ML20106F875
| ML20106F875 | |
| Person / Time | |
|---|---|
| Site: | Beaver Valley |
| Issue date: | 02/08/1985 |
| From: | Woolever E DUQUESNE LIGHT CO. |
| To: | Knighton G Office of Nuclear Reactor Regulation |
| References | |
| 2NRC-5-018, 2NRC-5-18, NUDOCS 8502140127 | |
| Download: ML20106F875 (5) | |
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2ggg0,ia (412)923-1960 Nuclear Construction Division Telecopy (412) 7s7-2629 Robinson Plaza, Building 2, Suite 210 R"sbur9, PA 15205 PeDruary 8, ]985 h
United States Nuclear Regulatory Comniosion Washington, DC 20555 ATTENTION:
Mr. George W. Knighton, Chief Licensing Branch 3 Of fice of Nuclear Reactor Regulation
SUBJECT:
Beaver Valley Power Station - Unit No. 2 Docket No. 50-412 Reactor Systems Branch Open Items / Questions Gentlemen:
l This letter forwards responses to draft SER open items and questions provided by the Reactor Systems Branch. Attached are responses for Questions 440.75 and 440.76 and a supplement ary response fo r O pen I tem 161.
Informal responses for these have been previcusly transmitted to you.
It is noted that Duquesne Light Company letter 2NRC-4-122 from Mr.
E.
J.
Woolever to Mr.
G.
W. Knighton dated August 10, 19 84, provided the original res pons e to Open Item 161 and that it atso provided a response to Open Item 162 which addresses the same subject as attached Question 440.75.
DUQUESNE LIGHT COMPANY By
- /-
E.VJ. Woolever Vice President JJS/wjs Attachment cc:
Mr. B. K. Singh,. Project Manager (w/a)
Mr. G. Walton, NRC Resident Inspector (w/a)
SUBSpRIBED AND SWORN TO BEFORE ME THIS ff/t, DAY OF M /uto,2 a 1985.
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Notary Public ANITA ELAINE REITER, NOTARY PUBLIC -
ROBINSON TOWNSHIP, Alt.EGHENY COUNTY.
MY COMMISSION EXPIRES OCTOBER 20,198&.
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~ Unitid Stctes Nuclecr.Ragulctory Conuniscion Mr. Gacrge W.- Knighton, ' Chief Page 2-COMMONWEALTH OF PENNSYLVANIA
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COUNTY OF ALLEGHENY
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On this,
/d day of caut
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, before me, a Not ary :Public - in and for said Commonwealth and County, personally 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 and file
'the / foregoing S ubmittal on -. behalf of said Company, and (3) the statements set - forth' in the Submittal 'are true and correct to the best of his knowledge.
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Notiary Public ANITA ELAINE REITER, NOTARY PUBLIC '
RCS!NSCN TOWNSHIP, ALLEGHENY COUNTY MY COMM;SSION EXFIRES OCTOBER 20,1986.
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' QUESTION 440.75 In its July 23, 1984, draft response to Outstanding Issue #162, the Duquesne Light Company compared the details of natural circulation at Beaver Valley
- Unit 2 to those of North Anna. Unit 2 where a natural circulation test was performed.
However, the Reactor System Branch (RSB) has not received the
- results nor the. analysis of the North Anna 2 test.
Thus North Anna Unit 2's ability; to satisfy the natural circulation criteria fo SRP Branch Technical Position, RSB 5-1, has not been confirmed.
The RSB -will have to receive and confirm that the results of' the North Anna Unit 2 natural circulation test prove compliance with-RSB 5-1 before this issue can be closed.
Respons,e '
Refer to April 22, 1982, letter from R.
A.
Clark, Chief, Operating Reactors Branch #3,. Division of Licensing to R.
H.
Le asburg,' Vice President of Nuclear Operation, Virginia Electric and - Power Company (VEPCO).
It acknowledges the VEPCO results which show that the.boration
' capability under natural circulation is more than adequate to of fset the cooldown reactivity effects.
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' QUESTION 440.76 The L functional diagram for the pressure relief system on the pres surizer, which is _ Figure 7.2-1 Sheet 17 of the BVPS-2 FSAR, shows an " Auto" position
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of the PORV block valve control switch.
Does this mean that when the switch is ' in l this " Auto" position the pressurizer, PORV, block valve will automat-
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.ically. close on the loss of pressurizer pressure?
I f so:
(1) What are the
- set -points on this. automatic closure system?
(2) Is automatic closure accounted ' for in the emergency procedures which will be followed after a steam -generator tube rupture?
(3) What alarms will alert the operator if the switch is in the wrong position?
-Response.
The ~ pressurizer pressure relief interlock signal as shown on Figure 7.2-1 Sheet 6 causes the pressurizer PORV block valves automatically to
- open.on pressurizer high pressure and automatically to close on pressur-izer low pressure when: the MCB control switch is. In the automatic posi-t ion. Although automatic closure is not mandatory for the block valves -
because.~ operator action can close them subsequent to a PORV f ailing to close, this ' automatic. closure on low pres sure is not detrimental to reactor safety. considering PORV LOCA, steam generator tube rupture recovery, or ICC' recovery procedures as discussed in' WCAP-9804.I~
Auto-matic opening of these block ; valves is provided. by an alternate means
. when. the Cold Overpressure Mitigation System (COMS) "is manually initi--
ated~.
. Also the block valves. may be directly opened by administrative '
means by holding the block valve control switch :in its " spring-return"
. open position, recognizing that the switch will' return to the. automatic z
position.on release of the switch.
<There 'is '. a "depres urrizer check' step" in.the. ERG for Steam. Generator-
~
- Tubi -Rupture E3, - as well as~ in other. ERG's, that 1 " flags" l the ; need -c for
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-proper alignment o'f the block valve'and PORV..
/An' : annunciation 'of L the bl'ock valve opening - signal is' visible to /the-operator at the main control board.
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11 WCAP-9804,' D.
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Wood, ' C.
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Gottshall, = "Probabilistic ' Analysis and:
Operational -; Data ;in > Response to --? NUREG-0737. Ites ; II.K.3.2 for ;WNES /
LPlants"
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OPEN ITEM 161 Since both RHRS pumps are located ins ide of containment, there is a question of whether or not this envirorn. ant could cause a common mode failure.
Moreover,: the Equipment Environmental Qualification Table (3.11-1) in the FSAR for the. RHRS does not include the RHR pumps.
For a reliable system
-these pumps are going to have to be qualified for the contairunent environment and included in Table 3.11-1.
Supplementary Response (Original Response 8/10/84, 2NRC-4-122)
The FSAR section referenced in the original response should be 5.4.7.2.6.
The safety grade systems which perform the function of removing residual heat from the reactor core for LOCA conditions are the ECSS, AFWS, and stean generator PORVs.
The ECCS systems used would depend 'on the LOCA event, the _ size of ^ the break.
The systems that could be employed are
' High-Head Safety Injection, Low Head Safety Injection, and the Accumula-tors. Depending on the severity of the accident, one, two, or all three
' systems could be employed.
FSAR Section 3.11 now references Table
- 1. 7 -3.
Table 1.7-3 references the equipment qualification report as a separate submittal. This report was submitted by' Letter 2NRC-4-087 dated June 22, 1984, and it contains Table 3.11-1.
Environmentally qualified elect rical equipment provided
.to meet GDC 34 is included in this table.
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