ML20083Q625
| ML20083Q625 | |
| Person / Time | |
|---|---|
| Site: | Beaver Valley |
| Issue date: | 04/18/1984 |
| From: | Woolever E DUQUESNE LIGHT CO. |
| To: | Knighton G Office of Nuclear Reactor Regulation |
| References | |
| RTR-NUREG-0737, RTR-NUREG-737, TASK-2.B.3, TASK-TM 2NRC-4-042, 2NRC-4-42, NUDOCS 8404230165 | |
| Download: ML20083Q625 (6) | |
Text
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$VL 2NRC-4-042 (412) 787 - 5141 Telecopy 12) 8 -
Nuclear Construction Division April 18, 1984 Robinson Plaza, Building 2 Suite 210 Pittsburgh, PA 15205 United States Nuclear Regulatory Commission Washington, DC 20555 ATTENTION:
Mr. George W. Knighton, Chief Licensing Branch 3 Office of Nuclear. Reactor Regulation
SUBJECT:
Beaver Valley Power Station - Unit No. 2 Do cke t No. 50-412 Responses to NRC Chemical Technology Section Draf t SER Outstanding Issues Gentlemen:
On March 13, 1984, DLC met with the NRC Chemical Engineering Branch-Chemical Technology Sect ion to discuss the draft SER open' itens related to this se ct io n.
These are indicated as Open Item Nos. 78 through 81 in Table 1.2 of the draf t SER.
Based on the discussion at this meeting, res pons es to these open items have be en pr epared and are pr ov ided in At tachment 1.
The as sociated revisions to FSAR Sect ion 9.3.2.3 and the res pons e to NRC Ques t ion 281.4 are provided in Att achment 2.
These revisions will be incorporated into FSAR Amendment 7.
Based on the aforementioned meeting, it is DLC's understanding that this submit t al closes draft SER Open Items 78 through 81, unless furt he r notification indicating otherwise is received from the NRC.
DUQUESNE LIGHT COMPANY r
By E (/J." Wooleve r Vice President JD0/wjs At tachment s cc:
Mr. G. Walton, NRC Resident Inspector (;/a)
Mr. M. Lacitra, Project Manager (w/a)
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SUBSCRIBED AND SWORN TO BEFORE ME THIS j
/78 DAY OF _[/om/,
, 1984.
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s 840k230165 840418
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Notary Public
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PDR ADOCK 05000412 PDR-ELVA G. LC50.';DAK, NOTAP.Y PU3LIC E _
I?CSINSON TOWNS (no, ALLEGHENY COUNTY MY COMMISSlON E??igjs CCTOBER 20,1985
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' United States Nuclear Regulatory Commission Mr. George W. Knighton, Chief Page 2 COMMONWEALTH OF PENNSYLVANIA )
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COUNTY OF ALLEGHENY
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On this /7 b day of 2
__/fh before me, a Notary Public in and fo r said Commonweal th and County, pe rso nally appeared E. J. Woolever, who being duly sworn, deposed and said that (1) he is Vice President of Duquesne Light, (2) he is duly authorized to execute l
and file the foregoing Submit t al on behalf of said Company, and (3) the statements set fo rth in the Submittal are true and correct to the best of his knowledge.
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' Not ary Public
- LVA G. LESONDAK, NOTARY PUBLIC RCSINSON TOWNSHIP, ALLEGHENY COUNTY MY COMMISSION EXPlRES OCTOBER 20,1986 4
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ATTACHMENT 1 Open Item No. 78 (SER 9.3.2.2)
Procedure to estimate extent of core damage.
Res pons e:
Refer to the revised res pons e provided fo r FSAR Que s t ion 28 1.4, Pa rt 1 (At tachment 2).
Open Item No. 79 (SER 9.3.2.2)
Backup post-accident sampling through grab samples for inline analyses
Response
Refer to revised FSAR Section 9.3.2.3.2 (page 9.3-24, At tachment 2).
Open Item.No. 80 (EER 9.3.2.2)
Measuring radionuclide concentrations Res ponse :
Refer to the revised res ponse provided for FSAR Ques tion 281.4, Part 3
( At tachment 2).
Open Item No. 81 (SER 9.3.2.2)
Performance of PASS instrumentation and analytical procedures Res ponse :
Refer to the revised res pons e provided for FSAR Ques tion 281.4, Part 2
( At tachment 2).
t
i ATTACHMENT 2 BVPS-2 FSAR NRC Letter: August 31, 1983 Question 281.4 (Section 9.3.2.3, SRP 9.3.2) 1.
Provide a core damage es timate procedure to include radionuc lide con-centrations and other physical parameters as indicators of core damage.
an ac ceptab le methodo logy fo r pr epa ring plant At tachment 1 provides specific core damage procedures.
2.
Provide info rmation demons trating applicability of procedures and ins trument ation in the pos t-ac cident water chemistry and radiation e nv ironme nt, and retraining of operators on semi-annual basis. Indicate the measurement accuracy of each chemical and radiological anal ys is.
Guidance for analytical chemistry procedure is enclosed as Attachment 2.
3.
Show how clarification (9) in Item II.B.3 of NUREG 0737 is met.
Response
1.
BVPS-2 will adopt the. final ve rs ion of the Westinghouse Owners Group post-accident core damage as ses sment methodolegy which is currently being reviewed by the NRC.
When the final ve rs ion of this generic methodology is available, the necessary adjustments in parameter values will be made and the BVPS-2 plant specific procedure will be prepared.
In the meantime, BVPS-2 will adopt the lates t available draft ve rs ion of the Wes tinghouse Owners Group methodology.
2.
Refer to revised Section 9.3.2.3.2 and new Table 9.3-11 for the Pos t-Accident Sampling System (PASS) parameter ranges and accuracies.
Following their initial training, PASS operators will be retrained on a s emi-annual basis to ens ure their familiarity with the system ope ra-tions and procedures.
PASS instrumentation will be calibrated ' on a semi-annual basis.
3.
An isotopic analys is will be performed using a Germanium de t ecto r connected to a computer-based multichannel analyzer.
The ' PASS has the capability to dilute both liquid and gas samples for isotopic analysis.
Further dilutions, if necessary, could be performed in the laboratory.
The accuracy of the method of performing an isotopic analysis for post-accident samples is considered to be +_ 50%.
Amendment 7
'Q281.4-1 1984 i
L.
BVPS-2 FSAR return samples to various locations commensurate with sampling conditions.
The following post-accident sampling points have been included in the PASS design:
Primary coolant hot leg sample (four points),
1.
2.
Residual heat removal heat exchanger outlet sample (two points),
3.
Reactor containment sump sample, 4.
Reactor containment atmosphere sample, 5.
Safeguards area sump sample (two sumps),
Auxiliary building sump sample (four cumps),
6.
Pipe tunnel sump sample (one sump), and 7.
8.
Recirculation spray pump discharges.
The following sample return points will be utilized for each of the sampling conditions indicated:
1.
Normal plant operations Primary drains transfer tank (ausiliary building), and a.
b.
Volume control tank.
2.-
Post-accident operations Pressurizer relief tank, and a..
b.
Reactor containment sump.
analyzed on-line in the PASS panel will be analyzed via Samples not facility grab samples at the shared BVPS-1/BVPS-1 emergency response mies,qsosts for all on-line. anelyses.pliny Cephilify, Via gyn b Laborata that is onsite. Backup Sam The following accident sampling analyses will be-provided within to sample, except 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> or less from the time a decision is made for chloride which will be provided within 4 days:
Amendment 1 9.3-24 May 1983
BVPS-2 FSAR l
l.
Primary coolant and stsup samples:
a.
Gross activity - provided as an on-line capability at the PASS panel, b.
Gasuna spectrtsa (isotopic analysis) - at the emergency response facility, c.
Baron content - provided as an on-line capability at the PASS panel, d.
Chloride content - provided as as on-line capability at the PASS panel, e.
Dissolved Na or total dissolved gas, and O.- provided z
as an on-line capability at the PASS panel (reactor I
coolant only), and f.
pH - provided as an on-line capability at the PASS panel.
2.
Containment atmosphere sample Hydrogen content - provided as an on-line capability in a.
the combustible gas control system (Section 6.2.5),
b.
carv.s content - provided as an on-line capability at
(-
the PASS panel, and.
c.
Gamma spectrum (isotopic analysis) - at the emergency response facility.
in accordance with the requirements of Sample analyses ranges are Regulatory Guide 1.97 for i.yye 5 variables.
PASS panel consists of a shielded panel with internal capability The for on-line analysis, as previously described, and shielded grab sample acquisition capability.
manipulate panel control equipment at the panel-front, Operators admitting samples for on-line analysis and/or grab sample collection.
1 The PASS panel collects sample drains and routes them back to the plant through various systems. (Figure 9.3-11).
The PASS panel is located in the aumiM ary building at el 735 ft-6 in in an area accessible.to personnel under all plant operating conditions.
The following delineates the specific methods utilized to route each of the individual samples required to the PASS panel (Figures 9.3-11 and 9.3-12):
1.
Primary coolant hot leg samples s
Amendment L 9.3-25 May 1983 Sanyle anlysi.s aawracie.s ar.A runp Sr A Mss are own
/n Ta4/e 9.3-//,
4 BVPS-2 FSAR TABLE 9.3 POST-ACCIDENT SAMPLING SYSTEM PARAMETER RANGES AND ACCURACIES 4
l Parameter Range Accuracy Liquid Samples Isotopic activity 1 uCi/mi to 10 Ci/ml Factor of 2 Boron content 0 to 6000 ppm
),1000 ppm: f;5% of measured value
< 1000 ppm: f 50 ppm Chloride content 0 to 20 ppm
> 0.5 ppm: j;10% of
,measured value
< 0.5 ppm: + 0.05 ppm Dissolved hydrogen 0 to 2000 cc
> 50 cc/kg: + 10% of or total dissolved
(*STP)/kg measured value gas
< 50 cc/kg: j;5 cc/kg Dissolved oxygen 0 to 20 ppm
> 0.5 ppm: j[10%of
,measured value
< 0.5 ppm: f;0.05 ppm.
l pH 1 to 13
> 5 to < 9: f 0.3 pH unit s
. < 5 or > 9: + 0.5 pH i
i units 1
Gaseous Samples t
j 0xygen content 0 to 30% by volume
- + 10% of scale Isotopic content 1 uCi/ml to 10 Ci/ml Factor of 2 NOTE
t
- STP - 0*C and one atmosphere I
i I
1 of 1 l
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