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| | number = ML20153D167 | | | number = ML20205N658 |
| | issue date = 08/24/1988 | | | issue date = 10/24/1988 |
| | title = Discusses Equipment Qualification Insp Rept 50-423/88-04 on 880314-18 & Forwards Notice of Violation.One Violation Discussed at Enforcement Conference Re Qualification of Cable Has Been Reclassified to Unresolved Item.W/O Notice | | | title = Ack Receipt of 880801 Ltr Informing NRC of Steps Taken to Correct Violations Noted in Insp Rept 50-423/88-04 Re Heat Shrink Tubing Over Braided Cable Jacketing.Response Re Other Raychem Installations at Plant Needs Clarification |
| | author name = Johnston W | | | author name = Martin T |
| | author affiliation = NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) | | | author affiliation = NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| | addressee name = Mroczka E | | | addressee name = Mroczka E |
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| | license number = | | | license number = |
| | contact person = | | | contact person = |
| | document report number = EA-88-177, NUDOCS 8809020064 | | | document report number = NUDOCS 8811040264 |
| | document type = CORRESPONDENCE-LETTERS, NRC TO UTILITY, OUTGOING CORRESPONDENCE | | | document type = CORRESPONDENCE-LETTERS, NRC TO UTILITY, OUTGOING CORRESPONDENCE |
| | page count = 2 | | | page count = 4 |
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| ,- AUG 24 M8 Docket N License No. NPF-49 EA No. 88-177 Northeast Nuclear Energy Company ATTN: Mr. E. J. Mroczka Senior Vice President - Nuclear Engineering and Operations Group P. O. Box 270 Hartford, Connecticut 06141-0270 Gentlemen:
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| Subject: EQ Inspection Report No. 50-423/88-04 This letter refers to the equipment qualification inspection conducted on March 14-18, 1988 at the Millstone Power Station, Unit 3. The inspection report (NRC No. 50-423/88-04) was sent to you on July 6,198 Based on the results of that inspection it appears that certain of your acti-vities were not conducted in full compliance with NRC requirements, as set forth in the Notice of Violation, enclosed herewith as Appendix At the time of the inspection, two items (50-423/88-04-05 and 50-423/88-04-07) were identi-fied as potential enforcement items. Based on subsequent information furnished by you at the Enforcement Conference, July 20, 1988, the NRC has categorized these as violations in accordance with the "General Statement of Policy and Procedure for NRC Enforcement Actions," 10 CFR Part 2, Appendix C (Enforcement Policy). Our determination considered that the unqualifiable Litton-V connectors were only associated with position indication functions for contain-ment isolation valves that were in different safety system In addition, we noted that you appropriately placed administrative controls over the valves and that the v11ves were closed, thus, minimizing any safety significance. One potential violation discussed at the enforcement conference (50-423/88-04-02) | | OCT 2 41988 . |
| relating to the qualification of GA HRRM cable has been reclassified to an
| | Docket No. 50-423 Northeast Nuclear Energy Company ATTN: Mr. E. J. Mroczka i Senior Vice President- Nuclear Engineering and Operations Group P.O. Box 270 Hartford, Connecticut 06141-0270 Gentlemen: |
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| | Subject: Inspection No. 50-423/88-04 This refers to your letter dated August 1,1988, in response to our letter dated June 6, 1988. |
| unresolved item based on information provided at the conferenc You are required to respond to this lette In preparing your response, you should follow the instructions in Appendix The responses directed by this letter and the accompanying notice are not subject to the clearance procedures of the Office of Management and Budget as required by the Paperwork Reduction Act of 1980, PL 96-51 OFFICIAL RECORD COPY EQ LTR MILLSTONE 88-04 - 0001. /18/88 8809020064 880924 J
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| | Thank you for informing us of the corrective and preventive actions, documented in your letter to resolve Violation 50-423/88-04-06 relating to heat shrink ! |
| | tubing over braided cable jacketing, j Your response to statements in inspection report E0-423 regarding other Raychem l installations at Millstone 3 with bend radius or splice seal length deficiencies needs clarification. We discussed the bend radius deficiencies with your staff in a telephone conversattor on October 13, 1988. We understand that your installation specification E-350 and installation instructions PII-57100-A did not include explicit guidance regarding Raychem splice bend radius limits. |
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| | However, we understand that these documents did reference a Raychem document that did specify limits on splice bend radius. This infcrmation was available before the splices were installed at Millstone 3 in January 1986. With regard to our statements regarding deficient splice seal lengths with teal lengths less than two inches, we understand that your staff's review of this issue did not identify any instances at Millstone 3 where kaychem splices were installed with less than a 2-inch seal length. |
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| | We request that you respond to this letter. Your response should address I corrective steps to addrass Raychem splice bend radius deficiencies at - |
| | Millstone 3; corrective steps to avoid further bend radius deficiencies and the date when bend radius deficiencies will be corrected. |
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| | OFFICIAL RECORD COPY RL MILL 3 88-04 - 0001.0.0 g |
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| | 10,'21/88 e Okto c> $ # *W 14-*1 R(7&%$vb6 t' M If el n ) |
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| . . | | . . OCT 8 419?3 Northeast Nuclear Energy Company -2-Your cooperation with us is appreciated. |
| Northeast Nuclear Energy Company -2-Your cooperation with us in this matter is appreciate | |
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| Sincerely, ORIGINAL. Slci'm "I WILLIAf1 V. J0rmma William V. Johnston, Director Division of Reactor Safety Enclosure: Notice of Violation, Appendix A cc w/ enc 1: | | Sincerely, Crigiral Cicntd Eyt Clifford J. A lercon Thomas T. Martin, Director Division of Reactor Safety Enclosure: Application Guide cc w/ enc 1: |
| W. D. Romberg, Vice President, Nuclear Operations 0. O. Nordquist, Director of Quality Services R. M. Kacich, Manager, Generation Facilities Licensing S. E. Scace, Station Superintendent Public Document Room (POR) | | W. D. Romberg, Vice President, Nuclear Operations D. O. Nordquist, Director of Quality Services R. M. Kacich, Manager, Generation Facilities Licensing S. E. Jcace, Station Superintendent Public Document Room (POR) |
| Local Public Document Room (LPOR) | | Local Public Document Room (LPDR) |
| Nuclear Safety Information Center (NSIC) | | Nuclear Safety Information Center (NSIC) |
| NRC Senior Resident Inspector State of Connecticut bec w/ enc 1: | | NRC Senior Resident Inspec. tor State of Connecticut bec w/ enc 1: |
| Region I Docket Room (with concurrences) | | Region I Docket Room (with concurrences) |
| Management Assistant, ORMA (w/o enc 1)
| | M=;==t ^.::iztut, DPE(v/c encl)- |
| ORP Section Chief S. Pindale RI, Beaver Valley W. Raymond, SRI, Millstone 1&2 R. Ferguson, LPM, NRR R. Lores, DRSS J1 &
| | DRP Section Chief S. Pindale, RI, Beaver Valley W. Raymond, SRI, Millstone 1&2 D. Jaffe, LPM, NRR R. Bores, DRSS |
| Cf4 RI:0RS 6}(
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| | C Iq Cf Q RI:DRS RI:DRh RI:DRS Paolino Anderson Durr 10/ft/88 10/If/88 10N/88 0FFICIAL RECORD COPY RL MILL 3 88-04 - 0001.0.1 10/18/88 |
| RI:0RS</s RI:E0 R L, | | |
| A Paolino/ki/rw Anderson Johnsth Holody Russell 8/sf*/88 8/ / y/38 8// f/88 8/9/88 8/ M 8
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| (P,6 , o , f a 0FFICIAL RECORD COPY EQ LTR MILLSTONE 88-04 - 0001. /18/88 9 /Y I | | ; |
| | WCSF-N Application |
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| | Sp*CNketion: Descripth:m: |
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| | i Heat ShnnkaNe Tutung WCSF.N ; |
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| | 3.3.3 CLEAN AND DEGREASE cable jacket and wire moulatert with a solvent (such as b |
| | V t t.1 trichloroethane) whch is approved by the cable matlufacturer. All surf aces must be free of grease, oils, moisture or other contaminaats proof to being brought into contact with Psychem products. |
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| | Cable preparaton kits are avadable from Raychem: Kit No. CPK-0140 (contains 6 solvent wipes and I abrasive cloth). |
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| | 3.4 Detail inetsNetion instructione 3.4.1 When shims are required (refer to Section 2.4). INSTALL SHIMS on the wire. |
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| | Abgn to within %" of the insulation (or jacket) cutback. SHRINK IN PLACE. |
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| | 3.4.3 SUDE THE SPLICE SEALING SLEEVE over enhor wire to be sphced. DO NOT SHRINK. If a bolt pad is required (refer to Section 2.3.3) side bolt pad over enhor wire to be sphced. DO NOT SHRINK. |
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| | 3.4.3 MAKE CONDUCTOR CONNECTIONS. Examine each connection area for sharp edges or protrudog wire strands. Remove these with an abrasive cloth or file. |
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| | 3.4.4 When bott pad is required. CENTER THE BOLT PAD over the connecton area. |
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| | SHRINK IN PLACE. |
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| | 3.4.5 CENTER THE SPLICE SEALING SLEEVE over the connecten area. Where shims are used, it must overlap the outer shim. SHRINK IN PLACE. |
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| | 3.4.6 DO NOT FLEX spbce untd comfortable to touch. It may then be formed to a max-imum five times the outside diameter bend radius. DO NOT VIOLATE CABLE SEND RADIUS. |
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| | 4.0 inopoetion of installation Tubing is "funy recovered" when both of the following critena are met: |
| | 1. O tter surface is smooth and has a glossy appearance. |
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| | 2. Inere is a visible flow of adhesive at each end of the tubing. (The outer sleeve is not required to shrink down to the cable or enNbit adhesive flow where it overtaps a shim ) |
| | 4.1 Overheating Overheatmg of the tubing must ce avoided. This is evidenced by scorching or bhstering on the surface. Any minor surface scorching that can be removed by solvtfit cleaning is acceptable. Tubing wah deep blistereg must be replaced. |
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| | 4.3 Underheating WCSF N tubing which has a lumpy appearance not conforming to the substrate of has a dut surf ace has not been heated sufficiently. Underheatog can be cot-rected at any twne by reheating and contmuing the thrmking process. |
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| | NORTHEAST UTILITIES o.n.ru on.c.. . s.io.n sir..i. 8.n.n. cen.ci.cui L |
| APPENDIX A NOTICE OF VIOLATION Northeast Nuclear Energy Company Docket No. 50-423 Millstone Nuclear Power Station, Unit 3 License No. NPF-49 As a result of the equipment qualification inspection on March 14-18, 1988, and in accordance with the "General Statement of Policy for NRC Enforcement Actions,"
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| 10 CFR Part 2, Appendix C, the following violation was identified:
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| 10 CFR 50.49, paragraph (f) requires that each item of electrical equipment important to safety be qualifie Contrary to the above, on March 18, 1988 NRC inspectors identified Litton-Veam connectors in safety related systems whose qualification had not been adequately established for use in a harsh environment. Forty three Litton-Veam connectors were identified for which a definitive long-term (i.e., 40 years) qualified life could not be determined with available test results. However, sufficient test information was available for un-aged connectors to demonstrate that these connectors would perform their intended function for the near term until the June 1989 scheduled refueling outage, at which time the licensee has committed to replace these connector Contrary to the above, on March 18, 1988 NRC inspectors identified Litton-Veam connectors installed in safety related sys+. ems that did not include the protective Raychem Heat Shrink Tubing specified in procedure No. VAp-241. Two cases (four connectors), involving position indication for two containment isolation valves, were found that were required to remain functional to mitigate the event causing the local harsh environmen These items are a Severity Level IV violation (Supplement I). | | * |
| | [[mTIcfm'o'. CONNECTICUT 061410 non us-sooo August 1, 1988 Q1cket No. SQ !?] |
| | 6911kB Re: 10 CFR 50.49 Mr. William V. Johnston, Acting Director Division of Reactor Safety U.S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406 |
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| | ==Dear Mr. Johnston:== |
| | Millstone Nuclear Power Station, Unit No. 3 Response to Notice of Violation inspection Report No. 50-423/88 04 1. INTRODUCTION By letter dated July 6,1988, the NRC transmitted its Inspection Report No. 50-423/88 04 and associated Notice of Violation relating to the Region I Staff's announced inspection of March 14-18, 1988, of Millstone Nuclear Power Station, Unit No. 3. In its letter the Staff identified one Severity Level IV violation, four sotential violations, and three unresolved items. The Staff requestec that Northeast Nuclear Energy Company (NNECO) respond to the Notice of Violation within 30 days of the date of the Inspection Report. In addition, the Staff requested NNECO to attend an enforcement conference to discuss the four potential viola-tions. This enforcement conference was held on July 20, 1988. At this meeting, NNECO provided information regarding the potential violation pertaining to Raychem splices. At the conclusion of this portion of our presentation, the Staff suggested that NNECO include that information when responding to the subject Notice of Violation. By this letter, NNECO responds to the Notice of Violation and the potential violation regarding Raychem splices. |
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| | II. EEt0][$PONSE TO V10L41103 . |
| | NNEr0's response to the Severity Level IV violation identified by the Staff is set forth below: |
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| | A. Staff Statement of the Vigttlig.n |
| | "10 CFR 50.49, paragraph (f), requires that electrical equipment important to safety must be qualified by test and/or analysis, dU Q b50"I 6fY' |
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| | Mr. William A07358/Page 2 August 1, 1988 i Contrary to the above, on March 18, 1988, the NRC identified Raychem cable splices installed in safety related EQ equipment that did not meet the requirements in that the heat shrink tubing was applied over braided cable jacketing. This was not a qualified configura-tion prior to the time of new test data, dated March 1987, which determined the splices were qualified. |
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| | This is a Severity Level IV violation, Supplement I." |
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| | B. NNECO Statement of Position NNECO does not contest the Notice of Violation as stated and accordingly admits there was insufficient documentation in the files to support the installation of Raychem splice over braided cable jacketing prior to March 1987. |
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| | C. Root Cause Craft personnel failed to follow the specified vendor product installation procedure during installation of these Raychem splices. |
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| | D. Corrective Steos Tilta |
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| | This installation was discovered on March 16, 1988, during the plant walkdown phase of Inspection No. 50 423/88 04. Qualification of this configuration was previously demonstrated by test in March 1987. This test data had been evaluated and included in the i |
| | Millstone Unit No. 3 Raychem qualification file prior to the inspec-I tion. |
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| | ; E. (orrective Actions to Prevent Recurrence The following corrective actions have been implemented: |
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| | 1. Craft personnel have received additional training to emphasir i |
| | the importance of following all specified procedures during d |
| | component installations, p 2. Craf t, inspection, supervisory, and engineering personnel have received specific Raychem installation training conducted by qualified Raychem Corporation representatives. |
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| | F. Due for Full Como11an_tt |
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| | Full compitance was achieved in March 1987. Pursuant to the requirements of 10 CFR 50.49, paragraph (f), this Raychem configura-tion was qualified by test as of that time. |
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| | Mr. William V. Johnsten A07358/Page 3 August 1, 1988 III. RELATED POTENTIAL VIOLATION 88 04 06 j A. Statement of the Issue |
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| | NRC Inspection Report Issue 50 423/88 04 06 states, "a review of j ' |
| | licensee walkdown records for Raychem splices indicate (s) additional i' nonconforming conditions involving excessive splice bends (less than u the recommended 5X outside cable di meter) and splice seal length |
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| | areas of less than 2 inches." Accorjing to the Staff, these def t-ciencies constitute a potential violation of 10 CFR 50.49 in that |
| | ; x the splices were not qualified per the instruction procedures in effect at the time of the installation. |
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| | , [ 8. hNECO Position Regardina the Existence of a Violation 1 NNECO does not agree with the Staff's conclusions that installation V of Raychem splices with a bend radius less than SX the outside cable f diameter was contradictory to the Raychem procedure / instructions existing at that time. NNECO followed existing procedures with regard to these installations at the time the plant went into operation. |
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| | NNECO also does not agree that the Millstone Unit No. 3 walkdown records indicate that the Raychem installation had splice lengths of s less than two inches. |
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| | s C. fltsis for Denyino that a Deficiency Existed |
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| Pursuant to the provisions of 10 CFR 2.201, Northeast Nuclear Energy Company ,
| | [ The original installation of the splices was made in accordance with Millstone Unit No. 3 Electrical Installation Specification No. E-350. This procedure stated that Raychem installation instructions shall be in accordance with Raychem's "Product Installation and Inspection Guide WrSF N Heavy Wall, Flame Retarded Nuclear Cable Sleeves" (Pil-57100 A) and installation instructions provided with each kit. E 350 also states that |
| is hereby required to submit to this office within thirty days of the date of the letter which transmitteJ this Notice, a written statement or explanation in reply, including: (1) the corrective steps which have bien taken and the results achieved: (2) corrective steps which will be taken to avoid further violations; and (3) the date when full compliance will be achieved. Where good cause is shown, consideration will be given to extending this response time, o .
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| | s specifications) that proper Raychem components are used, |
| | - manufacturer's installation instructions have been followed, |
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| 0FFICIAL RECORD COPY EQ LTR MILLSTONE 88-04 - 0003. /18/88
| | and an acceptable splice has been made. |
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| | , During the time at which Raychem Product Guide PII 57100 A |
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| | (November 1982) was in effect, Raychem did not specify bend radius acceptance criteris. Accordingly, contrary to the inspection report findings, the Raychem installations were made J' , in accordance with procedures in existence at that time. Upon l \.' issuance of NRC Information Notice 86 53 (June 26, 1986), NNECO pj gjf,3 a %u 7hd |
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| | Mr. William A07358/Page 4 August 1, 1988 took reasonable and prudent actions to address the issue. Bend radius criteria were first published in PII-57100 D (November 1987). 4 g?7 2. Seal Lenath Contrary to the NRC inspection report, NNE W s review of walkdown records does not reveal any instances whera Raychem splices with less than 2 inch seal lengths ex t!;t. NNECO Quality Control personnel witnessed the installation of some of ; |
| | the splices and did not note any such deficiencies in seal length. NNECO had no other indications that such deficiencies in seal length exist. Therefore, NNECO denies that the alleged deficiency in seal length existed. It should be noted that after issuance of Information Notice 86-53, in which this issue ; |
| | was raised, NNECO took reasonable and prudent actions to address it. * |
| | D. Safety Sianificance These issues have no safety significance because the March 1987 testing has established that a bend radius much less than 5X the outside diameter and seal lengths much less than 2 inches are qualified configurations. Accordingly, no replacements or modifica- < |
| | tions of the components were required to establish or maintain qualification. |
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| | E. Other Factors that Should Be Considered 1. Notwithstanding the final determination regarding the existence of a violation, craft personnel have received additional training to emphasize the importance of following procedures I during component installations. |
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| | 2. In addition to the above, specific Raychem training was provided by Raychem personnel to ensure that installations were correct. |
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| | 3. The EQ file was revised prior to the inspection to include test data (dated March 1987) that confirms the qualification of Raychem splices less than a 2 inch seal length and bends of less than 5X the outside diameter of the cable. The Staff has . |
| | concurred with the acceptability of the March 1987 report to ! |
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| | further establish qualification. (See Inspection l Report 50 423/88 04 at p. 21.) i |
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| | Mr. William A07358/Page 5 August 1, 1988 If you have questions regarding the information contained in this letter, please contact us. |
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| | Very truly yours, NORTHEAST NUCLEAR ENERGY COMPANY d |
| | MroczkV Se for Vice President cc: W. T. Russell, Region I Administrator D. H. Jaffe, NRC Project Manager, Millstone Unit No. 3 W. J. Raymond, Senior Resident inspector, Millstone Unit Nos. 1, 2, and 3 U.S. Nuclear Regulatory Comission Document Control Desk Washington, D.C. 20555 STATE OF CONNECTICUT ss. Berlin COUNTY OF HARTFORD Then personally appeared before me E. J. Mroczka, who being duly sworn, did state that he is Senior Vice President of Northeast Nuclear Energy Company, a Licensee herein, that he is authorized to execute and file the foregoing information in the name and on behalf of the Licensee herein, and that the statements contained in said information are true and correct to the best of d his knowledge and belief. |
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Category:CORRESPONDENCE-LETTERS
MONTHYEARDD-99-12, Informs That Time Provided by NRC Regulation within Which Commission May Act to Review DD-99-12 Has Expired.With Certificate of Svc.Served on 9910281999-10-28028 October 1999 Informs That Time Provided by NRC Regulation within Which Commission May Act to Review DD-99-12 Has Expired.With Certificate of Svc.Served on 991028 ML20217N8261999-10-25025 October 1999 Discusses Errata Re 991021 Filing of Northeast Nuclear Energy Co Answer to Request for Hearing & Petition to Intervene B17901, Submits Statement of Personal Qualification (NRC Form 398) Along with Supporting Certification of Medical Exam by Facility Licensee (NRC from 396) in Support of License Renewal for PM Miner.Encls Withheld,Per 10CFR2.790(a)(6)1999-10-18018 October 1999 Submits Statement of Personal Qualification (NRC Form 398) Along with Supporting Certification of Medical Exam by Facility Licensee (NRC from 396) in Support of License Renewal for PM Miner.Encls Withheld,Per 10CFR2.790(a)(6) B17886, Requests Permission to Utilize Code Case N-623, Deferral of Insps of Shell-to-Flange & Head-to-Flange of Reactor Vessel,Section Xi,Div 1, for Millstone Unit 21999-10-18018 October 1999 Requests Permission to Utilize Code Case N-623, Deferral of Insps of Shell-to-Flange & Head-to-Flange of Reactor Vessel,Section Xi,Div 1, for Millstone Unit 2 05000336/LER-1999-012, Forwards LER 99-012-00,re Unrecoverable CEA Misalignment Entry Into TS 3.0.3 on 990917.Commitments Made by Util Are Encl1999-10-15015 October 1999 Forwards LER 99-012-00,re Unrecoverable CEA Misalignment Entry Into TS 3.0.3 on 990917.Commitments Made by Util Are Encl B17900, Forwards Revised Assumptions Used in Fuel Handling Accident Analysis & Summary of Results.List of Regulatory Commitments Are Listed in Attachment 11999-10-14014 October 1999 Forwards Revised Assumptions Used in Fuel Handling Accident Analysis & Summary of Results.List of Regulatory Commitments Are Listed in Attachment 1 ML20217G9491999-10-14014 October 1999 Forwards Exemption from Requirements of 1-CFR50,App E, Section IV.F.2.c,re Conduct of full-participation Exercise in Sept 1999,at Plant,Units 1,2 & 3 ML20217D9671999-10-12012 October 1999 Forwards Copy of Transcript of Public Meeting Held by NRC Staff & NNECO on 990825 at Waterford,Connecticut on Decommissioning Program for Millstone,Unit 1.Without Encl ML20217D3011999-10-0707 October 1999 Forwards Request for Addl Info Re Util 990118 Request for Amend to License NPF-49 to Allow full-core Offloads to Spent Fuel Pool During Core Offloads to Spent Fuel Pool During Core Offload Events ML20217F0031999-10-0606 October 1999 Forwards Original Petition to Intervene Being Filed on Behalf of Clients,Connecticut Coalition Against Millstone & Long Island Coalition Against Millstone,Iaw Provisions of 10CFR2.714 ML20217P1201999-10-0606 October 1999 Informs NRC of Proposed Acquisition of Parent Holding Company of Central Maine & Requests NRC Concurrence,Based on Threshold Review,That Proposed Acquisition Does Not,In Fact, Constitute Transfer Subject to 10CFR50.80 B17892, Requests Withdrawal of License Amend Application Re 24-month SG Tube Insp Surveillance Extensions,Submitted in Util 950726 & s to NRC1999-10-0505 October 1999 Requests Withdrawal of License Amend Application Re 24-month SG Tube Insp Surveillance Extensions,Submitted in Util 950726 & s to NRC ML20217B4711999-10-0404 October 1999 Informs That Staff Did Not Identify Any Safety Concerns Re Licensee Proposals to Modify Commitments Made for Action Items 4.2.1,4.2.2,4.5.1 & 4.5.2 of GL 83-28 by Providing Addl Justifications or Safety Bases for Changes ML20212K1241999-10-0101 October 1999 Responds to Recent Ltrs to Chairman Jackson,Commissioners & Wd Travers,Expressing Concern Re Millstone Npps.Nrc Continues to Monitor Performace of Millstone to Ensure That Public Health & Safety,Adequately Protected ML20212J3051999-10-0101 October 1999 Discusses GL 97-06 Re Degradation of SG Internals,Dtd 971230.GL Requested Each PWR Licensee to Submit Info That Will Enable NRC Staff to Verify Whether PWR SG Internals Comply & Conform to Current Licensing Basis for Facilities ML20212L2081999-10-0101 October 1999 Responds to Recent Ltrs to President Wj Clinton,Chairman Jackson & Commissioners & Wd Travers,Expressing Concerns Re Millstone NPPs & Continued Lack of Mgt Plan for Eastern Long Island.Nrc Continues to Monitor Plant Performance ML20212J9991999-10-0101 October 1999 Responds to Recent Ltr to President Clinton,H Clinton, Chairman Jackson &/Or Wd Travers Expressing Concern Re Millstone Npps.Nrc Continues to Monitor Performance of Plant to Ensure That Public Health & Safety Adequately Protected ML20212L1971999-10-0101 October 1999 Responds to Recent Ltr to Chairman Jackson & Commissioners Expressing Concerns Re Millstone NPPs & Continued Lack of Emergency Mgt Plan for Eastern Long Island.Nrc Continues to Monitor Plant Performance to Ensure Public Health & Safety ML20212J2451999-10-0101 October 1999 Informs That Util 980807 & 990629 Responses to GL 98-01, Y2K Readiness of Computer Sys at NPPs Acceptable.Nrc Considers Subj GL to Be Closed for Units 2 &3 ML20212L1831999-10-0101 October 1999 Responds to Recent Ltr to Wd Travers Expressing Concerns Re Millstone NPPs & Continued Lack of Emergency Mgt Plan for Eastern Long Island.Nrc Continues to Monitor Performance of Millstone to Ensure Adequate Protection to Public Health ML20212L2171999-10-0101 October 1999 Responds to Recent Ltr to President Wj Clinton,Chairman Jackson & Commissioners,Wd Travers & Ferc,Expressing Concerns Re Millstone NPPs & Continued Lack of Emergency Mgt Plan for Eastern Long Island ML20217A9271999-09-30030 September 1999 Discusses Investigation Conducted at Millstone Nuclear Power Station by NRC OI Region I on 980319 to Determine If Contract Training Instructor Was Terminated for Raising Concerns About Quality of Training Matls ML20217B3221999-09-30030 September 1999 Refers to Investigation Rept 1-1997-035 Conducted at Millstone Nuclear Power Station by NRC Ofc of Investigation Field Ofc,Region I on 970915 to Determine Whether Former Health Physics Technician Discriminated Against ML20212J6621999-09-30030 September 1999 Informs of Completion of mid-cycle PPR of Units 2 & 3 on 990916.Identified Several Recent Instances in Which Condition Repts Were Not Initiated,Resulting in Untimely or Inadequate C/As.Historical Listing of Plant Issues Encl B17887, Requests Exemption from Requirements of 10CFR140.11(a)(4) Which Requires Licensees to Maintain Secondary Financial Protection Beyond Primary Layer1999-09-28028 September 1999 Requests Exemption from Requirements of 10CFR140.11(a)(4) Which Requires Licensees to Maintain Secondary Financial Protection Beyond Primary Layer ML20216J1341999-09-28028 September 1999 Ltr Contract:Task Order 49, Millstone Units 2 & 3 Employee Concerns Program Insp, Under Contract NRC-03-98-021 B17883, Forwards Mnps Unit 3 ISI Summary Rept,Cycle 6, IAW ASME Section XI,IWA-62301999-09-27027 September 1999 Forwards Mnps Unit 3 ISI Summary Rept,Cycle 6, IAW ASME Section XI,IWA-6230 B17890, Provides Response to GL 99-02, Laboratory Testing of Nuclear-Grade Activated Charcoal1999-09-27027 September 1999 Provides Response to GL 99-02, Laboratory Testing of Nuclear-Grade Activated Charcoal B17888, Informs That There No Longer Exists Need to Maintain Millstone Unit 2 SRO License for CA Hines,License SOP-10741-01,effective 9909151999-09-24024 September 1999 Informs That There No Longer Exists Need to Maintain Millstone Unit 2 SRO License for CA Hines,License SOP-10741-01,effective 990915 B17884, Forwards NRC Form 536, Operator Licensing Exam Data, for Mnps,Units 2 & 3,per Administrative Ltr 99-031999-09-24024 September 1999 Forwards NRC Form 536, Operator Licensing Exam Data, for Mnps,Units 2 & 3,per Administrative Ltr 99-03 ML20212F4961999-09-20020 September 1999 Forwards Insp Repts 50-245/99-08,50-336/99-08 & 50-423/99-08 on 990615-0809.Four Violations of NRC Requirements Occurred & Being Treated as Ncvs,Consistent with App C of Enforcement Policy 05000336/LER-1999-001, Forwards LER 99-001-00 Re Thermal Reactor Power Limit That Was Exceeded.Commitments Made by Util Encl1999-09-20020 September 1999 Forwards LER 99-001-00 Re Thermal Reactor Power Limit That Was Exceeded.Commitments Made by Util Encl B17867, Requests Relief from Requirements of 10CFR50.55a(g),IAW ASME Section XI for Millstone,Unit 3.Util Requests Relief from Performing Visual Exam of Reactor Pressure Supports to Extent Required by Code for Class 1 Supports1999-09-17017 September 1999 Requests Relief from Requirements of 10CFR50.55a(g),IAW ASME Section XI for Millstone,Unit 3.Util Requests Relief from Performing Visual Exam of Reactor Pressure Supports to Extent Required by Code for Class 1 Supports B17865, Provides NRC Staff with Updated Proposed Rev of FSAR Section 14.6.3, Radiological Consequences of SG Tube Failure. Updated Proposed Rev Will Replace Info Provided in Attachment 3 of Initial Submittal1999-09-16016 September 1999 Provides NRC Staff with Updated Proposed Rev of FSAR Section 14.6.3, Radiological Consequences of SG Tube Failure. Updated Proposed Rev Will Replace Info Provided in Attachment 3 of Initial Submittal B17876, Informs That Util Will Adopt Last Approved Northeast Util QA Program (Nuqap) Tr,Rev 21,dtd 990630,as Unit 1 Nuqap,Per Decision to Permanently Cease Operations at Subject Plant1999-09-16016 September 1999 Informs That Util Will Adopt Last Approved Northeast Util QA Program (Nuqap) Tr,Rev 21,dtd 990630,as Unit 1 Nuqap,Per Decision to Permanently Cease Operations at Subject Plant B17882, Forwards NRC Forms 398 & 369 in Support of License Renewal for Bb Parrish,License SOP-10399-2.Encl Withheld Per 10CFR2.790(a)(6)1999-09-15015 September 1999 Forwards NRC Forms 398 & 369 in Support of License Renewal for Bb Parrish,License SOP-10399-2.Encl Withheld Per 10CFR2.790(a)(6) B17881, Forwards NRC Form 398 & NRC Form 396 for Le Olsen,License SOP-10398-2.Encl Withheld Per 10CFR2.790(a)(6)1999-09-15015 September 1999 Forwards NRC Form 398 & NRC Form 396 for Le Olsen,License SOP-10398-2.Encl Withheld Per 10CFR2.790(a)(6) B17859, Forwards up-to-date Distribution Lists for NRC Correspondence to NNECO & NUSCO.Side-bars Indicate Changes from Previous Lists Provided to NRC on 9801281999-09-15015 September 1999 Forwards up-to-date Distribution Lists for NRC Correspondence to NNECO & NUSCO.Side-bars Indicate Changes from Previous Lists Provided to NRC on 980128 B17880, Forwards NRC Form 398 & NRC Form 396 for Rf Martin,License SOP-10397-0.Encls Withheld Per 10CFR2.790(a)(6)1999-09-15015 September 1999 Forwards NRC Form 398 & NRC Form 396 for Rf Martin,License SOP-10397-0.Encls Withheld Per 10CFR2.790(a)(6) B17872, Informs of Election to Consolidate Previous Commitments Re Work Observation Program with Two New Programmatic Commitments Listed in Attachment 11999-09-14014 September 1999 Informs of Election to Consolidate Previous Commitments Re Work Observation Program with Two New Programmatic Commitments Listed in Attachment 1 ML20212A9011999-09-10010 September 1999 Forwards Environ Assessment & Finding of No Significant Impact Re Application for Exemption,Dtd 990803.Proposed Exemption Would Provide Relief from Requirement of 10CFR50 ML20212A3171999-09-10010 September 1999 Discusses Investigation Rept 1-1998-045 Conducted on 981112 to Determine If Former Senior Health Physics Technician Being Denied Employment at Millstone in Retaliation for Having Raised Safety Concerns in Past.Synopsis Encl B17838, Forwards Revs 34 & 35 to Physical Security Plan.Explanation of Changes Provided as Attachment 1.Without Encls1999-09-10010 September 1999 Forwards Revs 34 & 35 to Physical Security Plan.Explanation of Changes Provided as Attachment 1.Without Encls ML20212A7501999-09-10010 September 1999 Forwards Staff Requirements Memo Response,Dtd 990525,which Provides Actions NRC Plans for Continued Oversight of safety-conscious Work Environ & Employee Concerns Program ML20211J9291999-09-0303 September 1999 Forwards mark-ups & Retypes of Proposed Conforming License Changes Required in Connection with Transfers Being Sought in 990615 Application of Montaup Electric Co & New England Power Co for Transfer of Licenses & Ownership Interests ML20211K5171999-09-0202 September 1999 Expresses Appreciation for Support Provided for NRC Public Meeting on 990825 05000336/LER-1999-010, Forwards LER 99-010-00,documenting 990804 Event of Failure to Perform ASME Section XI IST on Pressurizer Relief Line Flow Control Sample Valve Following Maint Activities.List of Util Commitments Contained in Attachment 11999-09-0202 September 1999 Forwards LER 99-010-00,documenting 990804 Event of Failure to Perform ASME Section XI IST on Pressurizer Relief Line Flow Control Sample Valve Following Maint Activities.List of Util Commitments Contained in Attachment 1 ML20216H0591999-09-0202 September 1999 Responds to Re Issues Submitted by Cullen on Behalf of Several Petitioners Concerning Offsite Emergency Prepardeness for Millstone Nuclear Power Station ML20211N9241999-09-0101 September 1999 Forwards Document Classification Form for Insertion Into Emergency Planning Services Department Procedures ML20211H0741999-08-30030 August 1999 Discusses GL 92-01,Rev 1, Rv Structural Integrity, Issued by NRC on 950519 & NNECO Responses for Millstone Unit 2 & 980715.Informs That Staff Revised Info in Rvid & Released Info as Rvid Version 2 Based on Response Review 1999-09-30
[Table view] Category:NRC TO UTILITY
MONTHYEARML20062F4991990-11-16016 November 1990 Forwards List of Unimplemented GSIs at Facilities,Per Generic Ltr 90-04.Timely Completion Requested ML20062G2441990-11-16016 November 1990 Forwards Combined Insp Repts 50-245/90-23,50-336/90-25 & 50-423/90-23 on 901001-05.No Violations Noted ML20217A6661990-11-15015 November 1990 Requests Addl Info Concerning Boraflex Degradation in Millstone 2 Spent Fuel Pool Storage Racks to Support Review of Util 901001 Submittal.Info Re Gamma Doses to Boraflex Matl During Blackness Testing & Storage Patterns Requested ML20058J1111990-11-14014 November 1990 Forwards Safety Insp Rept 50-423/90-19 on 900905-1015 & Notice of Violation ML20217A2021990-11-0909 November 1990 Forwards Insp Repts 50-213/90-83,50-245/90-82 & 50-336/90-82 & 50-423/90-83 on 900924-28.No Violations Noted ML20217A0821990-11-0505 November 1990 Forwards Safety Insp Rept 50-336/90-18 on 900822-1001 & Notices of Violation & Deviation ML20058F7061990-11-0101 November 1990 Forwards Amend 47 to License DPR-21 & Safety Evaluation. Amend Deletes Requirement That Combined Time Interval for Any Three Consecutive Surveillance Intervals Not to Exceed 3.25 from Tech Spec 1.0.X ML20062D5441990-10-30030 October 1990 Confirms 901018 Telcon Re Possible Unanalyzed Condition Re Repairs for Steam Generator Tube Plugs in Mar 1989 ML20058C3761990-10-30030 October 1990 Ack Receipt of & Payment of Civil Penalty in Amount of $25,000 for Violations Re Main Steam Line High Flow Setpoints & Gas Turbine Generator Surveillance Testing ML20058G3421990-10-29029 October 1990 Forwards Exam Rept 50-245/90-10OL Administered During Wk of 900827 ML20058E5871990-10-26026 October 1990 Discusses Programmed Enhancements for Generic Ltr 88-17, Loss of Dhr ML20058E6201990-10-26026 October 1990 Forwards Safety Insp Repts 50-245/90-19,50-336/90-21 & 50-423/90-17 on 900904-07.No Violations Noted ML20058E0931990-10-25025 October 1990 Advises That Schedule for Installation of Alternate Ac Acceptable,Per 900925 Response to Station Blackout Rule ML20058G6121990-10-25025 October 1990 Advises That 900926 Response to Station Blackout Evaluation Acceptable,Based on Installation of Alternate Ac Prior to Startup ML20062C7041990-10-24024 October 1990 Forwards Environ Assessment & Finding of No Significant Impact Re 900418 Request from Section IV.F.3 of App E to 10CFR50,Section IV.F.3 ML20058D5601990-10-24024 October 1990 Forwards Team Insps 50-213/90-82,50-245/90-81,50-336/90-81 & 50-423/90-82 on 901001-12 ML20058G0151990-10-23023 October 1990 Forwards Exemption to 10CFR50,App E,Section IV.F.3 Re Conduct of Full Participation Emergency Exercise,Per 900418 & 0801 Ltrs ML20058A9791990-10-17017 October 1990 Forwards Insp Rept 50-336/90-19 on 900910-14.No Violations Noted ML20058B3181990-10-17017 October 1990 Ack Receipt of Forwarding Payment of Civil Penalty in Amount of $50,000.Penalty Not Mitigated IR 05000336/19900271990-10-17017 October 1990 Forwards Operator Exam Rept 50-336/90-27OL on 901003.Exam Results:Operator Passed Retake Exam ML20058E0661990-10-16016 October 1990 Forwards SE Granting 900926 Request for Relief from ASME Code Inservice Insp Requirements to Repair Svc Water Sys ML20062B8831990-10-12012 October 1990 Extends Invitation to Attend 910220-21 Util Symposium/ Workshop in King of Prussia,Pa Re Engineering Role in Plant Support ML20062B8751990-10-12012 October 1990 Extends Invitation to Attend 910220-21 Util Symposium/ Workshop in King of Prussia,Pa Re Engineering Role in Plant Support ML20059N4061990-10-0303 October 1990 Forwards Safety Evaluation Accepting pressure-temp Limits Re Generic Ltr 88-11.Current pressure-temp Limits for Heatup, Cooldown,Leak Test & Criticality of RCS Acceptable ML20059N9681990-10-0303 October 1990 Forwards Partially Withheld Safeguards Insp Repts 50-245/90-16,50-336/90-17 & 50-423/90-16 on 900827-31 & Notice of Violation ML20059N3291990-10-0202 October 1990 Forwards Response to Comments Contained in Util Re Installation of Hardened Wetwell Vent IR 05000336/19900091990-10-0101 October 1990 Ack Receipt of 900727 & 0907 Ltrs Informing NRC of Steps Taken to Correct Violations Noted in Insp Rept 50-336/90-09. Actions Will Be Examined During Future Insps ML20059M1471990-09-27027 September 1990 Ack Receipt of & Payment of Civil Penalty in Amount of $50,000 Proposed by NRC .Corrective Actions Will Be Examined During Future Insps ML20059M0471990-09-14014 September 1990 Advises That NRC Does Not See Need for Formal Relief from ASME Code Section XI to Repair Leak in Svc Water Piping ML20059J8621990-09-12012 September 1990 Grants 900911 Request for Temporary Waiver of Compliance from Tech Spec Table 3.2.2 Re Containment Spray Interlock ML20059J7621990-09-12012 September 1990 Forwards Amend 45 to License DPR-21 & Safety Evaluation. Amend Changes Tech Spec Section 3/4.5.C by Adding Operability & Surveillance Requirements for Mods Made to Tie Breakers 14A to 14G ML20059F3301990-08-29029 August 1990 Forwards Safety Evaluation Accepting Util 890417,0530 & 900330 Responses Concerning Method of Dealing W/Station Blackout Provided Util Make Mods,Procedure Changes & Calculations Discussed.Technical Evaluation Rept Also Encl ML20059C8261990-08-28028 August 1990 Forwards Safety Insp Repts 50-245/90-11,50-336/90-12 & 50-423/90-09 on 900611-15 & 25-29.No Violations Noted ML20059D7281990-08-27027 August 1990 Requests Listed Ref Matls Needed for Senior Reactor Operator Licensing Exams Scheduled for Wk of 901112.Completed License Applications Required 30 Days Before Exam Date ML20059E2201990-08-24024 August 1990 Forwards Radiological Controls Insp Repts 50-245/90-14, 50-336/90-15 & 50-423/90-13 on 900723-27.One Noncited Violation Identified ML20059D7341990-08-23023 August 1990 Forwards Safety Insp Rept 50-423/90-10 on 900612-0723 & Notice of Violation.Util Should Respond to Violation Re Inaccurate Statement in LER 90-013 Concerning Rev of Procedure by Following Instructions in Encl App a ML20059J8481990-08-16016 August 1990 Forwards Training Effectiveness Team Insp Rept 50-423/90-06 on 900604-08.Training Programs Well Implemented & Personnel Effectively Trained.Few Weaknesses Identified ML20058M7711990-08-0909 August 1990 Requests Addl Info Re License Amend Application Under Generic Ltr 87-09 for Facility.Affirms That Remedial Measures Prescribed for Affected Action Statements Consistent W/Updated SAR & Supporting Safety Analysis ML20056A9451990-08-0707 August 1990 Forwards Insp Rept 50-423/90-80 on 900416-25.Weaknesses Identified ML20058N0581990-08-0606 August 1990 Discusses Licensee Engineering Initiatives.Other Power Reactor Licenses in Region 1 Encouraged to Start Similar Initiative to Provide for Sharing of Info & Experiences Involving Engineering & Solutions of Problems Common to All ML20058M5361990-08-0606 August 1990 Forwards Review of Westinghouse Rept WCAP-12277, Westinghouse Owners Group Bounding Evaluation for Pressurizer Surge Line Thermal Stratification, Per NRC Bulletin 88-011 ML20056A6901990-08-0101 August 1990 Forwards Insp Rept 50-336/90-11 on 900530-0711.No Violations Noted ML20058L3331990-07-25025 July 1990 Forwards Safety Insp Repts 50-245/90-13,50-336/90-13 & 50-423/90-11 on 900609-13.No Violations or Deviations Noted ML20055J2121990-07-25025 July 1990 Advises That Review of Cen 387-P, C-E Owners Group Pressurizer Surge Line Flow Stratification Evaluation, Concludes Adequate Bases Not Provided That Facility Meets All Appropriate Code Limits for 40-yr Plant Life ML20056A3551990-07-24024 July 1990 Forwards Requalification Exam 50-336/90-10OL-RQ on 900618-22 IR 05000245/19900081990-07-23023 July 1990 Discusses Insp Rept 50-245/90-08 on 900510-25 & Forwards Notice of Violation & Proposed Imposition of Civil Penalty. Violation Occurred on 900507 When Stated Cask Arriving at Barnwell,Sc Found to Contain Contaminated Water ML20055H3621990-07-23023 July 1990 Grants Temporary Waiver of Compliance Re Facility Tech Spec 3.6.6.1, Supplemental Leak Collection & Release Sys ML20055J2711990-07-20020 July 1990 Forwards Safety Insp Rept 50-245/90-09 on 900515-0625 & Notice of Violation ML20055H7621990-07-19019 July 1990 Forwards Safety Evaluation Re Util 871030 Inservice Testing (IST) Program & Requests for Relief.Ist Program & Other Info Submitted by 871030 & s,Together W/Granting of Relief W/Conditions Acceptable for 10-yr Insp Interval IR 05000245/19900051990-07-16016 July 1990 Discusses Insp Rept 50-245/90-05 on 900221-0402 & Forwards Notice of Violation & Proposed Imposition of Civil Penalty 1990-09-27
[Table view] Category:OUTGOING CORRESPONDENCE
MONTHYEARDD-99-12, Informs That Time Provided by NRC Regulation within Which Commission May Act to Review DD-99-12 Has Expired.With Certificate of Svc.Served on 9910281999-10-28028 October 1999 Informs That Time Provided by NRC Regulation within Which Commission May Act to Review DD-99-12 Has Expired.With Certificate of Svc.Served on 991028 ML20217G9491999-10-14014 October 1999 Forwards Exemption from Requirements of 1-CFR50,App E, Section IV.F.2.c,re Conduct of full-participation Exercise in Sept 1999,at Plant,Units 1,2 & 3 ML20217D9671999-10-12012 October 1999 Forwards Copy of Transcript of Public Meeting Held by NRC Staff & NNECO on 990825 at Waterford,Connecticut on Decommissioning Program for Millstone,Unit 1.Without Encl ML20217D3011999-10-0707 October 1999 Forwards Request for Addl Info Re Util 990118 Request for Amend to License NPF-49 to Allow full-core Offloads to Spent Fuel Pool During Core Offloads to Spent Fuel Pool During Core Offload Events ML20217B4711999-10-0404 October 1999 Informs That Staff Did Not Identify Any Safety Concerns Re Licensee Proposals to Modify Commitments Made for Action Items 4.2.1,4.2.2,4.5.1 & 4.5.2 of GL 83-28 by Providing Addl Justifications or Safety Bases for Changes ML20212J3051999-10-0101 October 1999 Discusses GL 97-06 Re Degradation of SG Internals,Dtd 971230.GL Requested Each PWR Licensee to Submit Info That Will Enable NRC Staff to Verify Whether PWR SG Internals Comply & Conform to Current Licensing Basis for Facilities ML20212L1831999-10-0101 October 1999 Responds to Recent Ltr to Wd Travers Expressing Concerns Re Millstone NPPs & Continued Lack of Emergency Mgt Plan for Eastern Long Island.Nrc Continues to Monitor Performance of Millstone to Ensure Adequate Protection to Public Health ML20212J9991999-10-0101 October 1999 Responds to Recent Ltr to President Clinton,H Clinton, Chairman Jackson &/Or Wd Travers Expressing Concern Re Millstone Npps.Nrc Continues to Monitor Performance of Plant to Ensure That Public Health & Safety Adequately Protected ML20212J2451999-10-0101 October 1999 Informs That Util 980807 & 990629 Responses to GL 98-01, Y2K Readiness of Computer Sys at NPPs Acceptable.Nrc Considers Subj GL to Be Closed for Units 2 &3 ML20212K1241999-10-0101 October 1999 Responds to Recent Ltrs to Chairman Jackson,Commissioners & Wd Travers,Expressing Concern Re Millstone Npps.Nrc Continues to Monitor Performace of Millstone to Ensure That Public Health & Safety,Adequately Protected ML20212L1971999-10-0101 October 1999 Responds to Recent Ltr to Chairman Jackson & Commissioners Expressing Concerns Re Millstone NPPs & Continued Lack of Emergency Mgt Plan for Eastern Long Island.Nrc Continues to Monitor Plant Performance to Ensure Public Health & Safety ML20212L2171999-10-0101 October 1999 Responds to Recent Ltr to President Wj Clinton,Chairman Jackson & Commissioners,Wd Travers & Ferc,Expressing Concerns Re Millstone NPPs & Continued Lack of Emergency Mgt Plan for Eastern Long Island ML20212L2081999-10-0101 October 1999 Responds to Recent Ltrs to President Wj Clinton,Chairman Jackson & Commissioners & Wd Travers,Expressing Concerns Re Millstone NPPs & Continued Lack of Mgt Plan for Eastern Long Island.Nrc Continues to Monitor Plant Performance ML20212J6621999-09-30030 September 1999 Informs of Completion of mid-cycle PPR of Units 2 & 3 on 990916.Identified Several Recent Instances in Which Condition Repts Were Not Initiated,Resulting in Untimely or Inadequate C/As.Historical Listing of Plant Issues Encl ML20217A9271999-09-30030 September 1999 Discusses Investigation Conducted at Millstone Nuclear Power Station by NRC OI Region I on 980319 to Determine If Contract Training Instructor Was Terminated for Raising Concerns About Quality of Training Matls ML20217B3221999-09-30030 September 1999 Refers to Investigation Rept 1-1997-035 Conducted at Millstone Nuclear Power Station by NRC Ofc of Investigation Field Ofc,Region I on 970915 to Determine Whether Former Health Physics Technician Discriminated Against ML20216J1341999-09-28028 September 1999 Ltr Contract:Task Order 49, Millstone Units 2 & 3 Employee Concerns Program Insp, Under Contract NRC-03-98-021 ML20212F4961999-09-20020 September 1999 Forwards Insp Repts 50-245/99-08,50-336/99-08 & 50-423/99-08 on 990615-0809.Four Violations of NRC Requirements Occurred & Being Treated as Ncvs,Consistent with App C of Enforcement Policy ML20212A9011999-09-10010 September 1999 Forwards Environ Assessment & Finding of No Significant Impact Re Application for Exemption,Dtd 990803.Proposed Exemption Would Provide Relief from Requirement of 10CFR50 ML20212A7501999-09-10010 September 1999 Forwards Staff Requirements Memo Response,Dtd 990525,which Provides Actions NRC Plans for Continued Oversight of safety-conscious Work Environ & Employee Concerns Program ML20212A3171999-09-10010 September 1999 Discusses Investigation Rept 1-1998-045 Conducted on 981112 to Determine If Former Senior Health Physics Technician Being Denied Employment at Millstone in Retaliation for Having Raised Safety Concerns in Past.Synopsis Encl ML20211K5171999-09-0202 September 1999 Expresses Appreciation for Support Provided for NRC Public Meeting on 990825 ML20211H0741999-08-30030 August 1999 Discusses GL 92-01,Rev 1, Rv Structural Integrity, Issued by NRC on 950519 & NNECO Responses for Millstone Unit 2 & 980715.Informs That Staff Revised Info in Rvid & Released Info as Rvid Version 2 Based on Response Review ML20211H9971999-08-27027 August 1999 Forwards Insp Rept 50-423/99-07 on 990614-0715.Violations of NRC Requirements Occurred Re Adequacy of C/As for Organizational Changes & Being Treated as NCVs DD-99-09, Informs That Time Provided by NRC Regulation within Which Commission May Act to Review Director'S Decision (DD-99-09) Expired.Commission Declined Any Review & Decision Became Final on 990823.With Certificate of Svc.Served on 9908261999-08-26026 August 1999 Informs That Time Provided by NRC Regulation within Which Commission May Act to Review Director'S Decision (DD-99-09) Expired.Commission Declined Any Review & Decision Became Final on 990823.With Certificate of Svc.Served on 990826 ML20211F5841999-08-23023 August 1999 Discusses Proposed Rev 21 to Northeast Utils Quality Assurance Program TR for NRC Review & Approval,Iaw 10CFR50.54 ML20211D5701999-08-20020 August 1999 Informs That in May 1999,Northeast Nuclear Energy Co, Restarted Millstone Nuclear Power Station,Unit 2.Licensee Has Been Tasked Charter with Listed Specific Responsibilities ML20211C4621999-08-18018 August 1999 Discusses Rev to TS Bases Sections 3/4.5.2 & 3/4.5.3, Emergency Core Cooling Sys Subsystems ML20210S9611999-08-13013 August 1999 Informs That NRC Received Encl Ltr from Pb Johnston Expressing Concern About Certain Impacts on Shareholders of New England Electric Sys with Respect to Nees Proposed Merger with Natl Grid Group ML20210S9511999-08-13013 August 1999 Responds to to Collins Expressing Concerns with Certain Terms of Proposed Merger Between New England Electric Sys & National Grid Group.Nrc Has No Authority to Interject Itself in Nees Merger with National Grid Group ML20210N4921999-08-0909 August 1999 Ack Receipt of 990331 Electronic Transfer of $88,000 for Civil Penalty,Proposed on 990309.Corrective Actions Will Be Examined During Future Insp ML20210C0751999-07-21021 July 1999 Forwards 990721 Notice of Public Meeting Re post-shutdown Decommissioning Activities Rept ML20210A9681999-07-14014 July 1999 Responds to Re Changes to Millstone Physical Security Plan Identified as Rev 32,submitted Per Provisions of 10CFR50.54(p).No NRC Approval Is Required,Based on Util Determination That Revs Do Not Decrease Plan Effectiveness ML20209E7341999-07-12012 July 1999 Discusses Util Responses to GL 92-01,rev 1,suppl 1, Reactor Vessel Structural Integrity. Responses Acceptable.Info Revised in Reactor Vessel Integrity Database (Rvid) & Is Releasing as Rvid Version 2 ML20209G2921999-07-0909 July 1999 Forwards Insp Repts 50-336/99-06 & 50-423/99-06 on 990420-0614.Ten Violations of NRC Requirements Occurred & Being Treated as non-cited Violations,Consistent with App C of Enforcement Policy DD-96-23, Informs That on 961226,NRC Issued Partial Director'S Decision DD-96-23,in Response to Petition Submitted,Per 10CFR2.206,on 9508211999-07-0101 July 1999 Informs That on 961226,NRC Issued Partial Director'S Decision DD-96-23,in Response to Petition Submitted,Per 10CFR2.206,on 950821 ML20196J2111999-06-30030 June 1999 Forwards SE Concluding Licensee USI A-46 Implementation Program Meets Purpose & Intent of Criteria in Generic Implementation Procedure for Seismic Verification of NPP Equipment, Rev 2 ML20196J5031999-06-30030 June 1999 Responds to 990414 Petition,Submitted Per 10CFR2.206 to Nrc. NRC Solicited Support from FEMA to Ensure That Appropriate Response to Enhancements Identified to Offsite EP in Event of Radiological Emergency at Millstone,Developed ML20196J1131999-06-29029 June 1999 Forwards Notice of Receipt & Availability for Comment of Post-Shutdown Decommissioning Activities Rept, Re .Notice Provided for Public Comments to Be Submitted within 30 Days of Notice Date ML20196G9531999-06-24024 June 1999 Discusses Changes Provided by NNECO on 990504 to TS Bases Sections 3/4.7.7 & 3/4.7.8.Returns TS Bases to NNECO to Be Inserted in TS to Ensure That NRC Staff & NNECO Have Identical TS Bases Pages ML20212H9661999-06-21021 June 1999 Confirms 990611 & 14 Telcons with M Selden,In Which Beckman & Assocs,Inc Was Advised to Stop Work Under Mod 4 to Task Order 005,under Contract NRC-03-98-021 ML20212H6661999-06-15015 June 1999 Forwards RAI Re 990315 Application Request for Approval of Proposed Indirect Transfer of Seabrook Station,Unit 1 License & Proposed Indirect Transfer of Millstone,Unit 3 License to Extent Held by Nepco ML20212J0751999-06-15015 June 1999 Forwards Notice of Withdrawal of Amend Request for Allowed Outage Time Extensions for Emergency Diesel Generators & Low Pressure Safety Injection Trains of Emergency Core Cooling Sys ML20195J3121999-06-15015 June 1999 Expresses Concern Re M Casey 990523 Column, Gaffes Turn Into Cash at NRC, & Disagrees with New London Day Earlier Editorial Criticism of NRC Investigations of Harassment & Intimidation of Employees at Millstone NPPs ML20195K0601999-06-15015 June 1999 Forwards Request for Addl Info Re fire-related IPEEE Analysis,Per GL 88-20 ML20195J4761999-06-10010 June 1999 Forwards Insp Rept 50-336/98-219 on 981214-18,990126-29 0208-19 & 0301-05.Four Violations Identified & Being Treated as Noncited Violations ML20195J0321999-06-10010 June 1999 Expresses Appreciation for Serving as Moderator for 990209 Public Meeting at Waterword,Ct.Questions Raised by Interested Members of Public & NRC Responses Encl.Staff Reply to Blanch Also Encl ML20196J5091999-06-0404 June 1999 Requests Assistance to Review Petition Submitted Under 10CFR2.206 of NRC Rules.Petition Concerns EP Issues for Millstone Nuclear Power Station ML20207G1121999-06-0303 June 1999 Forwards Insp Repts 50-245/99-05,50-336/99-05 & 50-423/99-05 on 990302-0419.No Violations Noted.Closure of 15 Significant Items List (SIL) Issues at Unit 2 Signifies Completion of Insp for Entire Unit 2 SIL ML20207G6271999-06-0303 June 1999 Forwards Amends 105,235 & 171 to Licenses DPR-21,DPR-65 & NPF-49,respectively & Safety Evaluation.Amends Replace Specific Titles in Section 6.0 of TSs for All Three Millstone Units with Generic Titles 1999-09-30
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OCT 2 41988 .
Docket No. 50-423 Northeast Nuclear Energy Company ATTN: Mr. E. J. Mroczka i Senior Vice President- Nuclear Engineering and Operations Group P.O. Box 270 Hartford, Connecticut 06141-0270 Gentlemen:
Subject: Inspection No. 50-423/88-04 This refers to your letter dated August 1,1988, in response to our letter dated June 6, 1988.
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Thank you for informing us of the corrective and preventive actions, documented in your letter to resolve Violation 50-423/88-04-06 relating to heat shrink !
tubing over braided cable jacketing, j Your response to statements in inspection report E0-423 regarding other Raychem l installations at Millstone 3 with bend radius or splice seal length deficiencies needs clarification. We discussed the bend radius deficiencies with your staff in a telephone conversattor on October 13, 1988. We understand that your installation specification E-350 and installation instructions PII-57100-A did not include explicit guidance regarding Raychem splice bend radius limits.
However, we understand that these documents did reference a Raychem document that did specify limits on splice bend radius. This infcrmation was available before the splices were installed at Millstone 3 in January 1986. With regard to our statements regarding deficient splice seal lengths with teal lengths less than two inches, we understand that your staff's review of this issue did not identify any instances at Millstone 3 where kaychem splices were installed with less than a 2-inch seal length.
We request that you respond to this letter. Your response should address I corrective steps to addrass Raychem splice bend radius deficiencies at -
Millstone 3; corrective steps to avoid further bend radius deficiencies and the date when bend radius deficiencies will be corrected.
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OFFICIAL RECORD COPY RL MILL 3 88-04 - 0001.0.0 g
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. . OCT 8 419?3 Northeast Nuclear Energy Company -2-Your cooperation with us is appreciated.
Sincerely, Crigiral Cicntd Eyt Clifford J. A lercon Thomas T. Martin, Director Division of Reactor Safety Enclosure: Application Guide cc w/ enc 1:
W. D. Romberg, Vice President, Nuclear Operations D. O. Nordquist, Director of Quality Services R. M. Kacich, Manager, Generation Facilities Licensing S. E. Jcace, Station Superintendent Public Document Room (POR)
Local Public Document Room (LPDR)
Nuclear Safety Information Center (NSIC)
NRC Senior Resident Inspec. tor State of Connecticut bec w/ enc 1:
Region I Docket Room (with concurrences)
M=;==t ^.::iztut, DPE(v/c encl)-
DRP Section Chief S. Pindale, RI, Beaver Valley W. Raymond, SRI, Millstone 1&2 D. Jaffe, LPM, NRR R. Bores, DRSS
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C Iq Cf Q RI:DRS RI:DRh RI:DRS Paolino Anderson Durr 10/ft/88 10/If/88 10N/88 0FFICIAL RECORD COPY RL MILL 3 88-04 - 0001.0.1 10/18/88
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WCSF-N Application
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Sp*CNketion: Descripth:m:
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3.3.3 CLEAN AND DEGREASE cable jacket and wire moulatert with a solvent (such as b
V t t.1 trichloroethane) whch is approved by the cable matlufacturer. All surf aces must be free of grease, oils, moisture or other contaminaats proof to being brought into contact with Psychem products.
Cable preparaton kits are avadable from Raychem: Kit No. CPK-0140 (contains 6 solvent wipes and I abrasive cloth).
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3.4 Detail inetsNetion instructione 3.4.1 When shims are required (refer to Section 2.4). INSTALL SHIMS on the wire.
Abgn to within %" of the insulation (or jacket) cutback. SHRINK IN PLACE.
3.4.3 SUDE THE SPLICE SEALING SLEEVE over enhor wire to be sphced. DO NOT SHRINK. If a bolt pad is required (refer to Section 2.3.3) side bolt pad over enhor wire to be sphced. DO NOT SHRINK.
3.4.3 MAKE CONDUCTOR CONNECTIONS. Examine each connection area for sharp edges or protrudog wire strands. Remove these with an abrasive cloth or file.
3.4.4 When bott pad is required. CENTER THE BOLT PAD over the connecton area.
SHRINK IN PLACE.
3.4.5 CENTER THE SPLICE SEALING SLEEVE over the connecten area. Where shims are used, it must overlap the outer shim. SHRINK IN PLACE.
3.4.6 DO NOT FLEX spbce untd comfortable to touch. It may then be formed to a max-imum five times the outside diameter bend radius. DO NOT VIOLATE CABLE SEND RADIUS.
4.0 inopoetion of installation Tubing is "funy recovered" when both of the following critena are met:
1. O tter surface is smooth and has a glossy appearance.
2. Inere is a visible flow of adhesive at each end of the tubing. (The outer sleeve is not required to shrink down to the cable or enNbit adhesive flow where it overtaps a shim )
4.1 Overheating Overheatmg of the tubing must ce avoided. This is evidenced by scorching or bhstering on the surface. Any minor surface scorching that can be removed by solvtfit cleaning is acceptable. Tubing wah deep blistereg must be replaced.
4.3 Underheating WCSF N tubing which has a lumpy appearance not conforming to the substrate of has a dut surf ace has not been heated sufficiently. Underheatog can be cot-rected at any twne by reheating and contmuing the thrmking process.
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[[mTIcfm'o'. CONNECTICUT 061410 non us-sooo August 1, 1988 Q1cket No. SQ !?]
6911kB Re: 10 CFR 50.49 Mr. William V. Johnston, Acting Director Division of Reactor Safety U.S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406
Dear Mr. Johnston:
Millstone Nuclear Power Station, Unit No. 3 Response to Notice of Violation inspection Report No. 50-423/88 04 1. INTRODUCTION By letter dated July 6,1988, the NRC transmitted its Inspection Report No. 50-423/88 04 and associated Notice of Violation relating to the Region I Staff's announced inspection of March 14-18, 1988, of Millstone Nuclear Power Station, Unit No. 3. In its letter the Staff identified one Severity Level IV violation, four sotential violations, and three unresolved items. The Staff requestec that Northeast Nuclear Energy Company (NNECO) respond to the Notice of Violation within 30 days of the date of the Inspection Report. In addition, the Staff requested NNECO to attend an enforcement conference to discuss the four potential viola-tions. This enforcement conference was held on July 20, 1988. At this meeting, NNECO provided information regarding the potential violation pertaining to Raychem splices. At the conclusion of this portion of our presentation, the Staff suggested that NNECO include that information when responding to the subject Notice of Violation. By this letter, NNECO responds to the Notice of Violation and the potential violation regarding Raychem splices.
II. EEt0][$PONSE TO V10L41103 .
NNEr0's response to the Severity Level IV violation identified by the Staff is set forth below:
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A. Staff Statement of the Vigttlig.n
"10 CFR 50.49, paragraph (f), requires that electrical equipment important to safety must be qualified by test and/or analysis, dU Q b50"I 6fY'
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Mr. William A07358/Page 2 August 1, 1988 i Contrary to the above, on March 18, 1988, the NRC identified Raychem cable splices installed in safety related EQ equipment that did not meet the requirements in that the heat shrink tubing was applied over braided cable jacketing. This was not a qualified configura-tion prior to the time of new test data, dated March 1987, which determined the splices were qualified.
This is a Severity Level IV violation, Supplement I."
B. NNECO Statement of Position NNECO does not contest the Notice of Violation as stated and accordingly admits there was insufficient documentation in the files to support the installation of Raychem splice over braided cable jacketing prior to March 1987.
C. Root Cause Craft personnel failed to follow the specified vendor product installation procedure during installation of these Raychem splices.
D. Corrective Steos Tilta
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This installation was discovered on March 16, 1988, during the plant walkdown phase of Inspection No. 50 423/88 04. Qualification of this configuration was previously demonstrated by test in March 1987. This test data had been evaluated and included in the i
Millstone Unit No. 3 Raychem qualification file prior to the inspec-I tion.
- E. (orrective Actions to Prevent Recurrence The following corrective actions have been implemented
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1. Craft personnel have received additional training to emphasir i
the importance of following all specified procedures during d
component installations, p 2. Craf t, inspection, supervisory, and engineering personnel have received specific Raychem installation training conducted by qualified Raychem Corporation representatives.
F. Due for Full Como11an_tt
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Full compitance was achieved in March 1987. Pursuant to the requirements of 10 CFR 50.49, paragraph (f), this Raychem configura-tion was qualified by test as of that time.
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Mr. William V. Johnsten A07358/Page 3 August 1, 1988 III. RELATED POTENTIAL VIOLATION 88 04 06 j A. Statement of the Issue
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NRC Inspection Report Issue 50 423/88 04 06 states, "a review of j '
licensee walkdown records for Raychem splices indicate (s) additional i' nonconforming conditions involving excessive splice bends (less than u the recommended 5X outside cable di meter) and splice seal length
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areas of less than 2 inches." Accorjing to the Staff, these def t-ciencies constitute a potential violation of 10 CFR 50.49 in that
- x the splices were not qualified per the instruction procedures in effect at the time of the installation.
, [ 8. hNECO Position Regardina the Existence of a Violation 1 NNECO does not agree with the Staff's conclusions that installation V of Raychem splices with a bend radius less than SX the outside cable f diameter was contradictory to the Raychem procedure / instructions existing at that time. NNECO followed existing procedures with regard to these installations at the time the plant went into operation.
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NNECO also does not agree that the Millstone Unit No. 3 walkdown records indicate that the Raychem installation had splice lengths of s less than two inches.
s C. fltsis for Denyino that a Deficiency Existed
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Bend Ridin
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[ The original installation of the splices was made in accordance with Millstone Unit No. 3 Electrical Installation Specification No. E-350. This procedure stated that Raychem installation instructions shall be in accordance with Raychem's "Product Installation and Inspection Guide WrSF N Heavy Wall, Flame Retarded Nuclear Cable Sleeves" (Pil-57100 A) and installation instructions provided with each kit. E 350 also states that
\ Quality Control personnel shall verify (in accordance with l
s specifications) that proper Raychem components are used,
- manufacturer's installation instructions have been followed,
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and an acceptable splice has been made.
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(November 1982) was in effect, Raychem did not specify bend radius acceptance criteris. Accordingly, contrary to the inspection report findings, the Raychem installations were made J' , in accordance with procedures in existence at that time. Upon l \.' issuance of NRC Information Notice 86 53 (June 26, 1986), NNECO pj gjf,3 a %u 7hd
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Mr. William A07358/Page 4 August 1, 1988 took reasonable and prudent actions to address the issue. Bend radius criteria were first published in PII-57100 D (November 1987). 4 g?7 2. Seal Lenath Contrary to the NRC inspection report, NNE W s review of walkdown records does not reveal any instances whera Raychem splices with less than 2 inch seal lengths ex t!;t. NNECO Quality Control personnel witnessed the installation of some of ;
the splices and did not note any such deficiencies in seal length. NNECO had no other indications that such deficiencies in seal length exist. Therefore, NNECO denies that the alleged deficiency in seal length existed. It should be noted that after issuance of Information Notice 86-53, in which this issue ;
was raised, NNECO took reasonable and prudent actions to address it. *
D. Safety Sianificance These issues have no safety significance because the March 1987 testing has established that a bend radius much less than 5X the outside diameter and seal lengths much less than 2 inches are qualified configurations. Accordingly, no replacements or modifica- <
tions of the components were required to establish or maintain qualification.
E. Other Factors that Should Be Considered 1. Notwithstanding the final determination regarding the existence of a violation, craft personnel have received additional training to emphasize the importance of following procedures I during component installations.
2. In addition to the above, specific Raychem training was provided by Raychem personnel to ensure that installations were correct.
3. The EQ file was revised prior to the inspection to include test data (dated March 1987) that confirms the qualification of Raychem splices less than a 2 inch seal length and bends of less than 5X the outside diameter of the cable. The Staff has .
concurred with the acceptability of the March 1987 report to !
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further establish qualification. (See Inspection l Report 50 423/88 04 at p. 21.) i
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Mr. William A07358/Page 5 August 1, 1988 If you have questions regarding the information contained in this letter, please contact us.
Very truly yours, NORTHEAST NUCLEAR ENERGY COMPANY d
MroczkV Se for Vice President cc: W. T. Russell, Region I Administrator D. H. Jaffe, NRC Project Manager, Millstone Unit No. 3 W. J. Raymond, Senior Resident inspector, Millstone Unit Nos. 1, 2, and 3 U.S. Nuclear Regulatory Comission Document Control Desk Washington, D.C. 20555 STATE OF CONNECTICUT ss. Berlin COUNTY OF HARTFORD Then personally appeared before me E. J. Mroczka, who being duly sworn, did state that he is Senior Vice President of Northeast Nuclear Energy Company, a Licensee herein, that he is authorized to execute and file the foregoing information in the name and on behalf of the Licensee herein, and that the statements contained in said information are true and correct to the best of d his knowledge and belief.
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