ML20237G980
| ML20237G980 | |
| Person / Time | |
|---|---|
| Site: | Vermont Yankee File:NorthStar Vermont Yankee icon.png |
| Issue date: | 08/11/1987 |
| From: | Capstick R VERMONT YANKEE NUCLEAR POWER CORP. |
| To: | Rooney V Office of Nuclear Reactor Regulation |
| References | |
| RTR-NUREG-0737, RTR-NUREG-737, RTR-REGGD-01.097, RTR-REGGD-1.097 FVY-87-77, NUDOCS 8708170008 | |
| Download: ML20237G980 (45) | |
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VERMONT YANKEE r
NUCLEAR POWER CORPORATION.
.y RD 5. Box 169, Ferry Road, Brattleboro, VT 05301 REPLY To i
ENGINEERING OFFICE 1671 WORCESTER ROAD yv FRAMINGH AM, MASSACHUSETTS 01701 TELEPHONE 617 812-8100 August 11, 1987 FVY 87-77 JUnited States Nuclear Regulatoty. Commission Washington, DC 20555 i
f-l l-Attention:
Office of Nuclear. Reactor Regulation l
Mr. V. L. Rooney, Sr. Project: Manager l
Project Directorate No_. I - 3
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Division of Reactor Projects - I/II
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References:
(a) Licenso No. DFR-28 (Docket No. 50-271)
(b) Letter, VYNPC to USNRC, FVY e4-127, dated October 30, 1984, "NUREG-0737,. Supplement No..l'-
(c) Letter, USERC to VYNPC, NVY 85-173, dated August 19, 1985.
" Request for Additional Information Following Preliminary Staff Review of Licensee Response to Generic Letter 82-33" (d) Letter, USNRC to VYNPC, NVY 85-187, cated August 29, 1985,
" Order Modifying License Confirming Additional Licensee Commitments on ERF" j
(e)
Letter, VYNPC to USNRC, FVY 85-99,. dated October 25, 1985, l
" Additional Information in Response to Preliminary Review 1
of NdREG-0737, Supplement 1, Regulatory Guide 1.9/
Submittal"
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(f) Letter, VYNPC to.USNRC, FVY'86-50, dated June 2, 1986, i
" Environmental Qualification of Electrical Equipment j
Important to Safety (10CFR50.49)"
1 (g) Letter, VYNPC to USNRC, FVY 86-122, dated December 19, 1986, " Request to Modify Confirmatory Order and Provide Schedular. Extension for ERF Requirements" (h) Letter, USNRC to VYNPC, NVY 87-31,' dated February 18, 1967, " Supplement 1, NUREG-Of37, Request for
'i rurther Modification of Commission order, dated
-Juno 12, 1984" l
Subject:
WUREG-0737, Supplement No. 1 - Regulatory Guide l'.97 Program Status
Dear Sir:
1 The purpose of this letter is to provide an updated status of the Vermont Yankee Program pertaining to Regulatory Guide 1.97, Revision 3,
" Instrumentation for Light-Water-Cooled Nuclear Power Plants to Assess Plant and Environment Conditions During and Following an Accident."
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B708170008 I 70811 PM ADOCK 5000271 f \\
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l United States Nuclear Regulatory Commicsion August 11, 1987 Attention:
Mr. V. L. Rooney Page 2 In prior correspondence, Vermont Yankee detailed our continuing efforts to address.the requirements of Regulatory Guide 1.97 By letter,, dated 1
June 2, 1986 1 Reference (f)], Vermont Yankee provideo a status of the
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Regulatory Guide 1.97 equipment upgrades with respect to the scope of our
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Environmental Qualification Frogram (10CFR50.49).
In response to the staff's i
August 19, 1985 request [ Reference (c)], Vermont Yankee submitted additional information [ Reference (e)) responding to the preliminary. staff review of Vermont Yankee's NUREG-0737, Supplement 1, Regulatory Guide 1.97 Program submittal of October 30, 1984 [ Reference (b)].
In our October 30, 1984 submittal [ Reference (b)], we provided the results of our plant-specific engineering assessment of Regulatory Guide 1.97, Revision 3. " Instrumentation for Light-Water-Cooled Nuclear Power Plants to Assess Plant and Environment Conditions During and Following an Accident."
Consistent with that submittal, this letter provides an updated status of equipment in two Attachments (all changes to the October 30, 1984 submittal are denoted by a bar in the right margin).
Attachment A - Qualification Summary (cubdivided into four sections).
1.
Equipment which is in full agreement with Regulatory Guide 1.97 requirements.
2.
Equipment where range, environmental qualification, or other attributes have been determined on a plant-specific basia, to be appropriate for Vermont Yankee.
Where these attributes differ from those shown in the Regulatory Guide, justification of the appropriateness of the attributes selected is provided.
3.
Equipment which has been or shall be modified or upgraded in order to provide adequate range, environmental qualification, or other characteristics.
4.
Equipment which has been deleted from the Regulatory Guide 1.97 List of Instrumentation.
This equipment has been removed as a result of further developments in operating procedures and the Vermont Yankee Equipment Qualification Program.
Attachment B - Regulatory Guide 1.97, Instrumentation Matrix.
Verwont Yankee's present commitment regarding the Regulatory Guide 1.97 confirmatory order [ Reference (d)) requirement to implement (install or upgrade) post-accident monitoring instrumentation is prior to startup for Cycle 13 (approximately fall 1987).
During the 1986 refueling outage. Vermont Yankee completed all Regulatory Guide 1.97 installation / upgrades associated with our Environmental Qualification Program.
The planned work scope for the 1987 refueling outage includes completion of all remaining Regulatory Guide 1.97 installation / upgrades.
Recently, however, we determined that'the LPRM power supplies should be upgraded.
Due to the difficulty of including this recently determined upgrade in the 1987 outage work scope due to the resource commitments associated with our containment safety efforts and based on the fact that, with the exception of this one item which is not a safety-related
United States Nuclear Regulatory Commission August 11, 1987 Attention:
Mr. V. L. Rooney Page 3 concern, all Regulatory Guide 1.97 installation / upgrades will be completed in i
l accordance with the existing schedular commitment; Vermont Yankee has l
requested [ Reference (g)J and received approval [ Reference (h)) that the subject order be modified to extend the Regulatory Guide 1.97 schedular commitment for this specific item one additional outage cycle (prior to startup for Cycle 14, approximately winter 1988/1989).
j We trust that the enclosed status update information is satisfactory and l
assists your review of the Vermont Yankee Regulatory Guide 1.97 Program.
l Should you have any questions or require additional information concerning this matter, please contact this office.
Very truly yours, VERMONT YANKEE NU LE POWER CORPORATION ll -
1 R. W. Capstick.
Licensing Engineer RWC/25.09 Enclosures l
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ATTACHMENT A l
Qualification Summary,_
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Page 1 of 17 j
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ATTACHMENT A
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Qualification Summary The following is a list of Regulatory Guide 1.97 (Regulatory Guide 1.97) instrumentation divided into four sections:
1.
Fully Qualified Instrumentation 2.
Equipment Determined to be Appropriate on a Plant-Specific Basis i
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Instrumentation Requiring Upgrade or Modification l
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Instrumentation Deleted From the Submittal Section 1 is a list of fully qualified instrumentation.
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Section 2 details equipment which has been evaluated on a plant-specific basis to provide the information required to support safe shutdown. This equipment j
may differ in range, environmental qualification, or other attributes from the'
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guidance in Regulatory Guide 1.97.
However, the analysis performed insures i
that this equipment supports the required safety functions specified in the Vermont Yankee Environmental Qualification Program and conforms to the new Symptom-Based Emergency Operating Procedures.
f Section 3 details additional instrumentation needed.
This additional ~
1 instrumentation could consist of entirely new instrument channels or existing instrument channels which require some upgrading. All equipment being
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installed will be qualified in accordance with the appropriate Vermont Yankee f
specific Design and Qualification Criteria category.,
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Section 4 details the instrumentation which has been deleted from the Regulatory Guide 1.97, List of Instrumentation. Vermont Yankee originally considered this equipment within the scope of Regulatory Guide 1.97.
- However, j
following further development of operating procedures and the Vermont Yankee Equipment Qualification Program, some equipment was no longer required to be operational. Consequently, it has been removed from the Regulatory Guide 1.97, Instrumentation Matrix (Section B).
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Under the EQ Program [ Reference (f)], in determining environmental H
qualification requirements, we have addressed all design basis events as
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i documented in Chapter 14 of the Vermont Yankee Final Safety Analysis Reports (FSAR), as well as High Energy Line Breaks (HELBs) outside containment and flooding. This is consistent with the intent of 10CFR50.49.
The method for identifying electrical equipment within the scope of Paragraphs (b)(1) and (b)(2) of 10CFR50.49 (i.e., safety-related as well as nonsafety-related electrical equipment relied upon to remain functional or whose failure under postulated environmental conditions could prevent I
Page 2 of 17 I
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satisfactory accomplishment of safety functions during and following design-basis accidents) is described and documented in Reference (f). This included:
Identification of general design criteria consistent with Vermont s(a) _ Yankee's plant-specific design and 10CFR50.49, (b) Defining required safe-shutdown-safety functions for design-basis accidents utilizing shutdown sequence diagrams based upon existing emergency operating procedures and the Vermont Yankee FSAR, (c) Identification of the major electrical components required for each postulated accident, in potentially harsh environments which are relied upon to operate (or to not fail) for required safety functions.
These components were identified by reviewing Plant Piping and Instrumentation Diagrams (P& ids), and t
(d) Identification of the remaining electrical components in potentially harsh environments (associated with the major required electrical components) that are relied upon to function, or whose failure could impact any required safety functions or mislead the operator such that required safety functions could be jeopardized. These components were identified by reviewing plant electz hal Control Wiring Diagrams (CWDs).
In addition, a field walkdown inspection of all major components and associated equipment was performed to insure accuracy and completeness.
The method used for identifying electrical equipment within the scope of Paragraph (b)(3) of 10CFR50.49 (i.e., "certain post-accident monitoring equipment") included the review of Symptom-Based Emergency Operating Procedures to identify a comple a list of associated display instrumentation.
The instrumentation necessary a determine that a system is performing its safety function is included in the list of post-accident monitoring instrumentation.
A review for plant-specific Type A variables was conducted utilizing the s
Symptom-Based Emergency Procedures. These procedures are living documents; as 1
future revisions to the E0Ps modify display instrumentation requirements, l
changes to the instrumentation list will be made accordingly.
The Category 1 variables, which require redundancy, have been evaluated to l
ensure that a single failure will not result in information ambiguities that l
l could lead operators to defeat or f ail to accomplish a required safety function. One or mc.e of the following means are available to access plant status of the affected parameter.
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(a) Crosschecking with an independent channel that monitors a different variable bearing a known relationship to the failed monitoring channel.
(b) Perturbing the measured variable to determine the failed channel by observing the response on each instrument.
F (c) Operating procedures.
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Page 3 of 17 It should be noted that Category 1 variable separation'at' Vermont Yankee is in accordance with the Vermont Yankee Ground Rules for Separation and
- l Identification of Reactor Protection and Safeguard Systems. This is the.
l criteria utilized during the original design and construction ot the plant.
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Its use in this application is therefore acceptable.
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Page 4 of 17 1
1.
Fully Qualified Instrumentation The following instrumentation currently installed at Vermont Yankee fully
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complies with. Regulatory. Guide 1.97 requirements:
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l Item Service i
A6 Torus pressure.
B2 Control rod-position.
B3 RCS soluble boron concentration.
C2 Primary coolant analysis (gamma spectrum).
CF/El Primary containment area radiation.
C11/C11 Containment /drywell hydrogen and oxygen concentration.
D1 Main feedwater flow.
D2 Condensate storage tank level.
D3 Suppression chamber spray flow.
D8 Drywell spray flow, D10 Primary safety relief valve position - ADS.
D16 LPCI flow.
D19 RHR system flow.
D23 Radwaste system.
D24 Emergency vent damper position.
i E3 Radiation exposure rate (safety access areas).
E10 Particulate / halogens.
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l Ell Airborne radiohalogens.
x E13 Isotopic analysis.
l E14 Wind direction.
l EIS Wind speed.
l E16 Atmospheric stability.
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l E18 Containment air sample.
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1 Page 5 of 17 2.
Equipment Determined to'be Appropriate on a Plant-Specific Basis I
l This section details equipment presently existing at Vermont Yankee, how l
it deviates from the Regulatory Guide specified instrumentation, and a l
justification for the existing equipment acceptability.
This justification is based upon the use of other instrumentation qualified under the' Vermont Yankee Environmental Qualification Program which bears a known relationship to the specified variable, or a Vermont Yankee position that the specified variable is not warranted.
This equipment is:
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Item No.
Results 1
l A4 - Drywell Pressure Regulatory Guide 1.97 requires both drywell-l B7 - Reactor Coolant System narrow and wide-range pressure measurement.
l Integrity -
Drywell narrow-range pressure transmitter, i
Drywell Pressure PT16-19-28, is a single-channel instrument.
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B9 - Maintaining Containment The wide-range pressure transmitters, f
Integrity -
PT16-19-29A/B, encompass both the narrow and i
Drywell Pressure wide ranges required and are displayed on CRP
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C8 - RCS Pressure Boundary -
9-25 and CRP 9-3.
These transmitter loops also Drywell Pressure meet the requirements for Category 1 C10 - Containment -
variables. -It is Vermont Yankee's position Primary Containment that narrow range drywell pressure is not Pressure needed post-LOCA, due to the fact that once the D4 - Primary Containment LOCA has been controlled, the drywell will not Related Systems -
repressurize. However,, if that were to happen, Drywell Pressure any changes in pressure will be displayed in the Control Room.
Therefore, it is not i
necessary to provide Category 1 instrumentation for narrow-range pressure.
It is Vermont Yankee's position that PT16-19-29A/B instrument loops meet the intent of these six variables post-LnCA.
i Page 6 of 17 Item No.
Results A8 - Torus Water Level Regulatory Guide 1.97 requires both narrow and C7 - Reactor Coolant Pressure wide-range torus level indication. The torus Boundary - Suppression is presently monitored by fully qualified level Pool Water Level -
transmitters which supply level signals that Wide Range are indicated in the Control Room. These DS - Suppression Pool Water transmitters cover.the wide range of the torus Level - Narrow Range from 2 to 25. feet. This range encompasses the narrow range regttired by Item D5.
Two narrow-range transmitters supply level indication to the Control Room during normal operation.
Post-accident high resolution l
indication in this range is not required by Vermont Yankee's Symptom-Based Emergency Operating Procedures. Post-accident torus level indication is displayed such that a change in level will be clearly visible to the plant operators.
It is Vermont Yankee's position that the vide-range level, is adequate.
for those variables based on the E0P requirements and the fact that the wide-range level transmitters are fully qualified.
Therefore, no further action is required.
A9 - Torus Airspace Temperature
. Torus airspace temperature was a single channel with a range of 0 to 3000F. When this variable was determined to be a Type A variable, it was upgraded and qualified, with a redundant qualified channel being installed.
However, the new channel has a range of 50 to 3000F. This range is acceptable since the torus is totally contained in a heated building, which ensures that the reduction on the' lower end of the instrument range will not adversely affect the plant operation.
Additionally, the reduced indication range increases the display resolution consistent with human factors requirements.
Page 7 of 17 Item No.
Results i
l B8 - Maintaining Containment The drywell sump level uses level switches to Integrity - Drywell Sump start /stop pumps during normal operation.
Level Regulatory Guide 1.97 requires continuous sump C6 - RCS Pressure Boundary -
level indication from the bottom to the top.
Drywell Sump Level The existing configuration is designed to detect and measure leaks in the drywell by-measuring both the sump pump running time and the time between pump initiations with external l
pump monitoring equipment.
During a LOCA, J
drywell sump level is ineffective due to the fact that the sump will fill and overflow into the torus which is monitored by an environmentally qualified level measurement system. Additionally, drywell pressure is also monitored by environmentally qualified j
instrumentation which will indicate a line i
break in the drywell before the torus level j
indicates a rise.
Therefore, it is Vermont Yankee's position that drywell sump level indication is not appropriate for Vermont Yankee and that the existing system is adequate.
B10 - Primary Containment Regulatory Guide 1.97 requires fully qualified j
Isolation Valve Position isolation valve position indication.
Per the
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l Vermont Yankee EQ Program, valve position j
indication for certain PC isolation valves is required to be qualified for ten minutes following a design basis LOCA.
The first ten l
minutes following a LOCA is generally j
acknowledged as a period in which the operator gathers information, tries to understand what has happened, and determines plant status.
Primary containment isolation status would be part of the information that the operator would gather during this period.
If one or more PC isolation valves were to indicate a failure to automatically close, the i
operator would attempt to manually close, from the Control Room, those valves that indicate l
open and should have closed.
The qualification i
of PC isolation valve indication is therefore l
warranted for initial verification of the PC isolation safety function.
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Page 8 of 17 Results The required qualification time per Regulatory Guide 1.97 (page 1.97-3) is:
.as long as the information.it provides is needed by the Control Room operating personnel." This is the same approach utilized in the EQ Program l
Report.
For_long-term post-LOCA, PC isolation valve position is not needed for the following general reasons:
o Any corrective action required would l
be done in response to the initial verification of.PC isola: ion.
o Subsequent failure of indication will not impact the actual valve position
-(i.e.,
fail safe).
Subsequent false valve indication o
would n n result in the operator l
i taking action that_would be detrimental to safety. Even if the operator did not terify that all isolation valves did close within the first ten minutes, his only option is to attempt to close those valves that (correctly or incorrectly) INDICATE open whenever he observes an open I
indication on a valve that should be closed.
o Radiation monitoring outsida the Reactor Building compareci with the radiation inside the containment will provide the best indication of the primary contairunent isolation safety function.
o Many PC isolation valvec are also, associated with other safety functions (i.e., ECCS_ valves); Position indications for these valves are qualified based upon Safety functions-other than PC isolation. The following PC isolation valves have been qualified for long-term post-LOCA operation including valve position.
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Page 9 of 17
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Valve No.
Service 10-13A kHR Pump Suution from Tcrus l
l 10-13B RHR Purup Suction f.com Torus 1
(10-13C RHR Pump Su; tion from Torus10-13D RHR' Purap Suction f rom Torus10-16A RER Min Flow Valves10-16B RHR Min Flow Valves t
l 10-25A RHR trCI to Reactor 10-25B RHR LPCI to Reactor 10-26A RHR Drywell Spray l
10-26B RHR Drywell Spray f
l 20~27B RER LPCI to Reactor I
10-31A RHR Drywell Spray 10-31B RHR Drywell Spray 10-34A RHR Suppression Pool 10-34B ItHR Suppression Pool 10-38A RER Torus Spray 10-38B RER Torus ispray 10-39A PHR Torus Spray Upstream Valve 10-39B RHR Torus Spray Upstre m Valve 14-5A Core Spray. Min Flow Valve 14-5B Core Spray Min Flow Valve 14-7A Core Spray Guetion 14-7B Core Spray Suction 14-11A Core Spray to Reactor 14-11B Core Spray to Reactor
Page 10 of 17
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l Item No.
Service l
14-12A Core Spray to Reactor 14-12B Core Spray to Reactor 16-10-11A Vac Breaker Sec. Cont. to Torus l
16-19-11B Vac Breaker Sec. Cont. to Torus I
For t he reasers stated above, it is Vermont Yankee's position that these valves meet the intent of this Regulatory Guide parameter.
(tem No.
Results i
01 - Fuel Cladding-hadiation Radiation levels in the main steam lines are Level in Circulatirig continually monitored by the main steam line l
l Primary Coolant radiation monitory which generate a scram if the steam radiation exceeds a precet level, i
indicating a failure of the fuel cladding.
As such, they.will accomplish.their intended function, which is to scram the reactor, prior to the onset of harsh environmental conditions.
In accordance with the methodology used in the Vermont Yankee EQ Program, these detectors, although utilized for fuel failure events, are not relied upon for LOCA or HELB events.
Once the MSIVs have closed, there is no circulating primary coolant in the mainsteam l
lines and no longer a need to accurately monitor steam line radiation levels. However, the drywell high-range rad monitors, which are environmentally qualified, will monitor the radiation buildup within the drrwell, witil direct coolant radiation level assessment being available from Chemical and Health Physics analysis via the Post-Accident Sampling System. For this reason, it is Vermont Yankee's position that the existing instrumentation is acceptable.
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Page 11 of 17 i
Item No.
Results C13 - Containment - Effluent Since' all anticipated post-acciduitt plCat Radiation Noble Cases effluents pass through the plant st'.0F, only l
C14 - Containment -
monitoring the common plant vent is tenuired by.
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Effluent Radioactivity the Regulatory Guide since it will provide (from buildings and areas indication of effluert radiation levels from in direct contact with these areas. The atack nonitoring instruments Primary Containment) cover the range required..Since they are E4 - Airborne Radioactive located in the stack, the only possible harsh l
Material Releases -
environment is due to radiation. However, l
Drywell/ Standby Gas since this equipment is,specifically designed l
l Treatment Purge Flow and tested to measure radiation levels higher E5 - Airborne Radioactive than those which will be encoun%ered, they are l
Material Releases -
qualified for their intended service:
Thess Secondary Containment instruments read out in millirem; nowever, a 1
Purge Flow simple conversion to microcuries per cubic l
Secondary Containment centimeter can be accomplished by healtb i
E6 - Airborne Radioactive physics.
Material Releases -
Secondary Containment E7 - Airborne Radioactive Material Releases -
j Auxiliary Building E8 - Airborne Radioactive Material Releases -
Common Plant Ventilation E9 - All Other Identified j
Release Points D13 - Safety Systems - RCIC Flow D14 - Safety Systems - HPCI Flow Both the HPCI and RCIC flow transmitters supply flow indication to the Control Room during the onset of a LOCA. Regulatory Guide 1.97 requires these two variables to be environmentally qualified. Per the Vermont Yankee EQ Program, these two variables do rot experience harsh environments during the small break LOCA event in which'they'are relied upon. Once the vessel has been'depressurized, both HPCI and RCIC become inoperative and their flow indication is not needed4. Therefore,:it is Vermont Yankee's position that the existing equipment is acceptable.
D15 - Core Spray Flow D22 - Cooling Water Flow to ESF In the EQ Frogram, flow indication for these System Components Safety Systems'was not required.
In lieu of various flows, the instrumentation'that monitors the reactor and pritary containment
f Page 12 of 17 Item No.
Results responses post-accident would be the ultimate indicat wr. of.ECCS performance (i.e., Rx vessel ~
level, yreesure, drywell temperature, drywell i
pressure).
In addition, ECCS valve position
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informa. tion, along rith ECCS pump motor running current ! amps) indicates the mode of operation and is far mere valuable than monitoring flow.
Therefore, additional qualification or upgrading is not warranted, and Vermont Yankee I
considers these variables Category 3.
I17 - SLLS Flow SLCS flov and storage tank level is required by D18 - SLCS Storage Tank Level Regulator 3 Guide 1.97 to be environmentally qualified.
However, per the EQ Program and the Vermont Yankee FSAR (Section 3.8.4), tbis system provides a method'to shut down the reactor from the full-power condition and maintain the reactor suberitical during cooldown independent of the control. rods. As such, it is not expected to be needed for plant j
safety following a DBA, Since this system is for independent tackup of the control rods, it is not relied upon for accidents in which harsh environments are created.
Therefore, l
environmental qualification of any SLC component is not warrante6 although specified in Regulatory Guide 1.9/..These parameters are i
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considered Category 3 by Vermont Yankee.
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'S 'les : Exchanger Regulatory Guide 1.97 regitires environmentally Octiet Temperature qualified monitoring ef these two variables.
D21 - Cooling Water Temperature In the Vermont Yankee EQ Program, monhoring to ESF System Ccmponents the RHR heat exchanger snell and tube side outlet temperature was -not relied upon.
The function of the RHR heat exchangers post-accident is to renove stcred and decay heat.
In lieu of the RHR heat exchangar temperature variables, monitoring the reactor and primary containment ree:ponses (i.e., tores water temperature, drywell, and reactor pressure) will be the most fmportant indicators of RHR heat exchanger performance.
Therefore, additional qualificatica ct upgrading is not warranted, and Vermost Ysnkee eunsiCers j
these variables Category 3.
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Page 13 of 17 Item No.
Results E2 - Reactor Building or Post-accident secondary containment area U
Secondary Containment radiation monitoring, as well as radiation Area Radiation monitoring in other areas where personnel eccess may be desirable, would be, helpful to the Health Physics Department in determining I
local radiological conditions prior to entering these areas.
This function is important from l
the standpoint of evaluating personnel i
habitability in the event of a severe core
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damage accident. However, areas.outside the Reactor Building that do require personnel access post-accident have been' analyzed using very conservative assumptions to show that habitability would be allowed. Also, the EQ l,
Program assumes tnat habitability in the j
Reactor Building is not possible for at least three months post-accident; and the essential equipment necessary to function for an extended period post-accident has gensrally been environmentally qualified for one year.
i Therefore, any decisions on habitability inside the Reactor Building would not be necessary for some time after the event.
If the secondary containment area radiation monitors were not.
'f f unctioning at this time, alternate means to j
estimate secondary containment radiation levels would be possible (i.e., correlations based on drywell, vent stack, and site area radiation i
measurements).
l In light of this, Vermont Yankee considers variable (E2), " Secondary Containment Area Radiation," as a Category 3 variable.
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E12 - Environs Radiation Presently, there is one portable survey l
Radioactivity Plant and instrument at Vermont Yankee that can measure 4
Environs. Radiation up to 10 R/Mr photons, but none that can 1
measure the Regulatory Guide required 106 r/hr beta. The existing instrumentation I
can measure approximately 102 r/hr beta.
These ranges are sufficient for portable plant use.
E17 - P.rimary Coolant Sample Regulatory. Guide 1.97 requires the on-site J
ability to perform several different analysis on the primary coolant sample, one of which was a pH concentration of 1 to 13.
However, in a 2
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Page 14 of
',7-l Results j
l previous'Jermont Yankee letter, dated j
September 21, 1984, concerning NUREG 073?c
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Item II.B.3, Post-Accident Sampling Capabiltty Criteron 10 tbat "... pH measurements are not -
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included because an undilated sample cannot be obt4 ned from the post-accident sample panel."
1 The NRC issued a safety evaluation report on January 14, 1985 accepting this position.
The above exception,is based on tests conducted i
at bermott Yankee on octual reactor coolant samples.
This sample was obtained and diluted l
with demineralized water to a dilution of 1000:1, which is tbe minimum dilution appropriate to maintain personnel radiation exposures'ALARA for the~ expected post-accident' l
coolant activk y levels.
The resulting measurement concluded that no meaningful l
information was obtained other than the I
undiluted sample was acidic or alkaline.
l Additionally, Vermont Yankee evaluated the need to measure coolant pH at a freshwater BWR site and determined that pH is not particularly important since all metals which contact the coolant a.te compatible with liquids having a vide range of pH.
Thus we conclude that relatively little meanir.gful information would be gained from post-accident coolant pH I
campling.
l Therefore, based on Vermont Yankees prior j
notification to NRC stating that undiluted pH i
samples cannot be obtained for the I
post-accident sastple sta* ion; NRC's acceptance of Vermont Yankee's provisions to meet 1
NUREG-0737. Item II.B.3, Criterion 10; and' 1
Vermont Yankee's evaluation of diluted pH l
camples discussed above, we have removed
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primary coe.Jant nB from our ?ost-Accident
. Monitoring Instrumentation list.
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Instrumentation Requiring tograde or Modif 3 cation This section details additional instrumentation needed for cospliance to the Regulatory Guide.
This additional instrumentatfor consists of any Equipment which requires modifications to establish comr!iance.
This i
could con 6ist of entirely ne, instrument channels or existing instrument' I
L channels which require some upgrading.
_ Item Ko.
Results l
l Al - Reactor Vessel Pressere Vessel level ard pressure are precently A2 - Reactor Vessel Level monitored by instrumentation which complies B4 - Core Cooling - Coolaat with Category 1 requirements. A review of the Level Symptom-Based Emergency Operating Procedures s
l B6 - RCS Integrity -
has indicated that trending of these parGoeters j
RCS Pressure is required. A design' change has been
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C4 - RCS Pressure Boundary -
initiated to provida recorders for these
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RCS Pressure parameters.
This modification will be C9 - Containment -
implemented in accordance witL our agreed upon l
RCS Pressure schedule.
A3 - Drywell Temperature Dryvell atmospheric temperature displays P7 - Primary Containment 0-3000F, which is less 1.han the 400F to 440 F range required.
The accident analysis l
0 Related Systems - Drywell Atmospheric Temperature conducted to support Vermont Yankee's EQ Program indicates that the postulated drywell temperature will not exceed 3500F.
The present instrumentation is powered from a-l common povar source and displayc on a cominon readout. device.
To provide compliance with the i
Regulatory Guide, redundant'lustrument channels f
and readout devices will be inrtalled. The i
range of these instruments will be consistent with accident analysis results.
)
A7 - Torus Vater Temperature Suppression pool water temperature displays l
D6 - Prinary Cantadasent 600F to 1800F in the Control Room, which is Related Systems -
less than the required 409F to 2300F range Suppression Pool Water specified.
The. existing range calibration will Temperature be expanded to accommodate a higher torus j
temperat.urs. Additionally, these instruments
{
t.Sare a ecmmen readout device which has'ene I
source of' power. As such, redundant.' indicators
{
and power sources-will be installed to provide thannel rcdundancy, T.1 - Reactivity Controls As 4cscribed 1n the Vermont Ya.nkee EQ Program, Neutron Flux only the LPRMs ele required to verify scram, not SRM/IRM equipment.
This is based on a p;sition that indication of neutron flux down m
l
- Pe_,
16 of 17 i
l I
i to one perWat power frather than 10- 6 j
j;erceut power) is sufficient ts determine that j
a successful scram has occurreC It should be j
rernembered that for accidentc a successful
)
reactor scre by the control roda is l
anticipated even'given a worst-case single failure. A f&ilure to scram event (ATWF) is not considered to be un accident in which harsh j
envircaments develop.
?t is Vermont Yankee's i
pooitson that the LPRMs hre adequate to verify l
a scrar As a result, the LPRMs were
]
env wciomentally qualified in accordance with
)
the Vermont Yankee EQ program. Additionally,
{
it has been discovered that a power
]
modification is needed to insure LPRM podt-LOCA operation. This modification will be completed l
in accordance with our agreed upon. schedule.
j 1
i D25 - Power Supplies -
120/240 V ac vital bus voltage and frequency
]
Standby Power Status have local indication on the vital at control panel.
Instrumentation will be vdded to l
indicate these variables in the' Control Room.
All other power supplies presently have j
instrumentation in the Control Room.
l I
1 l
l l
l 1
i L_.
~
r Page 17 of 17 i
-1 4.
Instrumentation Deleted From the Submittal j
This section detnils instrumentation which has been deleted from the original Reculatary Guide, 1.97 submittal The equipment removed, and
]
the reason for the remova'., are listed below.
l A3 - Reactor Vessel Reference Originally, Vermont Yankee classified this l
Leg Area Thermocouple variable as Type A Category 1, based'on the l
Vermont Yankee draft Emergency Operating Procedures (EOPs). Vermont Yankee has further j
developed the E0Ps, and concluded that these j
variables are not Type A variables.
This is based on the fact that this variable does not 1
provide primary indication of a plant parameter.
The reference leg thermocouple
(
provide the Contrc,1 Room operators with information of the reliability of'the reactor t
vessel level indication. As such, they provide indication of the confidence in a variable l
providing primary indication of a plant parameter.
Based on the above discussion, Vermont Yankee has removed this item from the Regulatory Guide 1.97 submittal, but will-install Environmentally Qualified reference leg 4
thermocouple as a part of the resolution of l
Generic Letter 84-23 " Reactor Vessel Water Level Instrumentation of BWRs,."
L10 - Primarf Containment RHR shutdown cooling supply, Valve 10-18, has Isolation valve Position been temoved from the original Regulatory Guide 1.97 submittal and the Vermont Yankee EQ Program. This valve is normally closed by a pressure interlock during plant operation and opened only when the plant is shut down.
Following a LOCA, this valve is not needed for j
accident mitigation. Additionally, post-LOCA i
failure will not cause the valve to open.
Consequently, removal of this valve from the Regulatory Guide CIS valve position list is acceptable.
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