ML20107A012
| ML20107A012 | |
| Person / Time | |
|---|---|
| Site: | Millstone  |
| Issue date: | 02/06/1985 |
| From: | NORTHEAST NUCLEAR ENERGY CO. |
| To: | |
| Shared Package | |
| ML20107A010 | List: |
| References | |
| TAC-56814, NUDOCS 8502190226 | |
| Download: ML20107A012 (23) | |
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1 i APPENDEX Proposed Technical Specification Changes 4 8502190226 yDRADOCKOh0hO36 PDR
e -. POWER DISTRIBUTION LIMITS SURVEILLANCE REQUIREMENTS (Continued) 4.2.1.2 ' Excore Detector Monitoring System - The excore detector monitoring . system may be used for monitoring the core power distribution by:
- a. Verifying at least or.ce per 12 hours that the f ull length CEAs are withdrawn to and maintained at or beyond the Long Term Steady State Insertion Limits of Specification 3.1.3.6.
- b. Verifying at least once per 31 days that the AXIAL SHAPE INDEX alarm setpoints are adjusted to within the allowable limits as required per Technical Specification 3.2.2.
- c. Verifying at least once per 31 days that the AXIAL SHAPE INDEX is maintained within the allowable limits as required per Technical Specification 3.2.2, where 100 percent of the allowable power represents the maximum THERMAL POWER allowed by the existing Reactor Coolant Pump Combination.
4.2.1.3 Incore Detector Monitoring System - The incore detector monitoring system may be used for monitoring the core power distribution by verif ying that the incore detector Local Power Density alarms:
- a. Are adjusted to satisf y the requirements of the core power distribution map which shall be updated at least once per 31 days,
- b. Have their alarm setpoint adjusted to less than or equal to the limits shown on Figure 3.2-1 when the following factors are appropriately included in the setting of these alarms:
- 1. Flux peaking augmentation f actors as shown in Figure 4.2-1.
- 2. A measurement-calculational mcertainty factor of 1.07,
- 3. An engineering uncertainty f actor of 1.03,
- 4. A linear heat rate uncertainty factor of 1.01 due to axial fuel densification and thermal expansion, and
- 5. A THERMAL POWER measurement mcertainty factor of 1.02.
MILLSTONE - UNIT 2 3/42-2 4
1.10
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- 0.2 8.4 g 0.6 AXI AL SHAPE IN.DEX FIGUFIE 32 2b AXIAL SHAPE INDEX vs Fraction of Allowable Poww Level-per Spea.fication 4.2.1.2c . .
4 MILI. STONE - UNIT 2 i 1. 0- ~- R l
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' POWER DISTRIBUTION LIMITS
' TOTAL PLANAR ' RADIAL PEAKING FACTOR - Fly .
LIMITING C'ONDITION FOR OPERATION 3.2.2. ~ Meet either of 3.2.2.1 or 3.2.2.2.
- -3.2.2,1 The calculated value of Fly, defined as Fly = Fxy' (1+Tq), sh'all be limited to 51.62 with the AXIAL SHAPE INDEX alarm setpoints adjusted consistent with the limits shown on Figure 3.2-2a, or 3.2.2.2 The calculated value of F1, defined as Fl limited to $1.719 with the AXIAL [HAPE INDEX r afa=m setpoints adjustedFxy (1+T consistent with the limits shown on Figure 3.2-2b.
1
- APPLICABILITY: MODE 1 *.~
= ACTION:
4 a. With Fly > 1.62 and the AXIAL SHAPE INDEX al' arm setpoints adjusted ' consistent with the limits shown on Figtre 3.2-2a, within 6 hours either: 1
- 1) -Reduce THERMAL POWER to bring the combination of i
THERMAL POWER and Fly to within the limits of Figure 3.2-
-3a and withdraw the full length CEAs to or beyond.the Long .
j Term Steady State Insertion Limit of Specification 3.1.3.6, or.
~
- j. 2) Apply the limits of Specification 3.2.2.2 and Figure 3.2-2b and
! within 72 hours adjust the AXIAL SHAPE INDEX alarm. setpoints consistent with the limits shown on Figure 3.2-2b, or
- 3) Be in at least HOT STANDBY.
) b. With Fly > 1.719 and the AXIAL SHAPE INDEX alarm setpoints adjusted consistent with the limits shown on Figure 3.2-2b, within 6. hours either: i
- 1) - Reduce THERMAL POWER to bring the combination of
. THERMAL POWER and Fly to within the limits of Figure 4
3.2-3b and withdraw the fulllength CEAs to or beyond the
- Long Term Steady State Insertion Limit of Specification .
3.1.3.6, or .
- 2) Be in at least HOT STANDBY.
. *See Special Test Exception 3.10.2 - ' } MILLSTONE - UNIT 2 - 3/42-6 l r k y y g-g-- 3 p.- ,, - w
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POWER DISTRIBUTION LIMITS SURVEILLANCE REQUIREMENTS - 4.2.2.1 The provisions of Specification 4.0.4 are not applicable.-
. 4.2.2.2 FI 'shall be calculated by the expression Fly _ : Fxy (1+Tq) and Fly -
shak! be determined to be within its limit at the following intervals:
- a. Prior to operation above 70 percent of RATED THERMAL POWER after each fuel loading,
- b. At least once per 31 days of accumulated operation in MODE 1, and -
- c. Within four hours if the AZIMUTHAL POWER TILT (T q )is > 0.02.
- 4. 2.2.3 _ Fxy shall be determined each time a calculation of Fly is required by using the incore detectors to obtain a power distribution map with all full length CEAs at or above the Long Term Steady State Insertion Limit for the existing Reactor Coolant Pump combination. This deterr.....ation shall be limited to core planes between 15% and 85% of full core height inclusive and shall i exclude regions influenced by grid effects.
4.2.2.4 Tgshall be determined each time a calculation of Fly si required and the value of Tq used to determine Fly shall be measured value of Tq . i a f MILLSTONE - UNIT 2 3/42-7
- g. ,._
FIGURE 3.2-3a Total Radial' Peaking Factor vs Allowable Fraction of Rated Thermal Power .
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n-, _ 3/4 2-8(b)
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^
e 4 , POWER DISTRIBUTION LIMITS.
' TOTAL INTEGR ATED RADIAL PEAKING F CTOR - FT
' LIMITING CONDITION FOR OPERATION '
- ^ 3.2.3 The calculated value of FTd efined as FT e Fr (1+Tq), shall be limitied to
~
1 1.565.
- APPLICABILITY: MODE 1 *. -
ACTION: .
.With FT >l.565, within 6 hours either:
i
- a. Reduce THERMAL POWER to bring the combination of THERMAL:
POWER and F T to within the limits of Figure 3.2-3b and withdraw the full length CEAs to or beyond the Long Term Steady State Insertion. Limits of Specification 3.1.3.6; or
- b. Be in at least HOT STANDBY.
SURVEILLANCE REOUIREMENTS
- 4. 2.3.1 - The provisions of Specification 4.0.4 are not applicable.
4.2.3.2 FT shall be calculated by the expression FT = F r (1+Tq ) and FTshall-- , be determined'to be within its limit at the following inEervals:
- a. Prior to operation above 70 percent of RATED THERMAL-POWER af ter each fuel loading, J
- b. At least once per 31 days of accumulated operation in Mode 1, and..
- c. Within four hours if the AXIMUTHAL POWER TILT (T 0.020. q )is >
1' y-4.2.3.3 . Fr shall be determined each time a calculation of' F T is required by
- using the incore detectors to obtain a power distribution map wifh all fulllength CEAs at or above the Long Term Steady State Insertion Limit for the existing
. Reactor Coolant Pump Combination.
- 4. 2.3.4 Tqshall be determined each time a calculation of F T is required and the value of Tq used to determine FT shall be the measured value of Tq .
*See Special Test Exception 3.10.2 MILLSTONE - UNIT 2 3/42-9 3 g- ---y -g y 7+ e 9p -
..5 y.
)
January- 31, 1985 WGC-85-G-69 GFL Form 3.010-7.1 April 4, 1983 CORRESPONDENCE FOLLOW SHEET , i TO: GENERATION FACILITIES LICENSING AGENCY LETTER DATE 1/23/85 i FROM: 7fML* DATE OF RECEIPT FROM AGENCY 1/31/85 W. G." tounsil Please distribute the attached document and insure proper and timely action cs per NEO Procedure 3.02 and CFL Procedure 3.01, as appropriate.
SUBJECT:
IE Information Notice No. 85-05: Pipe Whip Restraints All nuclear power reactor- facilities holding an operating license or a construction permit. COMMENTS: COTRAPFILENO:kgyg)6 RAA g R 'JA RTF 09'O, 30 M t. C y, g) KPW COPIES TO: RLM PC 6h fg 8 M S l- - RES
~
7qg zog A4 yag 7'M y /f 6 -T " ymF GLS C55NdYW'y NUCLEAR RECORDS gg7 L. .T ty g g ,3 MP3 CAP Exclusion l6 Frank Dicesare (S&WLIts# #40
-D y(M CY/MPl/MP2/MP3/NRB Chairmen (I&E Insp. Report) M /d m E/)R I&E Bulletins, Circulars and Information Notices to MP-3 Project and to S&W.
7 (n [m2) RESPONSIBILITY - [U( d [(44 Adp% LICENSING LEAD: h TECFNICAL LEAD: TECHNICAL SUPPORT: RESPONSE / RESOLUTION TECHNICAL SUPPORT DUE TO GFL: RESPONSE / ACTION DUE BY GFL: g,/g CO.'DtENTS : l O CY, MILLSTONE 1 & 2 dD ' MILLSTONE 3 & GENERIC k d
's SSINS No.: 6835 IN 85-05 UNITED STATES NUCLEAR REGULATORY COMMISSION 0FFICE OF INSPECTION AND ENFORCEMENT-WASHINGTON, D.C. 20555 RECEIVED January 23, 1985 J.9! 3 1995
'IE INFORf1ATION NOTICE NO. 85-05: PIPE WHIP RESTRAINTS SENIOR VICE PRESIDENT.
- Nuclear Encineering & Dee+!w I
Addressees: All: nuclear-power reactor facilities holding an operating license (OL) or a construction pemit (CP).
Purpose:
4 This infomation notice is provided to alert recipients of a potentially ' 4 significant problem pertaining to the energy absorbing material used in pipe
- whip. restraints. It is expected that recipients will review the infomation for applicability to their facilities and consider actions, if appropriate, to preclude a similar problem occurring at their facilities. However, suggestions
- contained in this information notice do not constitute NRC requirements; therefore, no specific action or written response is required.
Description of Circumstances: The Byron Nuclear Generating Station retested the energy absorbing material
- used in the pipe whip restraints and on October 31, 1984, reported that the dynamic c. rush strength of some samples was considerably lower than the' values used in the design. The "6 KSI" material supplied by HEXCEL/ MCI Division 3
should have a strength between 5,400 and 7,000 psi. The manufacturer's test results were between 5,800 and 6,200 psi, but 40%.of the material from Byron had a' strength between 3,800 and 4,500 psi. In one instance, the dynamic crush l strength was only 2,700 psi. The function of the material is to slow the motion of major. piping, such as the - main steam line, in the event of a double-ended guillotine pipe break. The material is contained within the pipe whip restraint. This structure 'is not intended to serve as a restraint in normal operation or seismic loading.- The material consists of stainicss steel sheets fomed into a honeycomb shape
~
l i and ioined by a nickel brazing alloy. The product is in the fom of rectangu-lar plates up to 36 in. in length, width, or depth. . HEXCEL manufactured the material for the Byron Nuclear Generating Station in
~
1978 and 1979. A recent audit by the Office of Inspection and Enforcement-found that an acceptable quality. assurance program was not-in effect during the period from 1978 to 1982. This material has been supplied by HEXCEL~to other [ nuclear generating stations. It is not known if the material supplied by other-j vendors was.made by HEXCEL. 8501230229 _ . _ _ . _ _ . _ _ _ . . u_ c__.._.___._ __ , 2 . _ . - _ _ . . _ _ _ , _ . _ , _ _ , .
IN 85-05 January 23,1985 Page 2 of 2 The licensee is conducting a further investigation and assessing the impact on the unit. HEXCEL is continuing their internal investigation. It should be noted that separate from this specific problem the NRC is presently _ reviewing the pipe break criteria to determine if some whip restraints may be eliminated.
~
'No specific action or written response is required by this information notice.
If you have any questions about _this matter, please. contact the Regional
-Administrator of the. appropriate NRC regional office or this office.
W
/.
. -l 4*2 / 4. .
7-dEdw' d Jordan, Director Divisi of Emergency Preparedness and ' ngineering Response Office of Inspection and Enforcement Technical
Contact:
P. Cortland, IE (301)492-4175
Attachment:
List of'Recently Issued IE Information Notices i i 1 i
o < Attachment IN 85-05 January 23, 1985 LIST OF RECENTLY ISSUED IE INFORMATION NOTICES Information Date of Notice No. Subject Issue Issued to 85-04 Inadequate Management Of 1/17/85 All power reactor Security Response Drills facilities holding an OL or CP, & fuel fabrication & pro-cessing facilities 85-03 Separation Of Primary Reactor 1/15/85 All pressurized water Coolant Pump Shaft And power reactor Impeller facilities holding an i OL or CP 85-02 Improper Installation And 1/15/85 All power reactor Testing Of Differential facilities holding Pressure Transmitters an OL or CP 85-01 Continuous Supervision Of 1/10/85 All material licensees Irradiators possessing irradiators that are not self-shielded and contain more than 10,000 curies of radioactive material 84-94 Reconcentration Of Radio- 12/21/84 All NRC materials nuclides Involving Discharges licensees other than Into Sanitary Sewage Systems licensees that use Permitted Under 10 CFR 20.303 sealed sources only 84-93 Potential For Loss Of Water 12/17/84 All power reactor From The Refueling Cavity . facilities holding - an OL or CP 84-92 Cracking Of Flywheel On 12/17/84 All power reactor Cummins Fire Pump Diesel facilities holding Engines an OL or CP 84-91 Quality Control Problem 12/10/84 All power reactor Of Meteorological facilities holding Heasurements Problems an OL or CP OL = Operating License CP = Construction Permit
-January 29, 1985 WGC-85-CY-008 CFL Form 3.010-7.1 April 4, 1983 CORRESPONDENCE FOLLOW SHEET ,
TO: GENERATION F ILITIES- ENSING AGENCY LETTER DATE 1/22/85 FROM: fM7 DATE OF RECEIPT FROM AGENCY l/29/85 W. K Counsil Please distribute the attached document and insure proper and timely action as per NEO Procedure 3.02 and GFL Procedure 3.01, as appropriate.
SUBJECT:
Notice of Violation (Inspection No. 50-213/84-24) Occupational Radiation Exposure. COMMENTS: Response requested within 30 days. COIRAP FILE NO: p p/g p gag gz 7 Ug CF5 COPIES TO: R4. 4f #4 FC. yFOS#Jt Y.TD l* 6RP
' NUCLEAR RECORBS l /,f/W MP3 CAP Exclusions }to Frank Dicesare (S&W) G, gox R d /f " " heyd CY/MPl/MP2/MP3/NRB Chairmen (I&E Insp. Report)
I&E Bulletins, Circulars and Information Notices to MP-3 Project and to S&W. (( RESPONSIBILITY Nac. Ogas LICENSING LEAD: W TECHNICAL LEAD: /J m @
~
TECHNICAL SUPPORT: RESPONSE / RESOLUTION //s . Op5 TECHNICAL SUPPORT DUE TO ePL-r [edruc ec /% /M
RESPONSE
COMMENTS:
/ ACTION DUE BY N . fedre,ar[: /, /93 5 Asc, ops J The NRC hcu, c.h o s e n &o c m u ck a. Sewdy L ev e. l Ill w '. h c o fine for th'i s incidew+. t%h Wd R c_y c h theec violed' sons foc 000. E f ('O ('.
D MILLSTONE 3 & GENERIC [L! d t. A - A ,/ $ _ i
. -. - =. . .- - ._ _ - .
m a
) 'ok UNITED STATES
?8 o NUCLEAR REGULATORY COMMISSION 4
$ l ~
REGION I 631 PARK AVENUE i KING OF PRUSSIA, PENNSYLVANIA 19406 January 22, 1985 Docket No. 50-213. EA 84-133- . RECEIVED Connecticut Yankee Atomic Power Company '19!201985 2 ATTN: Mr. W. G. Counsil l Senior Vice President -' Nuclear SENIOR VICE PRESIDENT
~,
Engineering and Operations Group Nedear Engineering & Opere'W P. O. Box 270 l Hartford, Connecticut 06101 Gentlemen:
Subject:
Notice of Violation (Inspection No. 50-213/84-24) This refers to the special NRC safety inspection conducted on October 22-23, i 1984 at the Haddam Neck Nuclear Power Plant, Haddam Neck, Connecticut, of 4 activities authorized by NRC License No. DPR-61. The report.of the inspection was forwarded to you on November 23, 1984. The inspection was conducted to review the circumstances associated with an unplanned occupational radiation exposure, in excess of that planned for a work activity,'to one of your employees. The unplanned exposure was identified on October 13, 1984 and reported to the NRC by your staff on October 15, 1984. On December 6, 1984, an enforcement conference was held with Mr. C. F. Sears and other members of i your staff during which the exposure, the associated violations, the cause of the violations, and your corrective actions were discussed. l Although the unplanned occupational radiation exposure received by the l individual was not in excess of regulatory limits, the violations which are i described in the enclosed Notice, are of concern to the NRC because adequate
- radiological controls over the performance of the work activity'were not
!' implemented, thereby creating a substantial potential for a radiation exposure in e,xcess of regulatory limits. Specifically, a Junior Health Physics Technician assigned the responsibility of providing radiological control coverage during the work activity was not qualified to perform the task. As a result, adequate
- coverage was not provided during the activity and the unplanned exposure
- occurred.
l The violations associated with this exposure have been categorized in the aggregate as a Severity Level III problem in accordance with the NRC Enforcement Policy, 10 CFR Part 2, Appendix C, as revised, 49 FR 8583 (March 8, 1984). Although a civil penalty was' considered for this Severity Level III problem, I have decided, after consultation with the Director, Office of Inspection and Enforcement, not to propose a civil penalty in this case.t In making this' decision, I have considered that: (1) you reported the event to the NRC; (2) your immediate and long-term corrective actions were
--....---45 r - ,,,- ,. - -,.,,__..,_y - , , , , , . ,- - . _ , . _ . - , ,
Connecticut Yankee Atomic 2 Power Company prompt and comprehensive; and (3) in light of your history of satisfactory performance in.this area, the event appears'to be an isolated occurrence rather than ind" ative of a programmatic weakness (performance in the radiological controls area was rated to be Category 1 in the last two NRC Systematic Assessments of Licensee Performance conducted for your facility). However, we emphasize that similar violations in the future may result in additional , enforcement action. You are required to respond to the enc 1csed Notice and should follow the instructions specified therein when preparing your response. Your written reply to this letter and the results of future. inspections will be considered in determining whether further enforcement action is appropriate. In accordance witn 10 CFR 2.790, a copy of this letter and its enclosure will-be placed in the NRC Public Document Room. The responses directed by this letter and the enclosed Notice are not subject to the clearance procedures of the Office of Management and Budget, otherwise required by the Paperwork Reduction Act of 1980, PL 96-511. Sincerely, Thomas E. Murley Regional Administrator
Enclosure:
Notice of Violation l cc w/ enc 1: 1 R. Graves, Plant Superintendent D. O. Nordquist, Manager of Quality Assurance R. T. Laudenat, Manager, Generation Facilities Licensing-J. F. Opeka, Vice President, Nuclear Operations Gerald Garfield, Esquire Public Document Room (PDR) Local Public Document Room (LPDR) Nuclear Safety Information Center (NSIC) NRC Resident Inspector State of Connecticut J O 4 r . -
+ e NOTICE OF VIOLATION Connecticut Yankee Atomic Docket No. 50-213 Power Company License No. DPR-61 Haddam Neck Nuclear Power Plant EA 84-133 On October 22-23, 1984, an NRC special safety inspection was conducted to
. review the circumstances associated with a reported occupational radiation _
exposure of 3.309 rems to the upper right arm of a worker during an attempted retrieval.of a wrench which had inadvertently been dropped into the secondary side of one of the steam generators. The_ radiation exposure was identified by the licensee on October 13, 1984 and reported to the.NRC on October 15, 1984. Altnough the exposure was subsequently determined to be less' than the regu-latory limit (3 rems), a substantial potential _ for exposure in excess of regulatory limits existed during the wrench recovery operation because adequate radiological controls were not implemented. The radiation exposure occurred while the worker'had his right arm inserted in the secondary side of Steam Generator No.1 through a handhole as part of the retrieval operation. The individual worked in this position for approximately 30 minutes. Although the Junior Health Physics (HP) Technician assigned to provide job radiological control coverage during the retrieval operation checked the monitoring devices on the worker after 15 minutes and noted a reading of 1250 mrem on the upper right arm, the Junior HP Technician erroneously concluded that the monitoring device was in error and allowed the worker to resume his activities for another 15 minutes after all monitoring devices were rezeroed. After observing a reading of 1400 mrem on the upper right arm of the worker after the second 15 minute interval, the worker and the Junior HP Technician vacated the area. The Junior HP Technician had been assigned the job of radiological control coverage of the wrench recovery operation on October 13, 1984 by the Senior Station HP Technician assigned as coordinator of steam generator activities. However, the Junior HP Technician did not possess the required years of experieace and had not received the appropriate training required for providing such coverage. t These events demonstrate the importance of your having adequate radiological controls over activities performed within the facility. In accordance with the General Statement of Policy and Procedure for NRC Enforcement Actions,10 CFR Part 2, Appendix C, as revised, 49 FR 8583 (March 8, 1984), the violations are set forth below: 2 A. Technical Specification 6.3.1 requires that each member of the facility staff meet or exceed the minimum qualifications of ANSI N18.1'1971 for comparable positions.
~
-l
. 1. > l
- LNotice'o'f' Violation 2 Section 4.5.2 of ANSI N18.1-1971 requires, in'part, that technicians in p i responsible positions' have:a' minimum of two years .of working experience
+ in their specialty. , p , l l Contrary to above, on October 13,1984, ~ a Junior Health Physics Technician P 'was assigned the responsibility of providing radiological control for.the. ,
. Steam Generator No. I wrench recovery operation with less than one year- l working experience in her s'peciality. >
~B. Techn'ical Specification 6.4.1 requires, in part, a replacement training -
F program for facility staff in accordance with Section 5.5 of ANSI-1 N18.1-1971. ! Section 5.5 of ANSI N18.1-1971 requires, in~part, special training sessions j for replacement personnel. l ' Contrary to the above, on October 13, 1984, a Junior Health Physics (HP) l Technician was assigned as a replacement Health Physics Technician, _with i ! the responsibility for providing radiological control . coverage during the , l retrieval of a wrench from the secondary side of Steam Generator No. 1, but
- the Junior HP Technician had not received any special training in station
! radiation protection procedures. f C. Technical Specification 6.13.1(c) requires, in part, a health physics qualified individual-(1.e., qualified in radiation protection procedures) with a
- radiation dose monitoring device to provide positive control over work l activities in high radiation areas.
- Contrary to the above, on October 13, 1984, a Junior. Health Physics :
Technician was assigned the responsibility of providing radiological con-i- trol coverage during the recovery of a wrench from the secondary side of ! Steam Generator No. 1, a high radiation area, but the technician did not I provide positive control over work activities and was not. qualified to j provide such coverage in that_she had not received the necessary training i and did not possess the required two years of radiation control experience i , .as described in Items A and B above. ! Collectively, these violations have been categorized as a Severity Level III ,
- problem (Supplement IV). .
L , 1 Pursuant to the provisions. of 10 CFR 2.201, Connecticut Yankee Atomic Power.
- Company is hereby required to submit to this office, within 30 days of the date
! of.this Notice, a written statement or explanation including for each alleged j violation: (1) admission'or denial of the alleged violation; (2).the reasons 1 : 1 I i j. < _._",__ _ ., _ . ._ _ _ ,__ _ _ _ ._ . . _ . _ . . . . . _ . - _ _ . . . . . . ~ . . , .
v- . 4 Notice of' Violation 3 for the violation, if admitted; (3) the corrective steps which have been taken
~
and the results achieved; (4) the corrective steps which will be taken to avoid; further violations; (5) the date when full compliance will be achieved. Consid-eration may be given to extending the response time for good cause shown. FOR THE NUCLEAR REGULATORY COMMISSION Thomas E. Murley Regional Administrator 4 King of Prussia, Pennsylvania j Dated thi s 22"a) day of January 1985. I L 4 i I
1 January 31,~1985 WGC-85-G-69 i I GFL Form 3.010-7.1 April 4, 1983 : CORRESPONDENCE FOLLOW SHEET , I TO: GENERATION FACILITIES LICENSING AGENCY LETTER DATE' 1/23/85 FROM: 7&d/A ' _ DATE OF RECEIPT FROM AGENCY 1/31/85 W. G." toons11 Please distribute the attached document and insure proper and timely action cs per NEO Procedure 3.02 and GFL Procedure 3.01, as appropriate.
SUBJECT:
IE Informa tion Notice No. 85-05: Pipe Whip Restraints All nuclear power reactor facilities holding an operating license or a construction permit. COMMENTS: COTRAP FILE NO: [ g g 76 Ryg KJA RTF JO M t. d gg RPk1 COPIES TO: RLM Pc &h SW, M S t- . o zg myg s*e l? Sts NUCLEAR RECORDS R.se 7 LJN T/W A0 # TMF T. C TG d'$5t1] R E S (SW<s#(Niuarm
#Ad MP3 CAP Exclusion lstfo Frank Dicesare E4D yt M CY/MP1/MP2/MP3/NRB Chairmen (I&E Insp. Report) M Ad M '
I&E Bulletins, Circulars and Information Notices to MP-3 Project and to S&W. 7 (pg [m) RESPONSIBILIIY - [U( d E(24 4[0% LICENSING LEAD: hh TECFNICAL LEAD: TECHNICAL SUPPORT: RESPONSE / RESOLUTION TECHNICAL SUPPORT DUE TO GFL:
RESPONSE
COMMENTS: / ACTION DUE BY GFL: M 1 0 I ! CY, MILLSTONE 1 & 2 'b [kd i MILLSTONE 3 & GENERIC
. ._ . __ ._ _ . _ _ __ .. _~ .
9_ f ,' n SSINSNo.:-L6835 IN 85 E UNITED STATES NUCLEAR. REGULATORY. COMMISSION 4' 0FFICE OF, INSPECTION AND ENFORCEMENT-WASHINGTON,-D.C..:205551
~ RECEIVED January 23,~1985 P.M 311985 IE11NFORf1ATION NOTICE-NO.~ 85-05: PIPE WHIP R'ESTRAINTS SENIOR.VICE PRESIDENT Nudear Enaineering & 0 er**!cy
' Addressees:. '
t All: nuclear power reactor facilities-holding:an operating license (OL) or a j; construction. permit (CP).
Purpose:
1 This information notice is provided to alert recipients of a potentially significant problem pertaining to the energy. absorbing material used in pipe whip restraints. It is expected that recipients will review the information .
> for applicability to their facilities and consider actions, if appropriate, to -
{ preclude a similar problem occurring at their facilities. However, suggestions contained in this information notice do not constitute NRC requirements; l therefore, no specific action or written response is required.- l Description of Circumstances: ! The Byron Nuclear Generating Station reteste'd the energy absorbing material ! used in the pipe whip restraints and on October 31, 1984, reported that the i dynamic crush strength of some samples was considerably lower than the values t used in the design.' The "6 KSI" material supplied by HEXCEL/ MCI Division- - should have a strength between 5,400 and 7,000 psi. The manufacturer's. test-results were between 5,800 and 6,200 psi, but 40% of the material from Byron i had a strength between 3,800 and 4,500 psi. In one instance, the dynamic crush ' j strength was only 2,700 psi. The function of the material-is to slow the motion of major piping, such as the main steam line, in the event of a double-ended guillotine pipe break. The
- material is contained within the pipe whip restraint. This structure.is not
! intended to serve as a restraint in normal operation or seismic loading.- i- ! The material consists of stainless steel sheets fomed into a honeycomb shape l- and joined by a nickel brazing alloy. The product is in the form of rectangu-j lar plates'up to 36 in. in. length, width, or-depth. i HEXCEL manufactured the material for the Byron Nuclear Generating Station in - l' 1978 and 1979. A recent audit by the Office of Inspection and Enforcement-found that an acceptable quality assurance program was not in effect during .the
- period from 1978.to 1982. This material has been supplied by HEXCEL To other j nuclear generating stations. It is not known if the material supplied by other i vendors was made.by HEXCEL.
r. i i
.8501230229
~~
t y 3 O e-IN 85-05 January 23, 1985 Page 2 of 2 The licensee is conducting a further investigation and assessing the impact on the unit. HEXCEL is continuingitheir internal investigation. It should be noted that separate from this specific problem the NRC is presently reviewing the pipe _ break criteria to' determine if some whip restraints may be eliminated. No specific action or written response is required by this information notice. If-you have any questions about this matter, please contact the Regional Administrator of- the appropriate NRC regional office or this office.
/
/ -Edw,_d e2d .
Jordan, Director Divisi of Emergency Preparedness and ' ngineering Response Office of Inspection and Enforcement Technical
Contact:
P. Cortland. IE (301)492-4175
Attachment:
List of Recently Issued IE Information Notices 4
~
bo Attachment IN 85-05 January 23, 1985 LIST OF-RECENTLY ISSUED IE INFORMATION NOTICES
~
Information Date of. Notice No. Subject Issue Issued to 85-04 Inadequate Management Of 1/17/85 All power reactor Security Response Drills facilities holding an OL-or CP, & fuel fabrication & pro-cessing facilities 85-03 Separation Of Primary Reactor 1/15/85 All pressurized water Coolant Pump Shaft And power reactor Impeller facilities holding an
- OL or CP 85-02 Improper Installation And 1/15/85 All power reactor Testing Of Differential facilities holding Pressure Transmitters an OL or CP 85-01 Continuous Supervision Of 1/10/85 All material licensees Irradiat~ ors possessi_ng irradiators that are not self-shielded and contain more than 10,000 curies of radioactive material 84-94 Reconcentration Of Radio- 12/21/84 All NRC materials nuclides Involving Discharges licensees other than Into Sanitary Sewage Systems licensees that use Permitted Under 10 CFR 20.303 sealed sources only
, 84-93 Potential For Loss Of Water 12/17/84 All power reactor l From The Refueling Cavity facilities holding I an OL or CP I 84-92 Cracking Of Flywheel On 12/17/84 All power reactor Cuarnins Fire Pump Diesel facilities holding Engines an.0L-or CP
-All power reactor
(.' 84-91 Quality Control Problem Of Meteorological 12/10/84 facilities holding Measurements Problems an OL or CP l OL = Operating License l CP = Construction Pennit l
.}}