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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
.     _
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))LONG ISLAND LIGHTING COMPANY
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)Docket No. 50-322
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)(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.
                                                  ; y I!qq,,                               ., , .., \
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-  
UNITED STATES GF AMERICA                             .        ep'         ,,\
.ENCLOSURE 1 AFFIDAVlT STATE OF NEW YCRK)
* NUCLEAR REGULATORY COMMISSION
: ss: COUNTY OF SUFFOLK)
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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.
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^ //,l/, ph' - )r-WILLIAM'd. MUSELER Sworn to before me this 20th day of June, 1979.
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Before the Atomic Safety and Licensinz Board
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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?
                                                                                            ,/ s.
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?
In the Matter of                         )
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.
LONG ISLAND LIGHTING COMPANY             )         Docket No. 50-322
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.
(Shoreham Nuclear Power Station,         )
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.
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 423    08
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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.
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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
 
.
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.
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.
B. Relatine to Cable Tray Records Q.1 Are the : oblems described in these records safety related?
Ther. lore, it can not state which of those E&DCR's, if any, rcise safety-related questions.
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
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.
          " 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
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.
such changes in the FSAR =ade and cite the sections.
The FSAR is periodically updated to 423 027 'incorporate changes made to the plant design, including any conflicts that arise from EaDCR's.
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
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.
incorporate changes made to the plant design, including any conflicts that arise from EaDCR's.
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
concern the cable trays,                        The c.&DCR's that as is often the case, have not required any FSAR changes.
("@ /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.
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
give the A.4 For those E&DCR's that receive a quality a the " Qual. Sys. Div.
          " Required" box,                                 ent in  the cli approval LILCO approval was obtained.
ssurance check, or Eng. Assur, Div." box is signed.
At the minimum, S&W must obtain LILCO approval pri or to issuing any E&DCR that changes a Category I iteri to category.                                            a lesser With regerd to FSAR changes, LILCO ews          revi all such changes prior to issuance Q.4
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.
Mas there been a quality assurance /qualit
These inspections demonstrate ccepliance with the latest d and any applicable E&DCR's.
("@ /QC") check with regard to such ch           y control details thereof;yes, when was such QA/QC     anges? check (a) if performed and A.4 (b) if not, why not.             give the For those E&DCR's that receive a quality a the " Qual. Sys. Div.                               ssurance check, or Eng. Assur, Div." box is signed.
rawing revisions
This approval is required for E&DCR's changes                                        that result in to quality assurance requireme nts.
<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?
Q.5 What at are theor criteria any change                    for verification fix with respect         of isolementation A.5                                              to the cable trays?
A.6 E&DCR's are changes to engineering uccuments and, there-fore, are answered by the engineering organization, or its designee.
All E&DCR's affecting safety-related cabl e trays are verified by field quality control.
The assigned Responsible Engineer re-searches the matter, reaches a resolutier and decides whether QA approval, client approval, and an FSAR change are required.
These inspections demonstrate ccepliance with the latest d rawing revisions and any applicable E&DCR's.
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?
                                                                  <of
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.
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?
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.
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.
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.
423   0rc' 1Q
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.
Q.9 What are the system identifiers?- (a) explain the
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.
numbering system for cable trays and safety related systems so as to permit determination of what the systems are.
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
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.
[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.
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.
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
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.
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.
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.
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.
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.
If SC has specific questions on certain E&DCR's, LILCO will respond to those questions.
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.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.
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.
A.2b Numerous E&DCR's have been approved and issued during the construction of Shoreham.
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.
It would be pointless and unduly burdensome to list each E&DCR.
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
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.
accordance with the normal E&DCR review procedure. No separate list of such recommendations is kept.
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.
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.
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.
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.
Therefore, SC's request is unwarranted.
i?rJ J " 42.3
i?
_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.
42.3    rJ J "
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.
_8_
Q/A.2-4 These questions request certain information regarding the NRC's technical review process.
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.
The'refore, no response is male by tie Applicant.
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.
: 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.
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?
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
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.
_9_
Then the quality organization reviews installation of these systems for compliance with the same criteria.
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.
The LILCO Construction and QA/Or reviews are carried out by a large number of engineers and inspectors from all disciplines.
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.
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?
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.
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.
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,       <
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.
423     034
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.
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.10 Are suggestiols or complaints received bv LILCO from craftsmen wich regard to such practices?
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?
If so, how does LILCO integrate and utilice such suggestions and/or complaints to improve and verify proper construction practices?
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.
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.
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?
From time to time such suggestions are received from LILCO, contractor, and Quality Assurance personnel.
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.
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?
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
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:
A.1 The following ASME III fluid systems have been hydro-statically tested:
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:
Percentage of System                   System Tested Core Spray                                     100%
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.
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:
Each subsystem test has its own test procedure and acceptance criteria.
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.
Because of the volume of this documentation, it would be unduly burdensome to supply copies of all test procedures 423 036 and acceptance criteria.
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.
Therefore, LILCO will make these documents available for perusal by the County's consultant.
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.
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.
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.
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?
Q.4 Has the NRC I&E Division observed any of such tests?
If so, provide copies of any inspection reports.
If so, provide copies of any inspection reports.
A.4 This question is addressed to the NRC.
A.4 This question is addressed to the NRC. Therefore, no response is made by the Applicant.
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?
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  
A.5 Yes.
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.ATTACHMENT 2 CABLE TRAY SYSTEM IDENTIFICATION SHOREHAM NUCLEAR POWER STATICN, UNIT 1 RACEWAY NO.
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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.
                                                                                                                                                                                              /7e
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.
04
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.
_                                                                                                                                                                    '
tA L              _
5             _                                                                                                                                                      .*
* 1              _                                                                                                                                                ,,
* _
* G _
* N _                                                                                                                                                  3,
                                                                                                                                                          .
* O -
* L    -
              -      _
X                  _
              -        _                                                                    '
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* T      _                                            S                                          TL                      SY            S                S        S                            S            f
* A       _                                            F                                          SU                      YS        N        M                      H N                        Y              5
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        -                                          -                  -
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  '
* 05/19/19                                                                          * * * * *
* 5 Y 5 iEH    I NOEX ******                                                                                                    P 4 t.L 2 5940Rifl AM tidC L E A R POWtk 5i418074 UNil NO 1                              LONG ISLANO ilGHilNG                        t, UMP ANY
(        _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _              _ _ _ _ _ _ _ -          __                _ ___-          ____________________________ _ ___ __________________                                                                      _______
    -
                                    $YSitM                                          SYSILM NAME
* i                             ______
_____                            ______________________________._______                                          ____                _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - _ _ _ _ _ _ _ _ _ _ _ _ _ -
    -
Hbl      titif L L,1NG SLRVIC E Hl 5LE LL ANEUU$ SY5itM te l l    HAlii SILAN SYSIEN I                                   Hll        (Ot40tNSAIE ANO FttLdATER SYSIEN I422      HLAIEN RLLILF Al40 VI tt i t ir4E 5 SYSTEN N2)        HI SCE t t ANE OUS OR A l t4 S - SECOf40ARY PL AN{ SYSILH N24        SfAL[NG WAILR $YSILH 425        RIP auRblNE SUPER I N S I R U Ht i4 ! S 8
N11        TUHulNL SY 5lEM N32        IllHult4E CONIROL SY5itM
    -
f433      5t AL Af40 H AOW A SI E SitAM SYSiEH I
F4 34      1.HSRICAllNG Olt 5f$ltH H35        HOI 5 i d,t t SLPARAiOh H flit. A TOR AND HE AILR DR AIN5 SYS f4 36      t'AIRACIION sit AM SYSILH N)I        H A lle f uRti SUPVSRV l tdi SYS I
f438      Hl Hi 4 8 SY$llH I439        IORNir4G 6 EAR SYsitM N41        6tf4LRAIOR SYST(H F44 2      il(URObtle SE AL SYSiEH N43        Gi r4 L R A I OR SI AIOR COOllt4G SYSTEM
(                                    I44 4      VACUdH PRINING AND AIR RLHOVAL SYSIEH I44 5      Gt'Nt H A f DH HYORUGEN AND CO2 PU'tGE SYSTEN f 451      F MC l i A l lord SYSitH I45 2      Cut 4HC f45 Ait OE H i r4 L R Al l i t .4 SYSTEN
(                                    H62        RAOWA5ft OFF-GA5 SV5lfH NFl        CIRLULAllNG WAl[R SYSitH
    -
012        PLANI ADMINISIRATIVE O20        PtANI SYSiLH Ot SCRIP flONS I                                   O21        PIAllute OP[RAllNG mat 40AL PROCE DUR E S Of)       PLAN: tHERGLNCY PLANS 0.5      PtANI IN5tRVICE INSPtClEUN 031        ttLL PROO RPl$.NEC UIOER NOCLEAR SIAiluNS
(                                    USS        Pt '4 f u'4 H ANL t' IESTING 04I      OP t R A I IIF4 A L IRAINjNG/ORGANI2AlION 042        Pt Atti IHAIN PROCPtRS REC-5NPS 051      PLAN        [ RAdlAllON PROBELIIOte C SAFEiY t                                     061      PtANs SECURRIY
: 06)        SI A l101 PL Atar41t4GCWORK SCHEut/LES 065        Pt.At41 RtV Ot2 OPtRAI COHN ROC 066        PLANI f40CLLAR klVitW BOARO I                                     071      PL Ardi H Alf4T EN At4CE /SuRVE It t ANCE Pil       Cut 40t NS AIE JM ANU E R ANO STORAGE SYSILM P21      DE MItatR Al t it D At40 WAltR HAKE-UP SYSILH P))        *AMPli SYSitH I                                    P41        $1RVICL WAILM SYSIIHS P4)      HLACIOR t>u l t u t tet, CLOSLO LOOP CHOL ING W ATER SY SIE H P4$        IURt-lNt tiU l L O I NG C l O 5 t O L OO P C OOL l ut, WAIER Sv$iEH i
P5J      COMPRt55tu AIR SYSILM Pol      RAOdA5ft SOL IOS H At40L l1G SY$it M P64      Mt llOttOL OGIC AL Md'41lORING P65      VIlik A Iinte MONI IUH I f4G Pil      low Dit4bOCf G SW UNAIN SYSTEM kil      5 8 4 8 : 0r4 IRAN 5tORMLHS SYSILM H55 AND RSS SYSIEH                                          .
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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)
H - 1st Voltage Level above 600 Volts (5KV Power)
L - 600 Volt Pcwer K - 600 Volt Power (Derated)
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.
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
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.
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.
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.
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.
When not used, it will be left blank.
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  
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.
In the Matter of LONG ISLAND LIGHTING COMPA'IY (Shoreham Nuclear Power Station, Unit 1)
Richard K. Hoefling, Esq.
__
Atomic Safety and Licensing U.S. Nuclear Regule.cory Board Panel Commission U.S. Nuclear Regulatory Commission Washingten, D.C.
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.
20555 Washington, D.C.
Elizabeth S. Bowers, Esq.                 Richard K. Hoefling, Esq.
20555 Jeffrey C.
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.
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.
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.
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.
20555 Howard L.Blau, Esq.
Washington, D.C.     20555               Cnmmer & Shapiro, P.C.
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.
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./.,
Washington, D.C.
vcts //AcT$kes F. Case Whittemore Hunton & Williams P.O. Box 1535 Richmond, Virginia   23212 DATED:   June 22, 1979 423     044}}
20555 Cnmmer & Shapiro, P.C.
9 East 40th Street Secretary of the Commission New York, New York 10016 U.S. Nuclear Regulatory Co= mission Washington, D.C.
20555 Energy Research Group 400-1 Totten Pond Road Atomic Safety and Licensing Waltham, Massachusetts 02154 Appeal Board U.S. Nuclear Regulatory Commission Washington, D.C.
20535 Atomic Safety and Licensing Board Panel U.S. Nuclear Regulatory Commission Washington, D.C.
20555 gs7 g.agg./., vcts //AcT$kes F. Case Whittemore Hunton & Williams P.O.Box 1535 Richmond, Virginia 23212 DATED: June 22, 1979 423 044}}

Revision as of 10:41, 19 October 2019

Answer Submitted by Util to Suffolk County 790606 Second Set of Interrogatories & Document Requests.Forwards Info Requested in Apps a & B.Affidavit of Wj Museler & Certificate of Svc Encl
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)
v • d • e


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Before the Atomic Safety and Licensinz Board

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In the Matter of )

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LONG ISLAND LIGHTING COMPANY ) Docket No. 50-322

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(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 423 08

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ENCLOSURE 1 AFFIDAVlT STATE OF NEW YCRK)

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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.

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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

.

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.

concern the cable trays, The c.&DCR's that 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

" Required" box, ent in the cli 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 category. a lesser With regerd to FSAR changes, LILCO ews revi all such changes prior to issuance 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 anges? check (a) if performed and A.4 (b) if not, why not. give the 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 changes that result in to quality assurance requireme nts.

Q.5 What at are theor criteria any change for verification fix with respect of isolementation A.5 to the cable trays?

All E&DCR's affecting safety-related cabl e trays are verified by field quality control.

These inspections demonstrate ccepliance with the latest d rawing revisions and any applicable E&DCR's.

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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.

423 0rc' 1Q

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.

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42.3 rJ J "

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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

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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

.

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

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