ML20237K201
| ML20237K201 | |
| Person / Time | |
|---|---|
| Site: | Vermont Yankee File:NorthStar Vermont Yankee icon.png |
| Issue date: | 08/10/1987 |
| From: | Murphy W, Selleck K ROPES & GRAY, VERMONT YANKEE NUCLEAR POWER CORP. |
| To: | NEW ENGLAND COALITION ON NUCLEAR POLLUTION |
| References | |
| CON-#387-4212 OLA, NUDOCS 8708190133 | |
| Download: ML20237K201 (10) | |
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UNITED STATES OF AMERICA.
cre' 006 NUCLEAR REGULATORY COMMISSION before the ATOMIC SAFETY AND LICENSING BOARD
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In the Matter of
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' VERMONT YANKEE NUCLEAR
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Docket No. 50-271-OLA POWER CORPORATION
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.(Vermont Yankee Nuclear
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' Power Station)
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APPLICANT'S RESPONSE TOLNECNP'S' THIRD SET OF INTERROGATORIES AND DOCUMENT REQUESTS TO.
VERMONT YANKEE NUCLEAR POWER CORPORATION Requests Nos, 2, 6,
7, 8,
9, 10, 11, 19a-h are objected to as not being relevant to the subject matter involved in 1
the proceeding in light of the Appeal Board's decision in Vermont Yankee Nuclear Power Corporation (Vermont Yankee Nuclear Power Station), ALAB-869, 26 NRC (July 21, 1987).
INTERROGATORY NO. 1 Is it VY's view that both trains of the spent fuel pool 1
cooling system are capable of removing the total heat load generated by a normal-(1/3 core) discharge such that the pool temperature i~s always kept below 1500F throughout the lifetime of the proposed amendment?
Explain the bases for g
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your response and identify all calculations, analyses or other documents which support it.
RESPONSE
It is Vermont Yankee's view that both trains of the Fuel Pool Cooling System are capable of maintaining the Fuel Pool temperatures below 1508 F for a normal (1/3) core) fuel discharge throughout the lifetime of the proposed amendment.
Calculation VYC-642, performed in accordance with SRP 9.1.3 requirements, documents this capability.
This answer developed by Chris Hansen, Senior Engineer, Vermont Yankee Systems Group.
INTERROGATORY NO. 3 I
With regard to specification A. of 6 3.14 of the proposed new Limiting Condition for Operation attached as Appendix B to the "NRC Staff's Brief In Opposition to the Brief of Applicant," June 25, 1987, for how many days after discharge of a normal 1/3 core will compliance with this Specification require the reactor to be shut down?
RESPONSE
The reactor will be required to remain shut down less than three additional days following discharge of one-third of the core for eleven days following initial shutdown in order to comply with proposed tech-spec change 3.14A.
s This answer developed by D.
K. McElwee, Engineering Program Manager, Vermont Yankee, Brattleboro, Vermont.
INTERROGATORY NO. 4 What is the length of past refueling outages for Vermont Yankee?
RESPONSE.
The start dates, end dates, and lengths of past Vermont Yankee refueling outages are listed below.
REFUELING OUTAGE START DATE END DATE OUTAGE LENGTH (DAYS)
January 17, 1973 March 1, 1973 44 September 29, 1973 November 18, 1973 51 October 12, 1974 December 12, 1974 62
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D' June 19, 1976 August 7, 1976.
50 August 20, 1977 October 5, 1977 47 September 16, 1978 October 10, 1978 25 September 22,_1979 November 3, 1979 43 September 27, 1980 December 23,.1980 88 October 16, 1981 December 1, 1981-47 March.5, 1983-June 17, 1983 105 June 15, 1984 August 6, 1984 53 Septebmer 21, 1985 June 30, 1985 282 This answer developed by M.
J. Marian, Project Engineer,
. Yankee Atomic Electric Company, Framingham, Massachusetts.
INTERROGATORY NO. 5 What is the current average daily cost of replacement power when VY is shut down for refueling?
RESPONSE
Vermont Yankee Nuclear Power Corporation is a wholesale electrical supplier and as such does not purchase replacement power.
This answer developed by D.
K. McElwee, Engineering =
Program Manager, Vermont Yankee, Brattleboro, Vermont.
INTERROGATORY NO. 12 Identify and provide all calculations, analyses or-any other documents which support VY's assertion that its
" previous history and.
calculations indicate that i
there is no need to augment spent fuel pool cooling."
(Licensee's First Response, 23,
- p. 20).
RESPONSE-j Calculation VYC-642 uses a greater number of stored assemblies than ever before and uses more conservative decay heat analysis methods (SRP 9.1.3) than ever before.
The response to interrogatory #1 shows that Vermont Yankee does not need to augment fuel pool cooling with'the RHR system.
This answer developed by Chris Hansen, Senior Engineer, Vermont Yankee Systems Group.
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l' INTERROGATORY NO. 13 Describe how VY's calculations of the combined heat load to be removed from the pool and core are affected by the change from an annual to an 18-month refueling schedule. I i
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Identify.and provide all documents which support your response.
RESPONSE
The heat loads for the Vermont Yankee. spent fuel pool were calculated using the. empirical correlations specified in the Branch Technical Position ASB 9-2, Page 9.2.5-8 in l
Reference 1.
These expressions provide the heat. generation rate as a function of the reactor operation period and the shutdown time.
The change from an annual.to an 18-month refueling schedule impacts both the reactor operation period and shutdown time.
The heat loads for the Vermont Yankee pool were derived accounting for'the reactor operation and shutdown periods for both projected future annual and 18-month cycles.
The net maximum heat load in the pool at a given time was obtained by summing contributions from the past and projected future discharges filling the pool to its maximum capacity.
In our analysis the most conservative heat load for j
projected operating cycles was used to evaluate the capability of the spent fuel pool cooling system.
Reference 1.
NUREG-0800, Standard Review Plan, Revision 2,
- July,
'1981.
i.
This answer' developed by Paul A. Bergeron, Transient Analysis Group, Yankee Atomic Electric Company, Framingham, Massachusetts.
INTERROGATORY NO. 14 Does the heat load of 17.3 MBtu/hr given at page one of the June 11, 1987 letter from Mr. Murphy to Mr. Rooney (FVY 87-65) include the assumption of a change from an annual to an 18-month refueling schedule?
Does the heat load of 18.26 MBtu/hr for 2,870 assemblies include the assumption of an 18-month refueling schedule?
RESPONSE
The heat loads calculated for the Verment Yankee pool have. considered both an annual and an 18-month operating cycle.
The heat loads of 17.3 MBtu/hr and 18.26 MBtu/hr bound the assumption of an 18-month refueling echedule.
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This answer developed by Vinod Chanvola, Transient Analysis Group, Yankee Atomic Electric Company, Framingham, Massachusetts.
INTERROGATORY NO. 15 Identify and provide the evaluation of a fuel pool 8
temperature transient to 200 F referred to at page 3 of Mr.
Murphy's letter.
(FVY 87-65).
RESPONSE
Yankee Atomic Electric Company memorandum VYS-63/87 reviews this transient.
The document is on file at the Vermont Yankee Corporate Office in Brattleboro, Vermont.
This answer developed by Chris Hansen, Senior Engineer, Vermont Yankee Systems Group.
INTERROGATORY NO. 16 Identify and provide the evaluation which concluded that each of the spent fuel pool cooling subsystems are capable of operation at a fluid temperature of 2008 F, referenced at page 3 of Mr. Murphy's letter.
(EVY 87-65).
RESPONSE
An evaluation was performed by the Yankee Nuclear Service Division to assess the impact of operation of the Spent Fuel Pool Cooling System (SFPCS) at fluid temperature up to 200 F.
The designs of piping, pumps, heat exchangers, valves and instruments were examined with results concluding that the SFPCS, including the Residual Heat Removal System augmented fuel pool cooling mode, would be capable of sustaining a transient increased operating temperature of 200 F.
Documents supporting the evaluation are on file at the Vermont Yankee Corporate Office in Brattleboro, Vermont.
This answer developed by Stan Miller, Vermont Yankee Project Manager, Yankee Atomic Electric Company, Framingham, Massachusetts.
INTERROGATORY NO. 17 Specify the original design basis for the Spent Fuel Pool Cooling System and its components.
Identify and provide the documents which support your response..
14, C
RESPONSE
The original 1 design basis for'the Spent Fuel Pool Cooling System and components is contained in.Section 10 of the original VYFSAR.
This answer developed by D. K. McElwee, Engineering Program Manager, Vermont Yankee, Brattleboro, Vermont.
INTERROGATORY NO. 18 Counsel for VY. stated the following at th'e Prehearing Conference of April 21, 1987:
But the point I am getting at this plant, the mistake-NECNP makes is on page 6 of their original filing and they start out after giving their basis l
for Contention 3,
'should this amendment be l
approved it would be necessary under certain
' conditions to-use one train of the reactor's residual heat removal system RHR in addition to the spent fuel cooling system in order.to maintain the pool water within the design limits of 150 degrees Fahrenheit.'
That is true, it's true today 1
This new amendment does not for the first tim 9.
require the utilization of RHR Prehearing Conference, TR. 59.
Are the underlined statements accurate?
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RESPONSE
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The underlined statements are accurate but warrant further clarification.
Vermont Yankee has never operated the RHR system to augment fuel pool cooling while the reactor is shut down or in the run mode.
The RER system is, however, available to be used if necessary (and it has not to this date ever been necessary) to supplement the fuel pool cooling system while the reactor is shut down or in the run mode.
This capability has been in existence since the plant was originally licensed.and is not changed by the license amendment at issue.
Therefore, the capability to augment fuel pool cooling with RHR should not be confused L
with the need for utilization of RHR to maintain fuel pool temperature below 150 F.
This answer developed by D.
K. McElwee, Engineering Program Manager, Vermont Yankee, Brattleboro, Vermont.
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.J-t : 4-INTERROGATORY No. 19-(DOCUMENT REQUEST)
Please provide the following documents to be picked up by a representative lyf NECNP at a mutually convenient time no later than August 10, 1987:
i.
All documents responsive to Interrogatory 19
-(Licensee's First Response, p.
16).
.j.
All documents responsive to Interrogatory 23b (Licensee's First Response, p. 21).
RESPONSE
- 1.. Such documents as exist, if.any, will be made available for inspection at the corporate offices of Vermont Yankee Nuclear-Power Corporation, Ferry Road, Brattleboro, Vermont, during regular business hours on such dates and at such specific times as counsel may mutually agree. 'The Applicant will make copying arrangements if any are requested and the costs will be paid.by the requesting
. p a.r t y.
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All plant operating or emergency procedures which would be used by the operators should one. train of RHR fail are available for inspection at the corporate offices of Vermont Yankee Nuclear Power Corporation, Ferry Road, Brattleboro, Vermont, during regular = business hours on such dates and at such specific times as. counsel may mutually agree.
The Applicant will make copying arrangements if any are requested and the costs will be paid by the requesting party.
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As to answers:
A M *+9 k WarrenP.purph STATE OF VERMONT Windham, ss August 10, 1987 Then appeared before me the above-subscribed Warren P. Murphy and made oath that he was an officer of Vermont Yankee Nuclear Power Corp ation authorized to execute the foregoing responses to interrogatories on its behalf, that a diligent inquiry had been made to obtain such information in response to the said interrogatories and that to the best of his knowledge and belief such information as the corporation has set forth in the foregoing answers.
4%L
- ccy, Before me, YR 1
1 Diane S. McCue l
Notary Public h
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My commission expires F ry 1 o
p #A4N'@
As to objections:
g "fhoedis G. Dignan, Jr.
Kathryn A. Selleck Ropes & Gray 225 Franklin Street Boston, Massachusetts 02110 (617)423-6100 l
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CERTIFICATE OF SERVICE rrn r
I, Kathryn A.
Selleck, hereby certify that on.4ygusts 10,9 mi 1987, I made service of the within document in accordanceJn-with the. rules of the Commission by. mailing a copy thereof postage prepaid to.the following:
Charles Bechhoefer, Esquire, David J. Mullet,' Esquire I
. Chairman Vermont Department of Administrative Judge Public Service Atomic Safety and Licensing 120 State Street i
Board Panel Montpelier, VT '05602 U.S.
Nuclear Regulatory-
-Commission' Washington, DC 20555 i
Mr. Glenn O.
Bright Ellyn R. Weiss, Esquire Administrative Judge Harmon & Weiss Atomic Safety and Licensing Suite 430 Board Panel 2001 S Street, N.W.
U.S.
Nuclear. Regulatory-Washington, DC 20009 Commission-
. Washington, DC 20555 Mr. James H.. Carpenter George B.
Dean, Esquire Administrative Judge Assistant Attorney General Atomic Safety and Licensing Department of the Attorney General Board Panel One.Ashburton Place U.S( Nuclear Regulatory Boston, MA 02108 Commission-
' Washington,.DC 20055 Atomic Safety.and. Licensing Ann P. Hodgdon, Esquire Board Panel Office of the General Counsel U.S.
Nuclear' Regulatory U.S. Nuclear Regulatory Commission.
Commission Washington, DC 20555 Washington, DC 20555 Atomic Safety and Licensing Appeal Board Panel U.S. Nuclear Regulatory l
Commission i
Washington, DC 20555 l
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i Geoffrey M. Huntington, Esquire Office of the Attorney General Environmental Protection Bureau State House Annex 25 Capitol Street Concord, NH 03301-6397 Ksthbyn A.
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