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Category:Letter
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TS 3.7/3.14 AOT for SW Piping Maintenance ML24164A0012024-08-12012 August 2024 Proposed Alternative Relief Request V-1 Inservice Testing of Pressure Isolation Valves (EPID l-2023-LLR-0060) IR 05000280/20240022024-08-0101 August 2024 Integrated Inspection Report 05000280/2024002 and 05000281/2024002 05000280/LER-2024-001, Troubleshooting Initiated Unknown Turbine Trip Feature in Control System2024-07-30030 July 2024 Troubleshooting Initiated Unknown Turbine Trip Feature in Control System ML24165A2782024-07-17017 July 2024 Issuance of Amendment Nos. 318 and 318, Reclassification of Regulatory Guide 1.97 Variable for Low Head Safety Injection ML24165A1232024-07-17017 July 2024 Proposed Alternative Relief Request P-1, P-2 Inservice Testing of Residual Heat and Containment Spray Pumps (EPID l-2023-LLR-0058) ML24190A4192024-07-0808 July 2024 Inservice Testing (IST) Program for Pumps and Valves Revised Sixth IST Interval Start Date and Updated Technical Specifications References for Alternative Request V-1 ML24179A2932024-07-0101 July 2024 Notification of Inspection and Request for Information for NRC Problem Identification and Resolution Inspection ML24178A2422024-06-25025 June 2024 2023 Annual Report of Emergency Core Cooling System (ECCS) Model, Changes Pursuant to the Requirements of 10 CFR 50.46 ML24177A2792024-06-20020 June 2024 Preparation and Scheduling of Operator Licensing Examinations ML24166A0622024-06-18018 June 2024 – Proposed Alternative Relief Request P-3, P-4 Inservice Testing of Boric Acid, Component Cooling Water Pumps ML24157A0542024-06-13013 June 2024 Audit Summary in Support of License Amendment Request for Proposed Reclassification of Low Head Safety Injection Flow Instrumentation Related to Regulatory Guide 1.97 ML24143A1622024-06-12012 June 2024 – Correction to Issuance of Amendment Nos. 297 and 280 and Surry Units 1 and 2, Correction to Issuance of Amendment Nos. 317 and 317, to Change Emergency Plan Staff Augmentation Times ML24170B0532024-06-10010 June 2024 DOM-NAF-2-P/NP-A, Revision 0.5, Reactor Core Thermal-Hydraulics Using the VIPRE-D Computer Code IR 05000280/20244032024-05-22022 May 2024 Information Request for the Cyber Security Baseline Inspection, Notification to Perform Inspection 05000280/2024403 and 05000281- 2024403 ML24141A2862024-05-22022 May 2024 Information Request for the Cyber Security Baseline Inspection, Notification to Perform Inspection 05000280/2024403 and 05000281- 2024403 ML24141A2512024-05-20020 May 2024 Proposed License Amendment Request - 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[Table view] Category:NRC Bulletin
MONTHYEARML19095A4841977-06-0303 June 1977 Response to IE Bulletin No. 77-01, Provide Study Results Concerning Pneumatic Time Delay Relays 1977-06-03
[Table view] Category:Response to Request for Additional Information (RAI)
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Response to Requests for Additional Information - Set 1 ML19148A4212019-05-10010 May 2019 All Enclosures with Coversheets ML18304A3302018-10-25025 October 2018 Proposed License Amendment Request TSTF-490 & Update of Alternative Source Term Analyses Response to Request for Additional Information & Revised Proposed Technical Specifications ML18302A1212018-10-18018 October 2018 Response to Request for Additional Information, Revised Reactor Vessel Materials Surveillance Capsule Withdrawal Schedules ML18303A2882018-10-18018 October 2018 Response to Request for Additional Information Regarding Relief Request S2-I5-LMT-P01 Examination Category R-A, Preservice Weld Examinations ML18267A0682018-09-18018 September 2018 Attachment - Response to Request for Clarification on Proposed Consolidated Emergency Operations Facility License Amendment Requests 2024-05-07
[Table view] |
Text
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Mr. Norman' o.:Moseley,, DireGtor Ser~al-No. "1'85/042977.
- Office of.Inspection and Enforcement . P(?~l/TAP:dgt. * . -
_* U_~* S. '.Nuc,lea:i::; Re*gul~t(,)ry Comm:ission -* Dod:et . Nos. 50".:.280:
- Region* tr *-* Suite 81S 50-281 23Q Peachtre~- Str~et*,: No:rthwe~*t '. License:* Nos.*. DPiz:..32
_Atlanta~ GE;orgia: 30303 :...- --
Dear:
~ir. ,1'1os*eley: i
. Th:is'. iett~r.:is, :i.n ~~spo{isc' to: iE nulletin:No~' Tl'-01 *co~c.erriin"g
.: pneumatic ,time *delay rel°ays., A. $tudy .ha*s been conducted and we ftnd that
- we ha:ve:*pneumatic:time:<1efay relays _irl. _the foll'owing systems::
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'.a) Emergency Diei~l- Cenerator .*.
. b)
- Turbine *Runback * . . . .
c) Generator Anti-Motoring d) Au~~il i~r'y Feed Pump .
- e).:Insi.de* Recirculation Spray-Pump**
f Y Outside. .Recirculation s*pray *Pump g) Safety* In'jdcl:icm l{es.3t .
-J:i) Undervol tacre * . . .
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. i-Iow~,;er, _the problera of. s*etpoint :drift; as :related in y:our bulletin*;;
was found n'ot .to.be o:E si.~ific~nce at our' Stfrry'.,Units~ 3pecific~l1.y;:*the *
-followin~ r~sp_o:nses. answer your* requests for action at. our_ Surry Units:
Niic Request:..
1} If *you have; be.er1 *. no.tifi~d* of the p~te~ti~l problem.~ i describ~
.. *tl~e' ;,i'c.tions taken regardii:ig, co.rrective**:measures .to identify, and resolve. ariy: sei:point dr:i.ft problems with the 'rTE* time*
The orig':i.nal bill* of electrical, niateri'&l
presentfi installed pl_ant stock* were inspected *. it ;a;s found that none of :the rrk'ltqrial 'was ma.nufactured* b)7 ITE Tolpe:dal*. Theref.ore,-
- **no corrective rne'asures areie1tiired.
- 2) tn additicin to item Labove, pneumatic.-t:Lme delay_-relays,intended for. use 'in safety rel.ate.d
- systems and Specifying a repeii.t. accuracy ..
range of + 15 percent or greater,.shou1d, be demonstrated to:pro'.'" /".'I * . .
.vi.d~ s~t:Gi'fact~ry*,op~rt:t~ion. You.1:1~e*requested .to*:pfovide yo,JJ>7 *.- .
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VIRGINIA ELECTRIC AND POWER COMPANY RICHMOND, VIRGINIA 23261 Mr. Norman C. Moseley, Director Serial No. 185/042977 Office of Inspection and Enforcement PO&M/TAP:dgt
- u. S. Nuclear Regulatory Commission Docket 50-280 Region II - Suite 818 50-230 Peachtree Street, Northwest License Nos. DPR-32 Atlanta, Georgia 30303 DPR-37
Dear Mr. Moseley:
This letter is in response to IE Bulletin No. 77-01 concerning pneumatic time delay relays. A study has been conducted and we find that we have pneumatic time delay relays in the following systems:
a) Emergency Diesel Generator b) Turbine Runback c) Generator Anti-Motoring d) Auxiliary Feed Pump e) Inside Recirculation Spray Pump f) Outside Recirculation Spray Pump g) Safety Injection Reset h) Undervoltage However, the problem of setpoint drift, as related in your bulletin, was found not to be of significance at our Surry Units. Specifically,* the following responses answer your requests for action at our Surry Units:
NRC Request:
- 1) If you have been notified of t~e potential problem, describe the actions taken regarding corrective measures to identify and resolve any setpoint drift problems with the ITE time delay relays.
Response
The original bill of electrical material schedule and the presently installed plant stock were inspected. It was found that none of the material was manufactured by ITE Imperial. Therefore, no corrective measures are required.
NRC Request:
- 2) In addition to item 1 above, pneumatic time delay relays intended for use in safety related systems and specifying a repeat accuracy range of+/- 15 percent or greater should be demonstrated to pro-vide satisfactory operation. You are requested to provide your
Mr. Norman c. Mosele~ Page No. 2 basis for concluding that existing pneumatic time delay relays are functioning as required, or provide your plans to assure satisfactory operation.
Response
, The only pneumatic time delay relays which are used in the emergency diesel generator circuits and other safety related sys-tems are manufactured by Square D and Agastat Control Instruments.
The Square D relay (type E02423-Gl) has a repeat accuracy of+/- 10%.
The Agastat Timing Relay (Series 2400) has a repeat accuracy of *
+/- 5% from 0-200 seconds and+/- 10"/o for longer settings.
Since the specified repeat accuracy of our relays is less than the limit for concern of+ 15% or greater and functional tests verify overall system performance, a program*to demonstrate the satisfactory operation of the presently installed pneumatic time delay relays is unwarranted.
Very truly Keeand Production cc: Mr. Robert w. Reid
.._i:,.P. REGv, _
-. ..:,t,'- ~,,. .. UNITED STATES
.-<I!
- n t'S!lW,~ .*
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0 9NUCLEAR REGULATORY COMMISSION REGION II 230 PE.O.CHTREE STREET, N.W. SUITE 1217
~~1,:*~. \.bJwVt ATLANTA, GEORGIA 30303
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o' APR 2 9 -ran In Reply Refer To:
IE: II :NCM 50-338 50-280 50-339 50-281 50-404 50-405 Virginia Electric and Power Company ATTN:
/
Mr. W. L. Proffitt Senior Vice President P. 0. Box 26666 Richmond, Virginia 23261 Gentlemen:
Enclosed is IE Bul]etin No. 77-01 which requires action by you with regard to your po~er reactor facility(ies) with an operating license or a construction permit.
Should you have questions regarding this Bulletin or the actions required of you, please contact this office.
Sincerely,
Enclosure:
IE Bulletin No. 77-01
NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT WASHINGTON, D. C. 20555 IE BULLETIN 77-01 Date: April 29, 1977 Page 1 of 3 PNEUMATIC TIME DELAY RELAY SETPOINT DRIFT DESCRIPTION OF CIRCUMSTANCES:
Millstone Unit 2 and North Anna Unit 1 facilities experienced repeated diesel-generator starting failures several of which investigation revealed were caused by setpoint drift on the pneumatic time delay relays used in the control circuitry for the diesel-generator. The relays involved are identified as ITE Imperial, Catalog Nos. J20T3/Jl3P20 and J20T3/J13P30. The affected diesel-generators are Fairbanks Morse Units by Colt Industries.
These types of time delay relays are used in several different applications in the control circuitry for the diesel-generator.
One of these relays is used to bypass the normal low oil pressure shutdown functions during diesel-generator startup. At Millstone Unit 2 the relay had drifted approximately 10 seconds from the required 20 second delay which allowed the low oil pressure trip circuit to shut down the diesel-generator before the oil pressure had time to build up. At North Anna Unit 1, excessive drift of similar ITE time delay relays was also observed during preopera-tional testing of the diesel-generators.
ITE Imperial has identified the time delay relays involved at Millstone Unit 2 as coming from the 1972 and 1973 production runs.
The catalog specification for this vintage of relays requires a trip-point setting repeat accuracy of+/- 15 percent. Units manu-factured in 1974 or later have demonstrated a repeat accuracy of
+/- 3 to 4 percent, well within the catalog specification of+/- 15 percent.
- IE Bulletin 77-01 Date: April 29, 1977 Page 2 of 3 Month and year of production for the time delay relays in question can be determined by the six or seven digit bold white number on the timer head. The first two or three digits indicate the month and year or production. (The last four digits provide other coded information.) For example: 124056 indicates a production date of January 1972; 1234056 indicates a production date of December 1973.
According to the time delay relay manufacturers, the potential for setpoint drift is a common characteristic of most pneumatic relays, irrespective of manufacturer. The magnitude of setpoint drift is r.-,elated to the repeat accuracy specified for the device and the mode in which it will operate, that is, energized or de-energized. In most cases energized units tend to be susceptible to greater devia-tions from setpoint because of the temperature effects on the internal parts of the unit.
ACTION TO BE TAKEN BY LICENSEES AND PERMIT HOLDERS:
FOR ALL POWER REACTOR FACILITIES WITH AN OPERATING LICENSE OR CON-STRUCTION PERMIT:
- 1. If you have been notified of the potential problem, describe the actions taken regarding corrective measures to identify and resolve any setpoint drift problems with the ITE time delay relays.
- 2. In addition to Item 1 above, pneumatic time delay relays intended for use in safety related systems and specifying a repeat accuracy range of+/- 15 percent or greater should be demonstrated to provide satisfactory operation. You are requested to provide your basis for concluding that existing pneumatic time delay relays are functioning as required, or provide your plans to assure satisfactory operation.
Reports for facilities with operating licenses should be submitted within 30 days after receipt of this Bulletin, and reports for facilities with construction perm.its should be submitted within 60 days after receipt of this Bulletin. Your report should include the date when the above actions were or will be completed.
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- IE Bulletin 77-01 Date: April 29, 1977 Page 3 of 3 Reports should be submitted to the Director of the NRC Regional Office and a copy should be forwarded to the NRC Office of Inspection and Enforcement, Division of Reactor Inspection Programs, Washington, D, C. 20555.
Approval of NRC requirements for reports concerning possible generic problems has been obtained under 44 U.S.C 3152 from the U. S. General Accounting Office. (GAO Approval B-180255 (R0072), expires 7/31/77)
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