ML20040C386
| ML20040C386 | |
| Person / Time | |
|---|---|
| Site: | Vermont Yankee File:NorthStar Vermont Yankee icon.png |
| Issue date: | 01/19/1982 |
| From: | Heider L VERMONT YANKEE NUCLEAR POWER CORP. |
| To: | Eisenhut D Office of Nuclear Reactor Regulation |
| References | |
| RTR-NUREG-0803, RTR-NUREG-803 FVY-82-4, NUDOCS 8201270592 | |
| Download: ML20040C386 (4) | |
Text
.
. VERMONT YAN KMM NUCLEAR POWER CORPORATION SEVENTY SEVEN GROVE STREET 2.C.2.1 RUTI.AND, VisRMONT 05701 FVY 82-4 REPLY TO:
ENGINEERING OFFICE 1671 WORCESTER ROAD FR AMINGH AM, M ASSACH USETTS 01701 TELEPHONE S17 872 8100 Janua ry 19, 1982 O
g 31ECEIVED
\\\\
9-v JAN2 6199y
~
United States Nuclear Regulatory Commission f
8 8E'W IWte g.
N 3
a Washington, D. C.
20555 g%stata d
s y
N Attention:
Office of Nuclear Reactor Regulation Mr. D. G. Eisenhut, Di rec t o r 4
N Division of Licensing Re f e rence s :
(a)
License No. DPR-28 (Docket No. 50-271)
(b)
Letter, D. G. Eisenhut to All BWR Licensees, dated April 10, 1981 (c)
Letter, VYNPC to USNRC, FVY 81-87, dated June 1,1981 (d)
Letter, D. G. Eisenhut to All CE BWR Licensees (Except llumbol t Bay), dated August 31, 1981 j
(c)
Letter, VYNPC to USNRC, FVY 81-14, dated January 27, 1981
Subject:
Ve rmont Yankee Response to NUPEG 0803
Dear Sir:
This letter is written in response to Reference (d), which requested certain information described in the subject NUREG report. The requested
'Information is presented below as sequential responses to each of the items listed in Table 5.1 of NUREG 0803.
1.
Periodic Inservice Inspection and Surveillance of SDV System The QA records of the original installation have been reviewed.
It is concluded that the system was constructed to the specified requirements for piping fabrication and testing.
All of the insert and withdrawal lines and the Scram Discharge Volume, Instrument Volume, vents, drain, and risers f rom the llCU's, are classified as Safety Class 2 and are included in the Vermont Yankee ISI p rogra m.
I h *(
o 8201270592 820119 k
0 L
65 DRADOCK05000g
United States Nuclear Regulatory Comnission Janua ry 19, 1982 At te ntio n:
Mr. D. G. Eisenhut Page 2 2.
Threaded Joint Integrity A preliminary inspection of the system has been completed and a minimal number of threaded joints have been found.
The system inspection will be completed and those threaded joints found will be assessed and, if necessary, modified by the end of the next refueling outage.
Since plant construction, there have been no problems related to threaded joints in the CRD system.
3.
Seismic Design Verification The CRD insert and withdraw lines were reanalyzed and hangers modified as found necessary in 1980.
These lines meet seismic requirements.
We are presently in process of designing the modifications committed to in Reference (e).
When installed, the modifications will meet the BWR
)
Owners Subgroup design and performance criteria, including seismic loads.
4.
HCU-SDV Equipment Procedures Review Our existing procedures, which control all work on safety-related systems, adequately address this concern.
5.
Environmental Qualification of Prompt Depressurization Function An analysis was performed of a high energy line break (HELB) in either SDV at a leakage rate of 3 gpm per drive. The same code was used as was applied to all the HELB calculations.
The SDV break was not found to be a limiting case for any equipment that was considered under the Environmental Qualification (EQ) program. Equipment needed to mitigate an SDV break is also needed for more severe breaks, which are limiting.
6.
As Built inspection of SDV Piping and Supports See response to Item 3.
7.
Improvement of Procedures We are in the process of improving the emergency procedures at our facility.
Appropriate symptoms for rapid depressurization of the reactor vessel have been identified. We are confident that, following implementation of a newly organized procedure network, the risks due to an unisolated primary system leak outside the containment will be diminished.
These procedures will be in place by the completion of the next scheduled refueling outage.
Per its charter, the BUR Owners Group cannot respond directly to NRC requests f or utility action, except at the discretion of its members.
Neither can Vermont Yankee commit the Owners Group to a specific course of action except by its participation in Owners Group decisions by vote.
Thus, Ve rmon t Yankee can only provide a response to the staff's guidance to the BWR Owners Group in NUREG 0803 as if it were addressed to Vermont
United States Nuclear Regulatory Commissiou Janua ry 19, 1982 Attention:
Mr. D. G. Eisenhut Page 3 Yankee directly.
In any event, Vermont Yankee continues to believe that the proper contact point for the NRC when initiating any new requirements is the licensee, not the Owners Group.
8.
Verification of Equipment Designed for Water Impingement The plant design was reviewed for susceptability of ECCS equipment to flooding, wetdown by overflow, and impingements.
Plant design is such that ECCS equipment is not subject to any of these conditions created by a n S DV b rea k.
There are curbs around stairways to ECCS rooms, equipment is not located under maintenance hatches and there is an open, coverless hatch to the torus area f rom the floor on which the SDVs are located which would divert any water.
9.
Verification of Equipment Oualified for Wetdown by 212 F Water See response provided for Item 8.
10.
Verification of Feedwater and Condensate System Operation Independent of the Reactor Building Environment Feedwater and condensate system pumps, motors, switchgear and controls are all located outside the reactor building and would be available for nake-up and core cooling following an SDV break.
Vessel level instrumentation is included in the environmental qualification program and will be qualified for a harsher environment than that created by an S DV b rea k.
11.
Evaluation of Availability of HPCI-LPCI Turbines Due to High Ambient Temperature Trips A high energy line break analysis was performed for SDV break at 3 gpm per d rive.
The environmental ef fects due to this break are not limiting, as described in the response to Item 5.
The HPCI 6 RCIC high temperature trip detectors are located below the floor on which SDVs are mounted so a break would not af fect them.
The detectors in the steam tunnel are connected to time delay relays of 30 and 60 minutes.
Therefore, an SDV break will not disable 'lPCI and RCIC.
12.
Verification of Essential Components Qualified for Service at 212 F and 100% Humidity As noted in the response to Item 5 above, a plant specific HELB for SDV break has been done.
Equipment needed to mitigate this and all other breaks required to be considered will be qualified for the calculated local conditions under the EQ program.
13.
Limitation of Coolant Iodine Concentration to Standard Technical Specification Values Vermont Yankee's Technical Specification limit on primary coolant iodine concentration is 1. luc 1/gm, compared to STS value of 0.2 uCi/gm and
United States Nuclear Regulatory Comaission Janua ry 19, 1982 Attention:
Mr. D. G. Eisenhut Page 4 Brown't Ferry 3 value of 3.2 uCi/gm.
Based on a straight line interpolation of the NRC data in NUREG 0803, Vermont Yankee concludes that the limit presently contained in our technical specifications is sa t i s f ac t o ry.
We trust the inf ormation provided above will be satisf actory; however, should you have any questions, please contact us.
Ve ry t ruly yours, VERMONT YANKEE NUCLEAR POWER CORPCRATION H. Heider Vice President dad COMMOINEALTH Of MASSACHUSETTS)
)ss MIDDLESEX COUNTY
)
Inen personally appeared berc re me, L. H. Heider, who, being duly sworn, did state that he is a Vice President of Vermont Yankee Nuclear Power Corporation, that he is duly authorized to execute and file the foregoing request in the name and on the behalf of Vermont Yankee Nuclear Power Corporation and that the statements therein are true to the best of his knowledge and belief.
Robert H. Groce Notary Public My Conmission Expires September 14, 1984 41...H. c,s s/
ihr
~
,,f"h c 3.
-^ p k
'('
Y>
- t b}f J'.
-c1 J
N 7 -4ctiO 43y ps%
.......... -