ML19225A284
| ML19225A284 | |
| Person / Time | |
|---|---|
| Site: | Shoreham File:Long Island Lighting Company icon.png |
| Issue date: | 06/22/1979 |
| From: | Whittemore F HUNTON & WILLIAMS |
| To: | |
| References | |
| NUDOCS 7907180761 | |
| Download: ML19225A284 (21) | |
Text
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_UNITED STATES GF AMERICA ep',,\*.NUCLEAR REGULATORY COMMISSION Zi ,i_.*ll .fi. . jt 17 y..,) ,/.~"'Before the Atomic Safety and Licensinz Board
,/ s.,-..>'-In the Matter of
))LONG ISLAND LIGHTING COMPANY
)Docket No. 50-322
)(Shoreham Nuclear Power Station,)Unit 1))APPLICANT'S RESPONSE TO SC'S JUNE 6, 1979 DISCOVERY REQUEST Suffolk County (SC) requested certain information from the Applicant in Appendices A and 3 of its Setand Set of Interrogatories and Notice to Produce, dated June 6, 1979.
The Applicant's response to this discc try request is enclosed.
Respectfully submitted, LONG ISLAND LIGHTING COMPANY Y*F. Case Whittemore W. Taylor Reveley, III Hunton & Williams 707 East Main Street Richmond, Virginia 23212 DATED: June 22, 1979 08 423/,r'J 7 b 'lC'--v//7907180 4-
.ENCLOSURE 1 AFFIDAVlT STATE OF NEW YCRK)
- ss: COUNTY OF SUFFOLK)
WILLIAM J. MUSELER, being duly sworn, states Pat he is Assistant Project Manager for the Shoreham Nuclear Power Station; that the attached LILCO Responses to SC's June 6, 1979 Discovery Request were prepared under his supervision and direction; and that statements contained therein are true and correct to the best of his knowledge, informction, and belief.
^ //,l/, ph' - )r-WILLIAM'd. MUSELER Sworn to before me this 20th day of June, 1979.
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..ENCLOSURE 2 LILCO RESPONSES TO SC'S JUNE 6, 1979 DISCOVERY REQUEST APPENDIX"A" A.Relating to Record Keeoing Q.1 Are the LILCO Shoreham construction and design documents on microfiche or hard copy?
A.1 As indicated in 1 4 of the Affidavit of Joseph P. Novarro, dated May 25, 1979, which was attached to the Applicant's May 29, 1979 pleading, E&DCR's are maintained in both hard copy and microfilm form.
Q.2 Does LILCO retain originals of all these documents on site?A.2 As indicated in 1 4 of Mr. Novarro's May 25, 1979 Affidavit, the originals of E&DCR's arc maintainad in S&W's Boston office.
At the Shorehan site, a reproducible hard copy of all E&DCR's is maintained by the Document Control Office and microfiLa copies are maintained onsite and in a separate offsite storage facility.
Q.3 What is LILCO's practice with respect to the disposal of documents?
A.3 Working copies of E&DCR's are disposed of at the discretion of each individual recipient after they have served their function.Disposal of working copies does not affect the completeness of the files of origina's and copien discussed in 1 A.2 above.
Q.4 Does LILCO claim that such disposal is permitted by any regulation of the NRC; (a) if so, cite the regulation.
A.4 The NRC's regulation covering retention of QA records, such as E&DCR's, appears in 10 CFR Part 50, Appendix 3, 428 026
.-2-Criterion XVII.
This regulation requires that " sufficient records shall be maintained to furnish evidence of acti-vities affecting quality." Retention of the origiaals and copies discussed in 1 A.2 above meets this requirement.
Retention of additional working copies is not ccvered in the regulation and, thus, an applicant is free to dis-pose of them at its discretion.
B.Relatine to Cable Tray Records Q.1 Are the : oblems described in these records safety related?A.1 LILCO does not know specifically which E&DCR's are in the possession of SC's counsel.
Ther. lore, it can not state which of those E&DCR's, if any, rcise safety-related questions.
It should be noted that a check in the" Nuclear Safety Related (QA Cat. I)" box does not mean, necessarily, that the E&DCR raises a safety-related question.That is because this bcx is checked if the E&DCR concerns a Category I document regardless of whether resolution of the E&DCR could affect plant safety.
Q.2 With regard to any problems identified in LILCO's engineering and design coordination reports (herein-after referred to as the " Reports") concerning cable trays, were FSAR changes required?- (a) if so, were
, such changes in the FSAR =ade and cite the sections.
A.2 If an E&DCR results in a codification that may conflict with something in the FSAR, then the assigned Responsible Engineer indicates this on the E&DCR by checking the appropriate box.
The FSAR is periodically updated to 423 027 'incorporate changes made to the plant design, including any conflicts that arise from EaDCR's.
The c.&DCR's that concern the cable trays, as is often the case, have not required any FSAR changes.
Q.3 such changes?;Was client approval requested and given (a) if not, why not?
with respect to A.3 For those E&DCR's with a check in the cli" Required" box, ent approval LILCO approval was obtained.
At the minimum, S&W must obtain LILCO approval pri or to issuing any E&DCR that changes a Category I iteri to a lesser category.With regerd to FSAR changes, LILCO revi all such changes prior to issuance ews Q.4.Mas there been a quality assurance /qualit
("@ /QC") check with regard to such ch y control details thereof;yes, when was such QA/QC check performed and anges? (a) if (b) if not, why not.
give the A.4 For those E&DCR's that receive a quality a the " Qual. Sys. Div.
ssurance check, or Eng. Assur, Div." box is signed.
This approval is required for E&DCR's that result in changes to quality assurance requireme Q.5 nts.What are the criteria for verification at any change or fix with respect of isolementation to the cable trays?
A.5 All E&DCR's affecting safety-related cabl e trays are verified by field quality control.
These inspections demonstrate ccepliance with the latest d and any applicable E&DCR's.
rawing revisions
<of 42B" Q.6 Who in the LILCO construction organization (which is deemed to refer also to Stone & Webster) makes the decision regarding QA/QC approval, client approval and FSAR chenge?
A.6 E&DCR's are changes to engineering uccuments and, there-fore, are answered by the engineering organization, or its designee.
The assigned Responsible Engineer re-searches the matter, reaches a resolutier and decides whether QA approval, client approval, and an FSAR change are required.
See Affidavit of Joseph P. Novarro at 1 3.Q.7 Is the person who makes that decisio;. the lead engineer?, (a) if not, does the lead engineer or design engineer have to approve or sign off as to such change?
A.7 As indicated in 1 A.6 above, the assigned Responsible Engineer makes these initial decisions.
Then, the Lead Engineer and the S&W Proj ect Engineer (or their designees) review r.he Responsible Engineer's decisions and approve his recocmended solution, if merited.
Q.8 If the item as to which the change is made is safety class 1, have analysis [ sic] been done of such change to reconfirm seismic and design adequacy?
A.8 The Shoreham cable trays are designated as either safety-related or non-safety-related.
When the design of a safety-related cable tray is changed, evaluations are performed to ensure that the tray still =eets the applicable seismic and design criteria.
0r 1 Q 423 c' Q.9 What are the system identifiers?- (a) explain the
, numbering system for cable trays and safety related systems so as to permit determination of what the systems are.
A.9 The system identifiers, including those for safety-related systems, are listed in Attachment 1.
The numbering system used for cable tray identification is described in Attachment 2.
C.Relating to County's Prior Letter to Chairman Bowers Dated May 17, 1979 Q.1[ Provide] a technical explanation and assessment of the documents referred to in [The Southhampton Press] article
[of May 17, 1979] and those delivered to our office.
A.1 A technical explanation and assessment of the de^.usents (E&DCR's) referred to in 1 Q.1 above was provided in the Affidavit of Joseph P. Novarro.
That Affidavit stated in 1 2 that E&DCR's are design control documents similar to those used at all U.S. nuclear proj ects.
E&DCR's are used to ensure that specified engineering and design documents for the Shoreham plant are properly interpreted and that engineering evaluations of any requested changes to these documents are performed to demonstrate and document the acceptability of these changes.The procedures folicwed to prepare, review, and approve E&DCR's were outlined in 1 3 of Mr, Novarro's Affidavit.
Moreover, 1 6 of that Affidavit indicated that NRC, S&W and LILCO personnel, as well as the ASME Code Co=mittee Survey Team, have reviewed the Shoreham ELDCR system (including representative samples) and 423 030 found it to be in ccmpliance with applicable engineering standards and NRC regulations.
See NRC Staff (Hoefling) letter to the Board, dated June 12, 1979.
To provide a specific technical assessment of the approximately 2000 E&DCR's that are apparently in the hands of SC's counsel would be unduly burdensome.
If SC has specific questions on certain E&DCR's, LILCO will respond to those questions.
Q.2a[ Provide] a schedule or punch list of all incomplete items and engineering problems to date, giving details a.c to how any of such problems have been or are being taken care of.A.2a E&DCR's are the best source of information on these matters.LILCO agrees to make the E&DCR's available for perusal by SC's consultant.
Q.2b[ Provide] a list of design changes made in the field.
A.2b Numerous E&DCR's have been approved and issued during the construction of Shoreham.
It would be pointless and unduly burdensome to list each E&DCR.
Moreover, SC's counsel apparently already has in hand a substantial number of representative E&DCR's.
Q.2c[ Provide] a list of instructions from LILCO's proj ect engineering management to the field as to any changes needed to be made and their disposition.
A.2c As to any desigr
-4 nge that the LILCO Proj ect Management Office believes is warranted, it recommends that S&W issue an E&DCR.
That recommendation is then treated in 423 031 accordance with the normal E&DCR review procedure.
No separate list of such recommendations is kept.
Q.2d The NRC should physically inspect the entire construction to make certain that it conforus to all of the NRC's requirements.
A.2d As already explained, the NRC Inspection and Enforcement effort at Shorehan has been and will continue to be more than adequate to ensure the safety of the plant.
See Affidavit of Joseph P. Novarro at 11 5-6; NRC Staff (Hoefling) letter to the Board, dated June 12, 1979.
Therefore, SC's request is unwarranted.
i?rJ J " 42.3
_8_APPENDIX"B" A.Relating to Variances Q.1 How is the variance finally reflected in the drawings and materials available to the plant operators and the NRC7 A.1 The latest design information on a component or system consists of the latest applicable revisions to drawings and other materials plus any applicable E&DCR's.
As necessary, drawings and other materials are updated periodically and at completion of the proj ect to reflect changes approved on E&DCR's.
This will produce a con-solidated record of the final condition.
Q/A.2-4 These questions request certain information regarding the NRC's technical review process.
The'refore, no response is male by tie Applicant.
3.Relating to NRC and LILCO's Insoection Practices Q/A.1-6 These questions request certain information regarding the NRC's Inspection and Enforcement effort.
Therefore, no response is =ade by the Applicant.
Q.7 Has anybody in the LILCO c)nstruction organization inspected Shoreham drawings against complete systems installed to insure that the drawings reflect the "as built" systems, that the original design quality requirements are not violated and that the crocedures specified by the drawings are followed?, (a) if so, specify who in LILCO's c_nstruction organization has performed this responsiblity and have any reports con-cerning such inspections been prepared?; (b) if so, provide copies; (c) if not, why not?
423 033
_9_A.7 As part of the " turnover" process prior to preopera-tional resting, LILCO Construction reviews each completed system for compliance with the latest design drawings, any applicable E&DCR's, and other applicable design documents.
Then the quality organization reviews installation of these systems for compliance with the same criteria.
The LILCO Construction and QA/Or reviews are carried out by a large number of engineers and inspectors from all disciplines.
The results of t'_a QA/QC review are contained in the individual component and system turnover packages.
The number of inspection documents for each system may run into the thousands.
In view of the bulk of this documentation, providing copies would be unduly burdensome.
Therefore, LILCO will make these records available for perusal by SC's consultant.
Q.8 Has LILCO checked these drawings randomly?; (a) has it checked them for all safety systems?- (b) has it checked them for all systems?
A.8 The design documents are reviewed on a randcm casis by LILCO's QA Department, as well as by NRC personnel.
Further, inspection documentation relating to ASME III piping syscens is 1007. revicted by the " Authorized Nuclear Inspector," the independent representative on site who ensures ccmpliance with the ASME code.
As indicated in 1 A.7 atove, all design drawings, applicable ELDCR's,<423 034. and other applicable design documents for safety-related systems are reviewed against the actual install.ttion by construction and quality assurance personnel.
The installation of non-safety-related systems is checked by the construction organication.
Q.9 Did LILCO's check also incluce a records check to assuie that all deviations and changes during construction have been verified and reflected on the "as built" drawings?
A.9 All deviations and changes are reflected 1.1 the final design documents as discussed in 1 A.1 al. e and are verified as stated in 11 A.7 .8 above.
Q.10 Are suggestiols or complaints received bv LILCO from craftsmen wich regard to such practices?
If so, how does LILCO integrate and utilice such suggestions and/or complaints to improve and verify proper construction practices?
A.10 To the best of our knowledge, no suggestions on the E&DCR initiation, review and approval process have been received directly from craftsmen by site resident engineering, Field Quality Control, or the S&W Site Engineering Office.
From time to time such suggestions are received from LILCO, contractor, and Quality Assurance personnel.
They are passed along to the appropriate LILCO and S&W personnel for evaluation and implementation, if warranted.
C.Relating to Evdrostatic Testine Q.1 L: critical hydrostatic tests regarding safety class fluid systems have been performed and are scheduled and on what dates?
423 035 A.1 The following ASME III fluid systems have been hydro-statically tested:
Percentage of System System Tested Core Spray 100%High Pressure Coolant Inj ec tiot:
100 Reactor Core Isolation Cooling 100 ruel Fool Cooling 100 Service Water 75 Reactor Building Closed Loop Cooling 75 Water Residual Heat Removal 50 The schedule for testing the remaining ASME III fluid cystems is as follows:
Date System June 1979 Remainder of Reactor Building Closed Loop Cocling Water July 1979 Remainder of Residual Heat Removal Reactor Pressure Vessel and all piping that forms the primary pressure boundary Standby Liquid Control System Main Steam Isolation Valve Leakage Control System Reactor Water Recirculation System Aug. 1979 CRD Control Linus Sept. 1979 Remainder of Service Water Q.2 Provide test procedures and acceptance criteria for such systems.A.2 The hydrostatic tests listed in 1 A.1 above require the testing of hundreds of subsystems.
Each subsystem test has its own test procedure and acceptance criteria.
Because of the volume of this documentation, it would be unduly burdensome to supply copies of all test procedures 423 036 and acceptance criteria.
Therefore, LILCO will make these documents available for perusal by the County's consultant.
Q.3 Provide reports as to the results of such tests.
A.3 The final reports on hydrostatic testing parallel the individual subsystem hydrostatic test procedures re-ferred to in 1 A.2 above.
Again, because of the volume of these documents, LILCO will make them available for perusal by the County's consultant.
Q.4 Has the NRC I&E Division observed any of such tests?
If so, provide copies of any inspection reports.
A.4 This question is addressed to the NRC.
Therefore, no response is made by the Applicant.
Q.5 7.s LILCO willing to allow the County's consultant to observe one of the tests chosen at random on safety class equipment?
A.5 Yes.423 037
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.ATTACHMENT 2 CABLE TRAY SYSTEM IDENTIFICATION SHOREHAM NUCLEAR POWER STATICN, UNIT 1 RACEWAY NO.
I I I U T Ss y ~JC C C NYE N OOO IPR U LNN TEV M 0DD I 3 RUU C E//E R AN UNIT -The number is the station unit number (i.e., Shoreham Nuclear Station Unit 1) and all raceways associated with the specified unit shall carry that unit's number.
Coccon raceways between Shoreham Nuclear Station Unit 1 and any other stations shall always be zero (0).
TYPE -The type character indicates the type of raceway to be scheduled.
This character sha'.1 always be an alpha-character.
A - Armored Cable or Direct Burial Cable C - Conduit D - Duct and Concealed Conduit over 20 feet F - Floor Sleeves and Concealed Conduit 20 feet or under T - Tray and Troughs U - Trenches and Block-outs W - Wall Sleeves SERVICE -The service character is an alpha synbol which indicates the service of cable to be carried in the designated raceway.
H - 1st Voltage Level above 600 Volts (5KV Power)
L - 600 Volt Pcwer K - 600 Volt Power (Derated)
C - Control X - Instrumentation NUM3ER -The grcup of three numbers assigned to specify the individual raceway.
This number consists of 3 numeric characters, within the limits of 001 through 999-423 042
.-2-COLOR -The color character is always an alpha symbol used to designate the electrical division for safety systems or that the cable tray is non-safety-related.
R - Red B - Blue Safety Systems 0 - Orange N - Non-safety Systems CONDU/A -When this character is for conduit identification, it will be a letter or blank.
When used for identification of sleeves or duct, it will be nu=eric.CONDU/N -This character is also used for conduit branch identification and will be numeric.
When not used, it will be left blank.
423 043
-.In the Matter of LONG ISLAND LIGHTING COMPA'IY (Shoreham Nuclear Power Station, Unit 1)
Docket No. 50-322
__CERTIFICATE OF SERVICE I hereby certify that copies of APPLICANT'S RESPONSE TO SC'S JUNE 6, 1979 DISCOVERY REQUEST were served upon the follcwing by first-class mail, postage pre-paid, on June 22, 1979.
Elizabeth S. Bowers, Esq.
Richard K. Hoefling, Esq.
Atomic Safety and Licensing U.S. Nuclear Regule.cory Board Panel Commission U.S. Nuclear Regulatory Commission Washingten, D.C.
20555 Washington, D.C.
20555 Jeffrey C.
Cohen, Esq.
Mr. Frederick J. Shon New York State Energy Office Atomic Safety and Licensing Swan Street Building - Core 1 Board Panel Empire State Plars U.S. Nuclear Regulatory Commission Albany, New York 12223 Washington, D.C.
20555 Howard L.Blau, Esq.
Dr. Oscar H. Paris 217 Newbridge Road Atomic Safety and Licensing Hicksville, New York 11801 Board Panel U.S. Nuclear Regulatory Commission Ralph Shapiro, Esq.
Washington, D.C.
20555 Cnmmer & Shapiro, P.C.
9 East 40th Street Secretary of the Commission New York, New York 10016 U.S. Nuclear Regulatory Co= mission Washington, D.C.
20555 Energy Research Group 400-1 Totten Pond Road Atomic Safety and Licensing Waltham, Massachusetts 02154 Appeal Board U.S. Nuclear Regulatory Commission Washington, D.C.
20535 Atomic Safety and Licensing Board Panel U.S. Nuclear Regulatory Commission Washington, D.C.
20555 gs7 g.agg./., vcts //AcT$kes F. Case Whittemore Hunton & Williams P.O.Box 1535 Richmond, Virginia 23212 DATED: June 22, 1979 423 044