALARA review." The procedure
^
recognizes the need for qualified engineers, however, a separate procedure listing
spec 1fic qualification requirements i.e. number of years of experience, levels
of training etc. has not been develo, ped. The statements regarding design
drawing sign-off and follow-up are partially correct. The documents, including
.l
drawings, that require ALARA review are identified in procedure DC-016. These
i drawings and associated DCNs are reviewed by the B&R ALARA reviewer. Once
.
'
the ALARA consents are resolved, the changes are incorporated into the drawings,
# however, follow-up on all connent resolutions can not be demonstrated. The
revised ALARA program will address this concern. This is not reportable
because it impacts ALARA not the safe operation of the plant and the health and
safety of the public.
NRC RIV QUADP.EX REVIEW
ngrtntt;0I D00VME!!T
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SLB 5/8/81
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.
ITEM NUMBER: 4.8.2.1 (c)
.
.
DISCIPLINE: Mechanical /HVAC
i
AGREE WITH FINDING: $
-
i
O
.
.-
DISAGREE WITH FINDING:
TNIS ITEM IS CONSIDERED TO BE:
REPORTABLE _.... _ _ _ ..O
POTENTIALLY REPORTABLE . D
INSUFFICIENT DATA FOR ASSESSMENT
NOT REPORTABLE . .. Q u
.
*
BASIS FOR AB0VE ASSESSMkNT:
.
.
In 5-7-81 session with HL&P, they provided basis for original decision to
delete filters. On this basis they stated the finding is not potentially
mportable. As B&R is not aware of the actual ALAP assumptions we do not
disagree.
.
NRC RIV Q'JACT.EX REVIEW
F.EFEREt402 000U?/.Ef:T
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ITEM NUPSER: 4.8.2.1-(d)
DISCIPLINE: ,
Nuclear Shielding Discipline ,
AGREE WITH FINDING:
*
C see below
- - -
..: *: [.
DISAGREE WITH FINDING: O
THIS ITEM IS CONSIDERED TO BE:
REPORTABLE. . _ _ _ . .O
POTENTIALLY REPORTABLE _ _D
INSUFFICIENT DATA FOR ASSESSMENTQ
NOT REPORTA8LE .G
~
BASIS FOR ABOVE ASSESSMENT:
This statement is partially correct. The need for specifying that a shielding
calculation is safety related should be evaluated on a case by case basis
i.e. some calculations may support safety related equipment and therefore
could be " safety related". Currently, shielding calculations are checked
by another shielding engineer and reviewed by the OPE. Specifying a calculation
is safety related requires a " design verifier" to verify the calculation.
The main difference between the checker and design verifier is the verifier's
training. Both the verifier and checker are knowledgeable on shielding.
The calculations will impact the design of shielding which could impact
ALARA. During pre-opt testing or plant operations, any areas that have
excessive dose rates will be corrected by procedures, modifying shielding
(temporary or pemanent), the ALARA program or changing the need for access.
84,R has not verified all NUS shielding calculations. The models and codes
used for the shielding analyses are being reviewed. These problems are
being addressed as part of the "as built" analyses. This is not reportable
because it does not impact the safe operation of the plant or public
health and safety.
.
NRC Riv QUADREX REVIEW
ntFEREf 40E DOCUMENT
7 _
. no. - a
.
'(
f)
SLB 5/8/81
.
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d '- .. . _ . . . .
- - .
.
.
..
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ITEM NipSER: 4.8.2.1-(e)
.
DISCIPLINE: Nuclear Shielding Discipline .
\ . . . , , ' '"* *
C
.
AGREE WITH FINDING:
(see below)
DISAGEE WITH FINDING:
THIS ITEM !$ CONSIDERED TO SE:
REPORTABLE. . . . . . . .O
.
POTENTIALLY REPORTABLE __ D
*
INSUFFICIENT DATA FOR A55E55 MENT D
NOT REPORTABLE . . .W
- .
' .
,
,,,
SA515 FOR AB0VE ASSESSMENT:
.
This statement is partially correct. The design and analyses of the shielding
'
identified in the.TRD A509NQ005, were based on the radiation zones soecified
in the TRD. However,.this was not a comprehensive evaluation. B&R has initiated
a comprehensive program for perfoming "as built" shielding analysis of the
STP. ISI requirements are currently being developed and will be factored into
the ALARA program. The need for temporary shielding is specified by operations
and maintenance activities. As these activities are defined, temporary shielding
will be provided, as needed. This is not reportable because the correlation
of shielding criteria to the shield design impacts ALARA not the safe operation
of the plant and the public health and safety.
NRC Rtv QUADREX REVIEW
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ITEM NWSER: 4.8.2.1-(f)
DISCIPLINE: Nuclear Shielding Discipline -
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AGREE WITH FINDINd:
DISAGREE WITH FINDING: O
THIS ITEM IS CONSIDERED TO BE:
REPORTABLE _ _ .. _ _ .O
POTENTIALLY REPORTA8LE . ._ _ D
INSUFFICIENT DATA FOR ASSESSMENTQ
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BASIS FOR ABOVE ASSESSWT:
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Radiation zoning maps have not been developed for use in specifying plant
The accident limits are specified in regulatory
C,.accidentdoseratelimits.
documentation. Analyses have been performed to determine the accident dose rates
relative to regulatory limits, e.g. the control room. Radiation zoning maps
provide a convenient visual means of specifying limits. This is not a reportable ,
item because the use of zoning maps does not affect the safe operation of the
plant or the public health and safety.
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ITEM NLMER: 4.8.2.1-(g)
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DISCIPLIE: Nuclear Shielding Discipline .
I AGREE WITH FINDING: h .
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DISAGREE WITH FINDING: O
THIS ITEM IS CONSIDERED TO BE:
REPORTABLE _ _ ._ _ _ _ _ _.O
_. _D
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POTENTIALLY REPORTABLE
INSUFFICIENT DATA FOR ASSESSMENTQ
NOT REPORTABLE- _._ _ _ 5
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BASIS FOR ABOVE ASSESSMENT:
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The design basis for removable concrete block walls is being developed and will
be incorporated into the General Structural Design Criteria, SA36950001. The
block wall criteria impacts maintenance activities and ALARA ~not the safe
operation of the plant and is therefore, not reportable.
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NRC Riv QUADREX REVIEW
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, ll; ENCLOSURE (2)
SupWARY OF BROWN AND RDOT FINDINGS ON
, SOUTH TEXAS PROJECT QUADREX ENGINEERING REVIEW (May 1981)
ITEM 4.4.2.1(a)/(b) .
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SUBJECT
Inadequacy of the following STP HVAC Systems:
- MAB
- Fuel Handling Building .
- EAB
DESCRIPTION OF POTENTIAL PROBLEM
On April 7,1980, Houston Lighting & Power (HL&P) infomed Brown & Root
of a potential problem of cooling the Radwaste Control Room in the MAB.
A B&R study group was formed (Special Problem #16) with repmsentation
from the (B&R) Mechanical Electrical, !&C, Structural, Nuclear Analysis
and HVAC Disciplines. On Septe2er 18,1980 a preliminary assessment
conceming candidate areas for additional study was released. The candi-
date areas included: the electrical penetration space in the EAB; the
radwaste control room, which contains the hot shutdown panel, the reactor
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make-up water pump cubicle, the boric acid transfer pump cubicle, the
CVCS valve cubicle at elevation 41'-0" and 10'-0" in the MAB: the spent
fuel pool cooling pump cubicles in the fuel handling building (FHB) and
the valve cubicles in the FHB when containment isolation valves in dis-
charge lines from the High Head Safety Injection, Low Head Safety In-
jection and Containment Spray pugs are located. At this time a possible
need for supplemental air cooled chillers to handle additional antici-
pated (based on engineering judgement) HVAC loads were discussed.
From January 7,1981 thru January 27, 1981, calculations were infomally
received from the HVAC group confiming the need for additional HVAC
cooling capacity. On March 12, 1981, a draft report was issued by the
B&R Special Problems Group which sumarized the themal environmental
data which had been rtceived and confirmed the need for supplemental
cooling of the equipment described in Table 1 (Attached).
On March 19, 1981, representatives of QUADREX, under contract to HL&P,
conducted a technical audit of B&R's HVAC System design and in a report
received by B&R on May 7,1981, confirmed B&R's earlier assessment that
there may be insufficient HVAC cooling' capacity for equipment located
in the MAB and FHB.
Although we do not yet have actual heat load data, including maximum
allowable operating temperature infonnation, for all potentially affected
systems, we believe that there is curmntly sufficient uncertainty con-
caming the adequacy of the HVAC Systems designed for the MAB, FHB and
EAB to consider the matter to be potentially reportable at this time.
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APPROACH TO RESOLUTION
A supplemental HVAC system coreosed of in-room fan-coil units and air
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: cooled chillers is curmntly being considered for incorporation into the
STP Units. Sketches showing proposed physical arrangements art currently
being prepared for candidate locations and additional thermal operating
data is being sought from all equipment vendors.
STATUS OF PORPOSED RESOLUTION
A final determination concerning the need for additional safety grade HVAC
capacity will be completed upon rtceipt of the following evaluations: pipe
breaks outside containment (QUADREX Audit Question 4.4.4.1.a); and, special
problem 16 (QUADREX Audit Question 4.4.4.1.b). These evaluations will con-
sider the equipment and piping heat losses and the maximum environment for
which the safety related components are qualified. Withorst performing
these evaluations we.cannot determine the exact magnitude of the impact
on plant safety.
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Based on these uncertainties, we feel that this problem is potentially re-
portable under 10CFR50.55(e) and is currently being investigated as a
potential 10CFR21.
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REASONS FOR FINAL REPORTABILITY DELAY
Project Engineering had not congleted sufficient thermal calculations to
indicate a clear need for a supplemental HVAC System.
PROJECTED COMPLETION OF CORRECTIVE ACTION
The projected completion date for the following Special Problem #16 acti-
vities is currently June 15, 1981 to have a definition of design qualification
temperatures for safety related equipment, a preliminary assessment of heat
losses and arta temperatures and a conceptual design and preliminary lay-
out for a supplemental HVAC system.
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REFERENCE po00 MENT
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CANDIDATES FOR h tiVAC SERVICE -
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LOCATION EQUIPMENT KQUIRING EQUIP. QUALIF. POST-ACClK MT POST-ACCIDENT EWIPMENT
TER CONTROL TEW. F TEWERATURE w/o HVAC, HEAT LOAD STATUS
F (1) Stu/hr
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Radweste Control Room. H M nitoring Equip. 104 184 270,000 ON SITE
2
M48
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Electrical Penetration Class IE Cables 120 1st F1: 193 211,260(3)
Space, EA8 (2) 2nd F.: 204 251,940 (3)
3rd F1.: 185 255, 620 (3)
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Reactor make-up water Reactor make-up 120 195 61,000
Pumps Cubicle, M48 Water Pumps
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Spent Fuel Pool SFPCCS Pw ys 120 268 66,300
Pump Cubicles. FHB
Boric Acid Transfer Boric Acid Transfer 120 197 42,000 =
Puups Cubicle, M48 Pumps (4)
Cont. Iso. Valve Cont. Iso. Valves (5) 120 (later) 31,800 ; =
Cubicles FH8 84R Valve Nos.:
(3 cubicles) ISI 004A, 8. C
ISI 018A, 8. C ,
105 001A, 8. C
33,400 , =
Valve Cubicles in MR8 CVCS Valves used for 120 E1. 10'-0": 150
(3 cubicles) boration (4) E1. 41'-0": 150 38,400
8&R Valve Nos.:
ICV 218
XCV 112C ',
ICV 1138
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XCV 1128 5
XCV 113A
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Elect. Aux. 81dg. EA8 Chillers (later) (later) (later)
Chiller Area '
(located in M48) ,
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Footnotes (see Page 2) ,
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