ML20093B952
| ML20093B952 | |
| Person / Time | |
|---|---|
| Site: | Beaver Valley |
| Issue date: | 10/03/1984 |
| From: | Woolever E DUQUESNE LIGHT CO. |
| To: | Knighton G Office of Nuclear Reactor Regulation |
| References | |
| 2NRC-4-158, NUDOCS 8410100290 | |
| Download: ML20093B952 (4) | |
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.1hVL 2NRC-4-158 October 3, 1984 (412) 787-5141 (412)9234 960 Nuclear Construction Division elecon (412) 787-2629 Robinson Plaza. Building 2. Suite 210 PittT Crgh, PA 15205 5
United States Nuclear Regulatory Commission Washington, DC 20555 ATTENTION:
Mr. George W. Knighton, Chief Licensing Branch 3 Of fice of Nuclear Reactor Regulation
SUBJECT:
Beaver Valley Power Stat ~on - Unit No. 2 Docket No. 50-412 Supplemental Submittal in Rasponse to Draf t SER Open Item No. 53 Gentlemen:
At tached is the response to the NRC Accident Evaluation Branch's Draft SER Open Item No. 53, including the response to Part 1 of this item which had not been previously provided.
The responses to Parts 2 and 3 of this item were provided previously in letter 2NRC-4-124, dated August 13, 1984, and are repeated in this submittal for information only. Please note in the response to Part 1 that DLC is requesting confirmatory status for this item.
DUQUESNE LIGHT COMPANY By E. /J. Woolever Vice President JD0/wjs Attachment cc:
Ms. M. Ley, Project Manager (w/a)
Mr. E. A. Licitra, Project Manager (w/a)
Mr. G. Walton, NRC Resident Inspector (w/a)
SUBSCRIBED AND SWD)/[Leh41N y pEFORE ME TH M O DAY OF L
, 1984.
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C Notary Public ANITA ELAINE REITER, NOTARY PUBLIC ROBINSON TOWNSHIP, ALLEGHENY COUNTY
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8410100290 841003 f.1Y COMM!SSION EXPlRES 00TCBER 20,1986 PDR ADOCK 05000412 E
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Unithd Stctsa Nuclacr R2gulctcry Commission Mr. George W. Knighton, Chief
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~ COMMONWEALTH OF PENNSYLVANIA )
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SS:
-COUNTY OF, ALLEGHENY
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, before me, a
.On'this day of e
Notary Public -in : and. for said Commonwealth and County, personally appeared
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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 and file the foregoing. Submittal on behalf of said Company, and-(3) the statements
- set. ' forth - in ~ the Submittal are true and correct to the best of his knowledge.
.4 /M/A Notary Public ANITA ELAINE REITER, NOTARY PUBLIC ROBINSON TOWNSHIP, ALLEGHENY COUNTY '
MY COMMISSION EXPIRES OCTOBER 20,1986 4
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Draft SER Open Item No.~53 (Section 6.4) - Control Room Habitability:
b The staf f review' of the. Beaver' Valley control roori emergency HVAC system L ndicates there. are several - additional open items, not previously i
identified;. that relate. to control room operator thyroid ' doses.
The following.three' areas will have to be addressed by the applicant:
II. Automatic control room pressurization on detection of radiation in the outside air-intake is not addressed in the applicable FSAR c
sections. : Radiation : de tectors in L the outside air intakes may be necessary to initiate the control room emergency. systems (and main-Ltain control room dose to within GDC 19 guidelines) in the event of design ' basis. accidents occurring outside the containment, such as stemslin, break, fuel handling accident and small line break outside containment.
2.
Flow rates of the bottled. air pressurization system, which pressur-ines' the control' room to 1/8 inch w.g. or greater for 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> follow-
'ing - a de s ign basis accide nt,- are needed.
If they are greater or much less than. the pos t-accident air makeup rate of 1,400 CFM (Table 6.4-1 of FSAR) ~ an explanation would have to be submitted by the applicant.
(
3.= Radioactive gases release point E, shown on Figure 6.4-5 of the FSAR appears to. be less than 100 feet from the nearest control room air int ake.
Because~ of the close proximity of this release point, an evaluation of control room operator doses is needed.from the appli-
~ cant for those design basis accidents that result in radiation to be released from point E.
Unti1 ~ these matters are resolved, control room habitability remains an open item.
Based upon the foregoing, the applicant has not demons trated that the J
control room habitability systems will adequately protect the control
. room operators in accordance - with the requirements of NUREG-0737, Item
=III.D.3.4, and 10CFR Part 50, Appendix A, GDC 19.
-Response:
1.
A containment Phase B isolation (CIB) signal from either BVPS-1 or BVPS-2 will automatically - isolate both the BVPS-1 and BVPS-2 sides of the 'coasson control room.
DLC is currently performing the appropriate analyses to determine whether the BVPS-2 control room radiation monitoring system provides adequate operator protect ion, in accordance with GDC 19, in the event of. a high radiation signal resulting from design basis acci-dents occurring outside the containment.
The results of these analyses will be provided to the NRC if they indicate that BVPS-2 meets GDC.19 with the existing design.
In this case, the BVPS emergency procedures will define control room operator action with l
respect to manual initiation of control room emergency systems.
If the ~ analyses indicate that GDC 19 is not met, DLC will perform the necessary plant design changes to ensure compliance with this criterion.
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~ Based 1on the above described - approach to resolving this open item, DLC is requesting that this. item be given confirmatory status.
2.
'In order to maintain 'a minimum pressure of 1/8 inch water gauge in the control. room following a ' design basis ac cident, an air makeup rate. of 800 cfm is ' required..
The BVPS control. room emergency a total 'of 1000 cfm
-bottled ai'r pressurization system can provide
' through ' the five. supply lines which carry 200 cfm each.
Current
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design' changes being. considered for the BVPS-1 energency pressuriza-tion : fans may : increase ' the post-accident air makeup rate of these
- fans from 'the current 400 cfm to as high as 1000 cfm.
This combined BVPS-1 and BVPS-2 air makeup. rate of 2000 cfm would present no prob-lems'as far as overpressurization of the control room is concerned.
- 3. - Point E is monitored by a BVPS-l' radiation nonitor. If a high radia-tion signal is~ received, the outflow from Point E is trans ferred to the ; BVPS-1 Supplementary Leak Collection and Release System.
The flow ' then -passes through a, train of HEPA filters before being released _ to the. atmosphere through BVPS-1 elevated release Point D
.which is located at the top of the BVPS-1 reactor cont aimment building.
Therefore, the control room operators are adequately protected against.any potential radioactive releases from Point E.
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