ML18113A617
| ML18113A617 | |
| Person / Time | |
|---|---|
| Site: | Surry  |
| Issue date: | 11/10/1978 |
| From: | Stallings C VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.) |
| To: | Harold Denton, Schwencer A Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 7811140128 | |
| Download: ML18113A617 (5) | |
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VIRGINIA ELECTRIC AND POWER COMPANY RICHMOND,VIBGIN IA 23261 November 10, 1978 Mr. H. R. Denton Office of Nuclear Reactor Regulation Attn:
Mr. Albert Schwencer, Chief Operating Reactors Branch No. 1 Division of Reactor Licensing U.S. Nuclear Regulatory Commission Washington, D. C.
20555
Dear Mr. Denton:
Serial No. 623 PO/HSM:scj Docket Nos.
50-280 50-281 DPR-32 DPR-37 License Nos.
Enclosed herewith are 40 copies of Revision 8 to the document entitled "Steam Generator Repair Program, Surry Power Station, Unit Nos. 1 and 2" submitted in our letter of August 17, 1978.
The revision contains supplemental information requested by your staff.
The document should be revised in accordance with the attached instructions.
If you have any questions regarding this material, we would be pleased to meet with your staff at their convenience to discuss them.
Enclosure cc:
Mr. James P. O'Reilly Office of Inspection and Enforcement Region II Ve~:J * '
C. M. Stallings
(,h/
President-Power Su ply~
Production Operations
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COMMONWEALTH OF VIRGINIA
)
) s. s.
CITY OF RICHMOND Before me, A Notary Public, in and for the City and Commonwealth aforsaid, today personnally appeared S. C. Brown, Jr., who being duly sworn, made oath and said (1) that he is Vice President - Power Station Engineer-ing and Construction, of the Virginia Electric and Power Company, (2) that he is fully authorized to execute and file the aforegoing Amendment in behalf of that Company, and (3) that the statements in the Amendment are true to the best of his knowledge and belief.
Given under my hand and notarial seal this l~ 'Jh day of
C-'------
b)./7vc't11hec
, 1978.
/~L-My Commission expires --~J~t::?t=.....Y1'---'-'V.'--='c::J~Y~,~y--2:'--'-'~~/__,J~~l~'f--22~)---------~
~ NotaryPublic (SEAL)
STEAM GENERATOR REPAIR PROGRAM FOR TIIE SUHRY P0\\"1m STATlON UNIT NOS. 1 and 2 REMOVE Revision 8 e.....
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. exposure commensurate with oyerall program 9bjectives. Special a*~folding and other components will.be pre~a'.bricated to the tent possible to minimize radiation exposure and outage time.
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The rek~t'or cavity will be covered by str~ctural members to minimize, the possibility of damage to tife reactor vessel and associat~d components during the repait program.
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i The repair program will be completed in accordance with the Vepco Nuclear Powe~\\Station Quality Assµi-ance Manual and Section XI of the ASME co4e, including sucq/items as interaction of repair activities with\\,the unaffected/part of the station, design reviews, radiation control\\procedures,;document control, material-acquisi-tions, etc.
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The actual repair p;*&~ess,k11 be similar to the methods used during original construction b{'lthe units.
Much of the experienced gained during original construc,tion is applicable to the repair process and will be used as appro\\riate.
The potential envir/~enta*~\\effects of the repair program are expected to be min:iinal.
How~ver, reasonable precautions will be I
exercised to furtner minimize any environmental impact.
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Presently instcj!lled station facilities will be augmented as required to aotomodate the additidnal personnel who will partici-pate in the r,pair program or to f;~ilitate the actual repair work.
The afeas of special concern 1re facilities to prevent the spreadff radioactive contaminati6n, disposal of radioactive material,and security provisions.
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. I The maj o"t* portion of the repair program will be performed by a commercial installer under the direction of\\Vepco personnel.
It is;presently anticipated that Vepco will 1utilize its own radia!tion control procedures and personnel. \\T.he installer will pro"'fide quality control personnel and procedur~~ and Vepco will provide quality assurance personnel.
The instal'ler will be re4uired to have an ASME "N" stamp applicable to \\he work he i£ to perform.
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I he length of the steam generator repair outage is no'ty' estimated to be approximately 180 days.
This schedule is predi2~ted on working 24 hrs/day.
The schedule is divided into the following phases:
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Preshutdown activities
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Shutdown and preparatory activities
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Removal activities
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Installation activities
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Post Installation activities
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Startup activities Post Startup activities
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Details and criteria used in the selections of the filtration unit
RESPONSE
and sump system of the Engineered Storage Facility shown in Figure 5.3-1 should be provided.
Include estimated rqdiation levels on the outside surface of the facility, at the nearest unrestricted area, and the site boundary.
Also provide jwitification that the facility will not flood under a plant desigJ basis flood or describe the flood size and probability for which the facility would be pro-tecte.
The basic design crite~ for both th/.filtration unit and sump system of the engineered storage facil\\y is that they be simple, maintenance free and require no outside electrical power.
Tnt filtration system is a penetration
\\ I in the building wall which will cont~in a HEPA filter. This will provide vent-
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ing to accomodate air expansion/co9>tra'ction.
No forced or induced ventilation is provided.
It is anticipated ;that th\\ filter will be changed on a periodic basis.
The sump system will)/ a passive\\ystem that will merely consist of provisions for any liquid to' drain to a sum~ This sump will be checked period-ically by use of a dip sti~ and pumped out. i~necessary.
No significant water I
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accumulation in the sump is anticipated. The bui'\\ding will be sealed against rainwater intrusion.
Condensation may contribute ~ight amount.
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The survei;nce program proposed for the storage f'q_c~lity for the first year is ;o check the sump level, check residual radio*activity levels inside the b ilding, and cha.nge the HEPA filters on a monthly basis.
At the collected will be reviewed and if warranted the period may be increased from monthly to quarterly.
Provisions in the building design have been made to allow the above sur-veillance activities to be performed from outside the building. It is not an-ticipated that entry to the storage facility will be necessary.
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