Text

Forwards Responses to NRC Comments on Util 820219 Submittal of Revision 4 to Rept on NUREG-0588 Re Equipment Qualification
	ML20052G954
Person / Time
Site:	Summer
Issue date:	05/12/1982
From:	Nichols T; SOUTH CAROLINA ELECTRIC & GAS CO.
To:	Harold Denton; Office of Nuclear Reactor Regulation
References
	RTR-NUREG-0588, RTR-NUREG-588 NUDOCS 8205190183
	Download: ML20052G954 (80)
	v • d • e

{{#Wiki_filter:, SOUTH CAROLINA ELECTRIC a gas COMPANY POSY OFFICE ACn 764 CotuMe:A, South CARoWNA 29218 T. C. NicHoLs, J n. May 12, 1982 v,u e.... ..... o. c m,- NucLEaa Optpar:0.s Mr. Harold R. Denton, Director Office of Nuclear Reactor Regulation U. S. Nuclear Regulatory Ccmnission Washington, D.C. 20555

Subject:

Virgil C. Sumer Nuclear Station Docket No. 50/395 Responses to Ccmtents on SCE&G NUREG 0588 Report, Rev. 4

Dear Mr. Denton:

On February 19, 1982, South Carolina Electric and Gas Ccarpany (SCE&G) subnitted to you Revision 4 of the SCE&G report on NUREG 0588, Equipment Qualification. Attached we provide responses to NRC staff coments on our February 19, 1982, subnittal and a sanple radiation calculation as requested by the staff. These responses were discussed previously with the NRC in recent telephone comunications. This attachment should provide all the required information to address the NRC's concerns. If you have additional questions, please let us know. Very truly yours, A T. C. Nichols, Jr. NEC:'ICN:lkb Attachment cc: V. C. Sumer (w/o attach.) G. H. Fischer (w/o attach.) H. N. Cyrus T. C. Nichols, Jr. (w/o attach.) M. B. Whitaker, Jr. J. P. O'Reilly H. T. Babb D. A. Nauman C. L. Ligon (NSRC) W. A. Williams, Jr. R. B. Clary O. S. Bradham A. R. Koon 4 g M. N. Browne h 9 go h 1 G. J. Braddick J. C. Ruoff ( i J. L. Skolds \\g J. B. Knotts, Jr. B. A. Bursey NPCF wilo B205190183 B20512 PDR ADOCK 05000395 'A PDR .j

1. 00fMEN'T: 1 Rev. 4 of the subnittal did not contain the alditional data that VCSNS was to provide supporting the conclusion that the mechanical integrity of penetrations with non-1E circuits will not be degraded when these circuits are subnerged. RESPO4SE: This concern is discussed in the V. C. Sumer FSAR Response to Regulatory Guide 1.63, Electrical Penetration Assemblies In Containment Structure For Water-Cooled Nuclear Power Plants, (pg. 3A-94). This discussion describes the basis for the qualification of the penetrations to maintain contairunent integrity even with the single failure of any overcurrent protective device. 2. GPNENT: VCSNS comited, during the audit, to provide troof of qualification of the Gulf oil Canpany lubricants by fuel load. The Rev. 4 subnittal states doctrnentation of qualification is under developnent and will not be canpleted by fuel load, but by full power operation. Justification for interim use should be trovided. Also, the lubricants are not listed in Table 1.2-1 " Class 1E Equipnent Subject to Harsh Environmental Conditions, NSSS Tables, nor BOP Tables.

RESPONSE

The Sununer Station has an approved rogram for the specification of I lubricants for safety-related use. Oils and greases are procured to industry standards which envelope the design conditions expected to be seen by the lubricant. These industry standards, however, do not address the radiation resistance troperties of the lubricants. 'Ihe specific concern is that insufficient documentation ensts to show that the o

lubricants used in certain Class 1E motors are capable of performing their function in the harsh environmental conditions postulated to occur following certain accidents. Included in this concern are the lubricants used with certain mechanical equipnent associated with the notors. Westinghouse (W) has provided qualification data on certain Mobil and Texaco oils and Gevron SRI-2 grease used in W equipnent that were tested at W testing facilities. It is reasonable to expect that W qualification data on I.S.O. grade 46 oils can be used to extrapolate qualification justification for I.S.O. grade 32 and 68 oils of the same family. Discussions with manufacturers' reIresentatives indicated that oils of the same family are fornulated of the same identical ingredients and additives but are blended to differing viscosities. Our latest information is that the results of the radiation testing for the oils by W has not been doctanented in an official report. However, there is no specific documentation that critical breakdown of the oils would be 8 expected by 2 x 10 rads. '1here is also sufficient information fran W, in the form of letters and test results to have a degree of assurance in the ra11ation resistance of these oils, h assurance of radiation resistance for the Gevron SRI-2 grease is better documented with information fran W as well as from Chevron. By letter of August 4,1981, Gulf Research and Developnent Ccrpany (Gulf R & D) provided the available qualification data for Gulf lubricating oil and grease. The letter notes that the data for grease is preliminary and the data for oil is dated and should not be applied to current Gulf products. A telecon was held on December 18, 1981,-with Mr. G. J. Schreuders of Gulf R & D. The testing of the Gulfcrown EP-2 grease is now canpleted up 8 to 3 x 10 rads using a slow gansna radiation source. Ooncerning the ' radiation testing of the Gulf Harmony series of oils, Gulf has contracted with National Laboratories at Oak Ridge to do radiation testing of Gulf Oils. The Harmony series will be among the first group of oils tested. e

Mr. Schreuders forwarded this information by letter dated December 21, 1981, to SCE&G. In further discussions with Mr. Schreuders on April 23, 1982, the test plan for radiation testing has been finalized and testing is expected to cmmence within two or three weeks. It may be three or four months before the results of the testing ata available. Mr. Schreuders expects the results to be similar to those of a 1969 Gulf 7 radiation testing program which showed degradation starting at 4 x 10 rads but the oil (Gulf Harmony 32) was still considered suitable for 8 further service after 1 x 10 rads. Since the time of this study some changes have been made in the type and character of the additives usel in these oils. The information therefore cannot be specifically applied to today's product, hence the new testing program soon to be underway. It is the judgement of SCE&G Nuclear Engineering that we Irocure Gulf lubricants as stip11ated in our lubrication manual. 'Ihe Gulfcrown EP-2 grease has been judged acceptable for use by Gulf R & D after exposure to 8 1.5 x 10 rads. Chevron SRI-2 grease has been testal by Westinghouse 8 and is not expected to breakdown until levels higher than 2 x 10 rads. Either of these greases are acceptable. Westinghouse has tested the Mobil DrE Medium and the Texaco Regal "B" oils (industry alternates 8 to Gulf Harmony #46) to 1 x 10 rads Critical breakdown of these oils 8 is expectal by 2 x 10 rads. Gulf R & D is contracting their own independent radiation testing of their oils to include the Harnony series with results expected in 1982. The Gulf Harmony series of oils, which meet the same industry lubrication specifications as its Texaco and Mobil counterparts, cannot be considered qualified based on the Westinghouse radiation testing programs. SCE&G Nuclear Engineering is not aware, however, of any evidence that Gulf oils should be considered suspect to significant radiation degradation and does not see sufficient reason to justify a change to the Mobil and Texaco oils until the results of the i Gulf contracted testing program would show a need to do so. When the testing trogram is empleted, the results will be reviewed for adequate radiation resistance for the intended usage of the Gulf oils, and any action required in switching to Mobil or Texaco oils would be taken at that time, a

s %e establislynent of qualification information on a series of lubricants does not relieve SCPM fra the responsibility of maintaining an "on going" assuran of quality throughout future gocurements, his will be accmcplished by establishing appogiate means to verify that the lubricants are equal or better than that which was qualified. 'Ib this end, Quality Assurance has investigated a bearing manufacturer's controls over lubricants in sealed bearings. Assurance that lulricants thanselves are of a consistently " equivalent" quality shall be established through procurement requirements developed by Engineering in cooperation with QA. Manufacturer controls over product batch testing, identification and sealing of cx>ntainers, product distribution, and our own history or satisfactory product use are sme of the means available for use in the developnent of assurance of the quality of lubricants gocured for safety related application. As can be seen by the above information, SCFM is not inactive in its quest for finalizing the lubrication qualification program. We do not, however, see sufficient reason at this time to revise our current lubrication program with radiation testing of Gulf oils about to ccmnence. The lubricants used at the Summer Station are considered consumable "cmponents" of the Class 1E equipnent and hence have not been individually listed in Table 1.2-1 nor the specific NSSS or BOP tables. Qualification of lubricants will, however, continue to be an outstanding itan to be fully addressed by full power operation. We feel the current status of our program gives sufficient interim justification until that time. 3. CX M Etff: VCSNS states that Valcor solenoid valves corrosion Iroblem has been corrected. The subnittal does not give the cause or corrective action for the corrosion nor does it Irovide the surveillance gogram which will be performed to ensure the problem will not reoccur. o

RESPCNSE: The corrosion was in the attachal D. G. O'Brien hermetic connector pins, causing an electrical short to ground. Corrective action consisted of an analysis of the corrosion found, and the following positive hardware modifications. 1. Stainless steel nipples are to be used with the stainless steel D. G. O'Brien connectors on all Valcor valves instead of galvanized nipples. 2. We area inside the D. G. O'Brien connector where the wires are attachal to the connector pins is to be patted with Dow (brning DC170 potting cmpaund. % is potting material is the same as used in j D. G. O'Brien connectors. 3. Water tight connections between the nipple and the O'Brien connector and the Valcor valve body will be accmplished by using Graphoil tape in the threaded connections. 4. ECN 1747 dated 10/26/81 was issued to install a voltage reducing circuit for the Valcor valve circuits. 5. D. G. O'Brien's " Instruction Manual 1060 Connector Assenbly" was revised to incorporate steps 1, 2 and 3. We VCSNS surveillance and maintenance program will be utilized to monitor this resolution to insure this problem will not reoccur. 4. COMENT The subnittal should state in the BOP Tables and/or BOP detailed reports (DR's) the 20 year qualified life for the Rosemount level transmitter depends on a 5 year replacement schedule of the O-ring. What action is planned at 20 years? I u

RESPWSE: At the end of the 20 year qualified life, one of several actions could take place. 'Ihese actions could include: 1. Replacanent with identical but new transmitter. 2. Replacement with a qualified transmitter of a different or newer type which would have to meet all technical and qualification criteria. 3. Replacanent with a different brand (manufacturer) which would have to meet all technical and qualification criteria. 5. OCBNENT: The DR for the Samuel teore instrument cable (DR 82) should state the cable was qualified for low voltage use (24-48 vdc); and, if it were to be used for an application with higher voltage, the qualification would be reevaluated for this higher voltage. RESPWSE: This DR could be revised in a future revision to the subnittal. However, whenever any piece of 1E equipnent is used in a new application, the qualification of the equipnent is reviewed for acceptability in accordance with approved procedures. We agree that if the cable were desired to be used in h3gher voltage application, such a review would be necessary. This type of condition would exist however for any new or differing application of 1E electrical equipnent. L-

6. CCM4ENT: VCSNS should provide information in the DR's for the PYCO RfD's (DR-01,

46) which states whether the RrD's were tested with the new sealant material, the RID's operated satisfactorily, aM that there was no ingress of rioisture.

RESPCNSE: Here again SG&G took a conservative approach to assure functioning of these RfD's in the event of an MSLB or LOCA event. These RrD's have only two possible moisture entry paths, one is directly through the conduit opening and the other would be at the threaded cap (provided for wire / cable termination). This threaded cap also utilizes a stainless steel 0-ring for sealing parposes. S &G has now installed qualified D. G. O'Brien hermetic connectors on the conduit entry points, and also used qualified DC-170 potting sealant on the threaded caps. As a result, SG&G does not consider it necessary to require retesting of this ccmbination by PYCO. In discussions with PYCO, it was considered that the threaded cap with O-ring did not need to have sealant to Iroperly perform it's function, however, SG&G considered this to be a minimal cost addition to provide redundant sealing of the cap. PYCO considered the conduit entry point to be the area of concern for line break /LOCA qualification. As a result, SG&G has used the hermetic connector approach to Ensitively provide a water tight boundary at the conduit entrance. 'Ihis could be doctanented in any next revision to the subnittal if required. 7. CCMENT: VCSNS did not address the OCW flow instrument for cooling water to the RHR motor. This was to be done by fuel load.

RESPWSE: Concerning the cmponent cooling water (CN) flow indicators for cooling supply to the residual heat removal pumps, an evaluation has been performed to confirm the instrments are troperly classified as non-1E and do not have to be environmentally qualified. The function of the C N supply to the Mm pumps is to provide cooling for the pump seals, because the MR systs handles high temperature fluids during normal plant cooldowns or during post-accident operation. We CN supply for each Mm pump flows directly frm one of two independent, redundant CW supply loops through (in respective order) a manual isolation valve, an orifice, another manual isolation valve, the Ma pump seal heat exchanger, a second orifice (for the flow transmitter), and two manual isolation valves to the OCW system return loops. % e C W flow rate to the M R pumps is established by orifice size during systs flow balancing ard is not adjusted during normal operation or rost-accident operation. The position of the manual isolation valves in the supply and return lines frm the MR rump seals are administratively controlled to assure that ON flow is maintained at all times except during any maintenance that would require securing CW flow to the Mm pumps. The purpose of the flow transmitters in the C N supply to the M a pumps is to provide additional assurance, by means of a low-flow alarm, that the manual valves are not closed inalvertently during maintenance and testing t activities in the vicinity of the valves in the auxiliary building. This alarm function is not required during post-accident operation of the OCW systs because maintenance, testing and manual operation of equipnent in the auxiliary building is conducted on a limited basis and under strict procedural controls. Also, the plant operators do not rely on this flow indication to perform any actions following an accident; and failure of the instrument (as a result of high radiation fields in the vicinity of the transmitters) would not cause the operator to perform actions adverse to safety because of the procedural controls on post-accident activities and the availability to the cperator of other indications that the OCW systs is functioning properly. Therefore, the flow transmitters are properly categorized as non-1E and are not required to be enviromentally qualified.

8. C09ENT: The Reliance fan motors had not originally been considered qualified because the proprietary data at the Reliance Cleveland office had not been audited. Ch 6/6/81, a GAI audit was performed at Cleveland on the Reliance fan motors and found acceptable. This method of qualification used is not generally allowed and would be acceptable only on a special case-by-case basis. The audit performed by GAI would have to include a detailed summary of the test report and the qualifying environnental data as it pertains to VCSNS. h VCSNS should make every effort to obtain qualifying data fran Reliance to be placed in the equipnent file. RESPCNSE: SCE&G and GAI were not successful in being able to obtain hardcopy proprietary data frcm Reliance. This is not an uncomon occurrence although fortunately only a few of the V. C. Sumner equipnent suppliers have taken such a position. The audit performed by GAI was canpleted by individuals involved with the NUREG 0588 review and also knowledgeable with the necessary documentation required to fulfill qualification criteria for the V. C. Sununer Nuclear Station. These efforts have resulted in a review which SCE&G considers acceptable to determine that the installed notors are indeed qualified to the parameters so stated in Rev. 4 to the NUREG 0588 Subnittal. 9. CXM1ENT: DR-48 (3) for the Rosanount Beactor Building Sump Level Transmitters states that nurgin is not applicable for an arbitrary chosen value of time. I think more explanation is required as to what manJ n VCSNS is ) i talking about and why it is not applicable. u u

1 RESPWSE: The margin VCSNS is discussing in DR-48, Its 3, concerns the first few seconds of the test LOCA profile versus the first few seconds of the VCSNS postulatal LOCA temperature profile. We main steam line treak postulutal profile has a quicker tmperature rise than the test gofile during the first few seconds of the LOCA event. We vendor's Irofile uses an arbitrary value for temperature rise based on a general knowledge of requirments fran nuclear power plants. We lack of margin during the first few seconds of the test is considered acceptable since the remainder of the test includes a considerable margin over the VCSNS postulated profile.

10. COPMENT:

The operability requirment of the Westinghouse RilR pump motor is listed as 4 nonths in the Rev 4 subnittal, but during tiu July audit the operability was listal as 1 year. Which is correct? If the Rev. 4 subnittal is not correct, then VCSNS should check the operability requirement of the listal equipnent to ensure correctness and qualification. RESPWSE: The Rev. 4 required operability time of 4 months is the correct value, and as such, the denonstrated operability was evaluated against this 4 month criteria.

11. CONENT:

The aging temperature and time for the Westinghouse RIIR pump motor is listed as "NA". This notor has been aged and the aging data should be entered into the subnittal. We aging temperature and time for all other equipnent in the subnittal which has been listal as "NA", "See Kerite Relmrt" or "NorE 51", should be checked and the missing information, if 1 l

any, entered into the submittal. Also, the method of analysis and justification (i.e., arrhenius,10*C Rule, etc.) used to extend qualified life should be stated in the subnittal. RESPCNSE: Ebr the RHR pump motor, this listing was marked NA since the entire and canplete notor was not qualified as a singular unit. Instead, notorette testing was utilized. As stated in DR-W(2) the materials in the insulation systan were subjected to thermal and radiation aging. 'Ihermal aging was prformed at 200'C for 21 days for the equivalent of 105'C for 40 years. As stated in DR-W(1), this thermal aging followed the 10'C " rule". The Kerite information was considered roprietary and as a result was I not included in the subnittal. We did however obtain permission to reproduce the accident Irofiles which we included in the back of the submittal. These Kerite proprietary reports are however on file at the VCSNS cantral file. In regard to other instances, SCE&G described within the DR's the method of analysis and justification used, such as, for (konite where the Arrhenius concept was discussed in DR-05(8).

12. CCMerr:

Swa equipnent was to have Iroblems resolved by fuel load now have been changed to full power operation.

1) Veritrak Transmitter

2) Motor Lubricants

3) Hydrogen Recombiners i

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i RESPCNSE: These resolutions had not been cmmitted by SCE&G to be resolved by fuel load. However, SG&G expects successful testing of the Veritrak Transmitter to be empleted in mid 1982, thus far Westinghouse has not found any test results that would indicate that it will not satisfactorily pass testing. Also contained herein (Question #2) is a status and justification for the SG&G proposal to cmplete lubricant qualification by full pwer operation. In addition, SG&G has done a material review of the Hydrogen Recmbiner in accordance with MURKi 0588 Category II 4(2) aging requirements. he Hydrogen Recombiners have been qualified to IEEE 323-1974 by Westinghouse as we are sure the NRC is aware, and at this pint in time SCE&G is actively pursuing a purchase order with Westinghouse to upgrade our qualification documentation with a hard copy of this IEEE 323-1974 testing. h is is expected to be empletal by full pwer operations.

13. A) CONENT:

VCSNS stated that ASCO solenoid valves would be installed to replace the following Westinghouse supplied air operated valves. XVT-8149A/B/C-G XVD-8047-RC XVT-8871-SI ICV-1003-WL XVD-7126-WL XVT-8152-CS i XVT-8880-SI XVT-8860-SI XVI-8961-SI ICV-44B-RC ICV-445A/B-RC L

A) RESPONSE: his is a correct statement, solenoid valves have been installed. B) CONENP: me subnittal did not ccintain qualification information on the following valves. XVT-8149A/B/C-CS XVD-8047-RC XVI-8871-SI ICV-1003-WL XVD-7126-WL XVT-8152-CS XVI-8880-SI XVT-8860-SI XVI-8961-SI B) RESPO3SE: his is not correct, the subnittal table 1,2-1 and the BOP foldout pages contain the qualification information on these valves. C) 00BNEtTr: The tag nunbers of the ASCO valves which have " Note 64" under " Operability Denonstrated" do not match the ones listed in Table 1.6-2. C) RESPONSE: All 1E harsh environment ASCO solenoids have been qualified and installed. Any " Note 64" in the subnittal is a clerical error and should not be considered pertinent. i 1 i L I

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14. COMMP:

The cabnittal did not state whether the ASCO solenoid valves XVG 9627A/B, iWL3531, 3536, 3541, 3546, 3551, 3556, XVT-2662A/B, ~ XVI-6384A/B, XV"-6385A/B, and XVI-2660 would be tested to ensure qualification of the conduit connection seals (see DR-60). \\' RESPCtJSE: e The conduit connections were sealed by SCE&G to Irovide an added measure of assurance that the valves would function in the event of LOCA envirornnental conditions. This sealing was performed by the use of qualified D. G. O'Brien hermetic connectors as contained aM listal in Rev. 4 of the NUREG Subnittal. SCE&G does not consider it necessary to require retesting of the ASCO solenoid valves to ensure the D. G. O'Brien connectors can Irevent moisture and/or sIray intrusion.

15. CONENT:

The subnittal does not indicate if a test report of the -N adhesive is part of the qualification package for the Raychen Nuclear mtor Connection Kits (see DR-80(10)). s u

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RESPONSE

i The -N adhesive was testal an an integral part of the entire kit and is therefore covered by the same test report, not a different one. j

16. CONEMr:

There is no detailed qualification report on the Gould-Shawmut fuses (page B-34). Is there a surveillance program to enusre no premature failure due to corrosion or other means? T ,_.s

m ,g ~ c p N RESPWSE: l' i.. As discussed in DR-19, a prmature failure of the fuse is totally acceptable. enese' fus~ s simply isolate the non-1E heat tracing circuits c from their IE power supply sources. As a result, arry p erahlre failure by any mechanism would tu acceptable and provide no safety concern whatsce;er.

17. CWMEte:

DR-76 for " Phenolic. Type" blocks states ".... tanperature and radiation are the only par.veters that would appear to cause the hise block to fail. " Has this been dccumented in the qualification file? Why was hinidity not addressed. RESPWSE: i. This definitely was doctznented in the VCSNS qualification Central File. At the time of review, these blocks had not empleted the full IEEE 323-1974 LOCA and MSLB testing. As a" result, SCE&G chose to only use thsse blocks in areas where there would not be LOCA or MSLB high noisture , ard lumidity conditions. As a msalt, we qualifial these blocks for their normal environmental conditions plus LOG Aadiation that they might see.. tis we have been able to mply doctxnent in 'our qualification file. It should be noted that subsequently these blocks have passed the full IEEE 323-1974 qualification.

18. Cat +CE:

Note 50 on page B-38 is very general. te equipnent whose qualifiel life depends on the periodic replacement of conponents (i.e., seals, solenoids, gaskets, etc.) should state when and what equipnent/conponents are to be replaced due to aging. er l Le

Example: The Allied solenoid valves have a 40 1 ear qualified life with a 5 year replacment program for seals and solenoids. The ASCO solenoid valvas indicate qualification is based on the periodic replacement of equipnent canponents, but "what" and "when" is not given. RESPCNSE: SCE&G intended to provide this infonnation in the DR's wherever it was applicable. This was an oversight to not include it for the ASCO solenoid valves. However, the elastamers and coils will be replaced every 4 years to maintain qualification. This was documented in the SCE&G review and has been incorporated into the SCE&G documentation central file.

19. COMENT-Equipnent whose qualified life is less than 40 years should have in the subnittal what action will be taken at the end of its qualified life (i.e., replacanent with new equignent, requalification of original equipnent, etc. ).

RESPCNSE: As discussed in Comment #4, SCE&G will make this determination on a case-by-case basis prior to the end of qualified life. However, SCE&G will install qualified equipnent which will be aiequately docmented for its intended normal and accident functions.

20. CONENT:

The subnittal should list for each equipnent its the method of qualification and the report I.D. for each environmental parameter. In see cases it was difficult to tell which envirorrnental parameters were qualified by test and which were qualified by analysis. 1 l

RESPCNSE: This coment apparently only applies to that equipnent which was stated in the foldout pages as being qualified by a conbination of test and analysis. Wherever the qualification did not specifically meet the NUREG 0588 requirements, a (Deviation Report) DR was written to provide the technical reasoning and thought process for acceptance. The canplete and detailed review is contained in the VCSNS documentation central file and it was not considered necessary to address this specifically in each foldout page. SCE&G com iders the method of analysis has been adequately discussed in the DR's to demonstrate the reason and method for acceptance.

21. COM4ENP:

The subnittal should list all the references used for the abnormal or accident environment for each parameter. RESPCNSE: Section 1.3 of the subnittal discusses the nethod and FSAR references for the developnent of the environmental service conditions. SCE&G did attanpt to provide a reference figure for each tanperature and pressure parameter in each line itan on the foldout pages for al: normal and accident conditions. Radiation and spray parameters are discussed in Section 1.3 and it was not considered necessary to reference these other than to indicate post-LOCA operchility time radiation dose when calculated for specific equipnent.

22. CONENP:

Equipnent that is not qualified at this time should have the qualification status statal in the W or B pages under " Qualified Life". L

Example: 1) Hydrogen Recanbiner

2) Veritrak Transmitter

3) W Accoustic Leak Monitor RESPCNSE:

These were left blank intentionally and the status was specifically listed in detail in Table 1.6-1. In any pssible future revision, SCE&G could reference this table in the foldout page under the heading of " Qualified Life".

23. CO NENT:

VCSNS should commit to periodically placing the results fran reviews of component /equipnent failures during "Pregmid Preventative Maintenance" and " Corrective Maintenance" into the subnittal to keep the doctanentation up to date. RESPCNSE: SCE&G does not consider this necessary, since the VCSNS doctrnentation central file will be performing this function. In addition, SCE&G is awaiting the new 10CFR50.49 rulemaking which will require a subnittal of information. It is our understanding that the NURE 0588 Subnittal requirements will be deleted upon issuance of the new rulemaking.

24. CONENT:

On sane equipnent, the demonstrated operability does not seem to include adequate margin over the required operability. RESPCNSE: SCE&G specifically reviewed all equipnent to meet the margin requirerents of NURE 0588. Wherever there was any difference between L

the testing qualification nargin and NUREG requirements, the difference was discussed and justified in the DR section of the subnittal. 25. _C g : 9 BOP Tables do not provide information of the concentration of chenical spray used. _RESPCNSE: Ebr each piece of 1E equipnent the spray testing ard results were cmpared to the required concentrations and durations as stated in Section 1.3-4 of Ibv. 4 to the NUREG 0588 Subnittal. mis review is documented for each piece of equipnent on the Check /Sumary Sheets as contained in Appendix I to the NUREG Subnittal. All of these reviews are filed in the V. C. Sumer Central File for environmental qualification. h is was a part of the total doc mentation as audited by the NRC Environmental Qualification Team during the July,1981 site review trip. We subnittal BOP foldout pages however only have the spray duration listed. However, as stated above, the tested spray concentrations were cmpared to required criteria and documented. Where any deviation existed in regard to either concentration or duration, this was doc mented and discussed in the Deviation Report for that piece of equipnent in the NUREG Subnittal. As a result, SCE&G did perfonn a total review to enempass both duration and concentration criteria for chenical spray qualification. L ~

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1 ( [ DESIGN VERIFICATION RECORD PAGE 1 0F FILIN G PROJECT: V. C. Sumer Nuclear Station, Unit 1 CODE /* I+ / .,g,, REVISION: Ccmpan'es SU B J ECT: CoAirsinneur Asr-LOCA Dose DATe, &.pg SECTION N AME AND NUMBER Applied Engineering Analysis Department W.O. 04-4461-/24 Nucleae (2109) and Mechanical (2107) Sections Safety Class M. F1. b)ASELus $ nna l fVO_ f PROJECT ENGINEER DATE CL A S$1 FIC A TIO N ORIGIN ATOR I THIS AN ALYSIS CONTAINS ASSUMPTIONS WHICH REQUIRE LATER CONFIRMATION. l YES (IDENTIFY BY P AGE NUMBER BELOW) NO COMPUTER PROGRAMS NOT USED USED CERTIFIED PROGRAM PER DCP1.50 USED, PROGRAM NOT CERTIFIED BUT VERIFIED PER CAPI.00 Ad#eruwW /weso ORIGIN ATOR DATE NO VERIFICATION REQUIRED, DESIGN DUPLICATES PREVIOUSLY VERIFIED DESIGN NOTED BELOW: NAME FILING CODE DATE VERIFICATION IS REOUIRED (SEE DCP 2.05, SECTION 2.7): METHOD ~~T3E S I S A3 2.Th> F LO (IF CUALIFICATION TESTS ARE USED ATTACH COPY OF TEST CONDITIONS AND ACCEPTANCE CRITERIA) V E RI F1 E R Y- /X SLI U C pQ hfjfgj f e w l-//)O/8 { SELECTION OF VERIFIER USE OF QUALIFICATION TEST VERIFICATION METHOD, IF APPLICABLE /l/l$f!1I k Le C W Y// 0 8 1 l'#// $ECTION MAN AGER OATE VERIFIER'S ATTESTATION: THE (DESIGN DOCUMENT HAS)(REVISIONS TO THE DOCUMENT OCCURRlNG SINCE THE PREVIOUS VERIFICATION HAVE) BEEN REVIEWED BY ME IN ACCORDANCE WITH DCP 2.05. ANY FINDINGS UNCOVERED DURING THE COURSE OF MY REVIEW HAVE BEEN DIRECTED TO THE ORIGINATOR AND RESOLVED. [ VERIFIER DATE P.E. REVIEW AND APPROVAL (FOR DESIGN ANALYSIS AND CALCULATION ONLY) c/ PRO;Ec7 ENGINEER t,. oATE w, s Gilbert / Commonwealth power ENGINEERING RE ADING L

r ( ~ .wSJECT OISID PQG2 Containment Post-LOCA Dose 1.6.1 2 r (3 Gilbert Associates,Inc. or a" l - Ld M- =J - M y -c _,.. .,4.. MICROFILMED PAGES ANALYSIS / CALCULATION oaiGINAToa M.Waselus DATE 12/18/80 Object: To calculate acceptable values for the containment post-LOCA integrated dose for V. C. Summer for equipment qualification using the information contained in References 1 and 2.

References:

1. IE Bulletin No. 79-OlB, " Environmental Qualification of Class IE Equipment," January 14, 1980. 2. NUREG-0588, " Interim Staff Position on Environm atal Qualification of Safety-Related Electrical Equipment," December, 1979. 3. V. C. Summer FSAR Section 6.2. 4. V. C. Summer FSAR Figures 1,2-4, 1.2-5, and 1.2-10. A. Containment Centerline Dose for 30 Days Assumptions: 6 1. Containment free volume - 1.84 x 10 ft3 (Ref. 3 - Table 6.2-1) 2. Reactor Power - 2910 Mwt (Ref. 3 - Table 6.2-2) Results: 7 From Figure 1 of Reference 1 the resultant integrated dose is given as 2 x 10 R. 7 For qualification a value of 2.4 x 10 R is specified to include a 10% factor to cover potential S exposure and a 10% margin for conservatism. 6 For equipment qualification for a MSLB accident, a value of 2.4 x 10 R is- / acceptable (Figure 1, Reference 1). B. Conservative estimate of Post-LOCA integrated dose to "short term" equipment on the 412' and 436' elevations of V. C. Summer reactor building outside the steam generator compartments. Assumptions: 1. The equipment is conservatively assumed to be located in a compartment equivalent to one half the free volume of the elevation. This is conservative in that no credit is taken for reduction of the volume by any equipment or concrete walls, n\\ ) PROPRIET ARY INFORM ATION OF GILBERT A$$OCI ATES, INC. - FOR INTERN AL U$E ONLY G As 44611-78

r p ' sDJECT CISID PQGE r Containment Post-LOCA Dose 1.6.1 3 g Gilbert Associates. Inc. or a"l Ld _d il _d r c_ _ j.... MICROFILMED PAGES ANALYSIS / CALCULATION oaiGIN AToa M. Waselus DATE 12/18/80 2. The required operational time is 1 hour. 3. The reduction factors are taken from Reference 1, Figures 2, 3, and 4. 4. A minimun of 24" concrete shielding is available (Reference 4) to reduce the dose from the centerline cloud dose. Calculation: 7 1. The total integrated centerline dose as given in Item A (above) is 2.4 x 10 R. 7 R and 24" of concrete the From Figure 2 (Reference l{ at a dose of 2.4 x 10 2. resultant dose is 7.0 x 10 R. To this, the dose from inside the compartment / must be added. 3. The free volume of the elevations are given as follows: 2 412' V = nr h = x(63 ft)2 (434-412) ft 3 = 274,320 ft 436' v = n(63 ft)2 (461-436) ft = 311,724 ft Where the configuration and dimensions are given in Reference 4. Using 1/2 the,,1,p,rger volume, the dose correction factor from Reference 1, Figure 3 is 0.M (conservative assumption sin _cc the larger volume results in a higher dose). The sum of the doses is then given as = 4 7 0M 8 ~'I 6 7 x 10 R + (2.4 x 10 R) (0,-Idd) = AM9 x 10 R 4. From Figure 4 (Reference 1) the correction factor for 1 hour operational time is 0.15. Therefore, the resultant integrated dose for equipment at 412' and 436' elevations is M R. (One hour required function time.) 1 3 x so' ( C. Conservative estimate of the containment post-LOCA centerline dose for 4 months and 1 year. The containment integrated LOCA dose provided in Item A was for a time period of 30 days. Subsequently, the need was identified for integrated doses for, " longer time periods. In order to expedite an answer to meet client requirdmqnt/y conservative doses were established based on extrapolating the data given In T y Reference 1 and Item A. G Al 4461 t=78 PROPRIE T ARY INFORM ATION OF GILBERT ASSOCI ATES, INC. - FOR INT ERN AL USE ONLY

f'1 W a3 JECT ' CISID PQGE Containment Post-LOCA Dose 1.6.1 4 rg, Gilbert Associates,Inc. or a"l Ld W _J al .r 2 g ,l. .P. PAGES MICROFILMEO ANALYSIS /CALCULAT10N ORIGIN ATOR g, gage}gg DATE 12/18/80 Assumptions: 1. The 30 day integrated dose is 2.4 x 10 R as given in Item A. pf 2. Figure 1 (attached)3 1s a plot of the integrated dose values from Tables D-5 and D-8 of Reference 1. The doses for 4 months and 1 year are conservatively estimated by extrapolating the 30 day design value @ a constant slope. The maximum value is based on the containment sump curve and is to be used as the design basis for equipment qualification. Calculation: Relative Dose at time of interest x Design 30 day dose = Design dose at time Relative Dose at 30 days of interest 7 7 At 4 Months: 6 x 2.4 x 10 R = 4.0 x 10 R 6x 0 7 7 ~ 7 1.0 x 10 x 2.4 x 10 R = 6.1 x 10 R 1 Yem 3, 3.96 x 10 Note: The above are acceptable values for equipment qualification post-LCCA inside containment except for equipment located directly above the sump, in the vicinity of filters or equipment recirculating post-LOCA fluids, or submerged in contaminated liquids. Results: The results were documented in the following memos: "V. C. Summer Nuclear Station [ Memo from M. M. Waselus to J. W. Reitnauer, Post-LOCA Containment Integrated Dose," December 12, 1980. g

Memo from M. M. Waselus to J. W. Reitnauer, "V.

C. Summer Nuclear Station Post-LOCA Containment Integrated Dose," December 18, 1980. Copies of the memos are given as an Attachment to this calculation. 3' % p.M. i fo J^ ^J W, " v. c.. & 6%.f-t-oc A W n /O 198/. i y N PROPRIET ARY INFORM ATION OF GILBE RT ASSOCI ATES. INC. - FOR INT ERN AL USE ONLY G Al 44611-78

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r 3 Q'f g 1,. m i ( r. c. (.c.t It u.'E & LJ & ATTACHMENT 1 ( g / f z, f g, p f Conservative estimate of Post-LOCA integrated dose to'"short tera". equipment' on the 412' and 436' elevations of V. C. Summer reactor building. i ' Assumptions: 1. The equipment is conservatively assumed to be located in a compartment [ equivalent to one half the free volume of the elevation. This is t r conservative in that no credit is taken for reduction of the volume by any equipment or concrete walls, t 2. The required operational time is 1 hour. 3. The reduction factors are taken from Reference 1, Figures 2, 3, and 4. r 4. A minimum of 24" concrete shielding is available. Calculation: 7 1. The total integrated dose as given in the memo is 2.4 x 10 R. 7 2. From Figure 2 at a dose of 2.4 x 10 R and 24" of concrete the resultant 0 dose is 7.0 x 10 R. To this,the dose from inside the compartment must be added, t F - 3. The free volume of the elevations are given as follows: 2 ^ 412' V = Trr h = Tr(63 f t)2 (434-412) f t 3 I = 274,320 ft 'f> ',\\? 's,; .'s.: m, - - - ~ - _ - . - - -. -,.,-,-:--..-~

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il2/#:S 28 0 to-J. W. REITNAUER from-M. M. Waselus subgtt-V. C. Summer Nuclear Station Post-LOCA Containment Integrated Dos.r aturamiten L3:,,1/hBL Ref: 1. Memo f rom M. M. Waselus to J: R. Ruii:!nana r.. "4. C'. $hmmter Nuclear Station Post-LOCA <crtti;rhamunc Dat;.q;;;ated D:ma,."' December 12, 1980. 2. IE Bulletin No. 79-01B, "Erniinnmentad 4tutllfili;catibni c6 Class IE Equipment," January D,, 3PH)L. The containment integrated LOCA dose ymv.viiludl i;:n Rafanunce.11.vam Setr a time period of 30 days. Subsequenfly,. :thu, acud, w.us; hiuntidlibd! for integrated doses for longer time pert.ul'.s.. I:n ardue to e:>;1udS:u an answer to meet client requirementr., ennntrutriur dimum waru-established based on extrapolating the diamo givum f!m ituitrtutuun 11 and 2. The following are acceptable vollnes; Tnr.uptbamunc. nut 21!Diiaatthra post-LOCA inside containment except int entAmmuna Ibuanath diilaucit3 y above the sump, in the vicinity of f 3Ilt: itis; nr submun:Indi ini euntau:dnated liquids: 4 month integrated dose 4 t! :x EthR one year integrated dose - 6.3 1 JY.T The method by which these values were dici ar:Jaadt iii, atavGlunt ini to this memo. h.,,/h.[1.bbc.cb+g-M. M. WARCIJ!S NUCLEAR INW123EE MMW:mm Attachments cc:

11. E. Yocom G. J. Braddick F. X. Rebill G. M. Kowal 4

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L ALW M 1 'L / I S/S u Conservative estimate of Post-I.0CA containment integrated dose for four months and one year.

(V. C. Summer Nucicar Station) Assumptions: 7 1. The 30 day integrated dose is 2.4 x 10 R as given in Reference 1. 2. Figure 1 of the attachment is a plot of the integrated dose values from Tabica D-5 and D-8 of Reference 2. The doses for 4 months and 1 year are conservatively estimated by extrapolating the 30 day design value at a constant scope. The maximum value is based on the containment sump curve and is to be used as the design basis for equipment qualification. Calculation: Relative Dose at time of interest x Design 30 day dose = Design dose at time Relative Dose at 30 days of interest 6 6.6 x 10 7 x 2.4 x 10 R = 4.0'x 107 R At 4 Months : 3.96 x 106 7 1.0 x 10 7 7 At 1 Year 6 x 2.4 x 10 R = 6.1 x 10 R 3.96 x 10 , ~ ~ ~,

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kx'. l 1.t. k ' \\ R.i i - y y gc. /. G. / Rev 2 memorandum Gilbert / Commonwealth to: J. W. REITNAUER from: t!. M. Waselus subject: V. C. Summer Nuclear Station Post-LOCA Containment Integrated Dose April 10, 1981 Ref.: 1. Memo from M. M. Waselus to J. W. Reitnauer, "V. C. Summer Nuclear Station Post-LOCA Containment Integrated Dose," December 12, 1980. During design review of the calculation package, an error was discovered in one of the values presented in Reference 1. The incorrect data was for the one hour integrated dose to equipment at the 412' and 436' elevations outside the steam generator compartmentc. 6 R which supersedes the previously The correct value is 1.3 x 10 reported value of 6.6 x 105 R (Ref. 1). All other reported values were determined to be correct. e/[]l}U W G II. M. WASELUS NUCLEAR ANALYSIS BDIW:mm cc:

11. E. Yocom G. J. Braddick G. M. Kowal

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( ( DESIGN VERIFICATION RECORD PAGE 1oF,3 FILING [*I* /A PROJECT: CODE V. C. Summer Nuclear Station, Unit 1 Su BieCis Courmanear Posr LXA Dost, REvlSION: 0 Ccmparue: } 4 MostrH APERAG/LITF AGOUIREMEAfr DATES 6/f/8/ SECTION NAME AND HUMBER Applied Engineering Analysis Department W.O. 04-4461-Nuclear (2109) and Mechanical (2107) Sections Safety Class W /9. $Li l//<A 81[~'os) b Y/ C L AS$l FIC A TIO N ORIGINATOR PROJECT ENGINEER DATE THIS AN ALYSIS CONTAINS ASSUMPTIONS WHICH REQUIRE LATER CONFIRMATION. YES (IDENTIFY BY PAGE NUMBER BELOW) NO COMPUTER PROGRAMS / NOT USED USED CERTIFIED PROGRAM PER DCP1.50 USED, PROGRAM NOT CERTel* LED BUT VERIFICO PER CAP 1.00 ~# ORIGINATOR DATE NO VERIFICATION REQUIRED, DESIGN DUPLICATES PREVIOUSLY VERIFIED DESIGN NOTED SELOW: NAME FILING CODE DATE VERIFICATION IS REQUIRED (SEE DCP 2.05, SECTION 2.7): A MJ hU METHOD y 7 (IF QUALIFICATION TESTS ARE USED ATTACH COPY OF TEST CONDITIONS AND ACCEPTANCE CRITERIA) VERIFIER WE44e4> (4 ues] / SELECTION OF VERIFIER USE OF QUALIFICATION TEST VERIFICATION METHOD, IF APPLICABLE l/ / #iECTION MAN AGER A?AwiJask 6/V/A/ DATE VERIFIER'S ATTESTATION: THE (DESIGN DOCUMENT HAS)(REVISIONS TO THE DOCUMENT OCCURRING $1NCE THE PREVIOUS VERIFICATION HAVE) BEEN REVIEWED BY ME IN ACCORDANCE WITH DCP 2.05. ANY FINDlHGS UNCCVERED DURING THE COURSE OF MY REVIEW HAVE BEEN DIRECTED TO THE ORIGINATOR M /'Sc J 6Me/ ^* " ' ' ' * - VERIFIER D' ATE P.E. REVIEW AND APPROVAL (FOR DESIGN ANALYSIS AND CALCULATION ONLY) [ PROJECT ENGINEER ,.DATE ' eq\\ 5 Gilbert / Commonwealth \\h' G At 6 6-80 POWER ENGINEERING. RE ADING

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