ML19319C194
| ML19319C194 | |
| Person / Time | |
|---|---|
| Site: | Davis Besse  |
| Issue date: | 08/28/1978 |
| From: | Haass W Office of Nuclear Reactor Regulation |
| To: | Engle L Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 8002050783 | |
| Download: ML19319C194 (4) | |
Text
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50-34{
n AUG 2 81978
/ocketNo D
. 50-346 y:,
MEMORANDUM FOR:
Leon Engle FROM:
Walter P. Haass
SUBJECT:
QA8 CORRECTIONS FOR DAVIS BESSE, UNIT 1 TRANSFER PACKAGE QAB has reviewed the Davis Besse Transfer Package (memorandtsa, Roger S.
Boyd to V. Stello, Jr.) and has identified several necessary corrections as indicated on the enclosed sheets.
My concurrence on the transfer package is contingent upon your incorporation of these corrections.
Original signed by Walter P.Haass Walter P. Haass, Chief Quality Asstesnca Branch Division of Project Management
Enclosures:
1.
Item 11, page 7 of Enclosure 1 2.
Pages 1 and 2 of Enclosure 3 DJ&MiBUTION:
Vuocket File QAB Projects d\\,'
QAB Chron. File
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DJSkovbolt, DPM c' r;--_ ~
RCueYoung, DPM f
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- JGilray, QAB RMcDennott, QAB
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l of duties were included in the staff's reghests for information \\.
regardin'g Revision 1 to the Fire Hazard Analysis Report for Davis-Besse, Unit 1.(\\
Reviewer _2gstonsibility and scheduling for resolution of this matter is identical t3 tem 5 of Enclosure No.1.
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s-12.
Modification to Spent Fuel Storage Capacity l-By letter dated December 19, 1977, the licensee requested an amendment i
to License NPF-3 for augmenting the existing spent fuel storage capacity.
A Federal Register Notice was filed on March 8,1978 a
specifying a time limit o'f April 14, 1978 for filing a timely petition to intervene.
No timely nor tardy petitions to intervence have been received as of July 6,* 1978.
On March 8, 1978, staff requests (DOR) for additional.information regarding the licensee's submittal of December 19, 1977 was sent to the licensee.
The licensee's response to the staff's request for information was received on April 4,1978.
Subsequent to theslicensee's submittal dated April 4, 1978, problems associated with the removal of the Burnable Poison Rod Assemblies (BPRAs) and Orifice Rod Assemblies (ORAs) from the core after 87 effec-4 tive full power days of operation required transferring the BPRAs and ORAs through the spent fuel pool to the adjacent cask pit (see Amendment No, 11, June 16, 1978).
During this transfer contamination occurred ^
and the licensee provided revised information on June 22, 1973 regarding their April.4,1978" response to the staff's request for information dated March 8, 1978.
t Further evaluation will be made by Division of Operating Reactors and management responsibility will be carried out by Operating Reactors Branch No. 4.
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'***AS k Q %lay Q l,'7.,, g Q4 N cs ENCLOSURE 3
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REGULATORY GUIDES USED DURING k.
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THE LICENSING REVIEW
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FOR DAV:S-BESSE, UNIT 1
- 1. D I.54-
/,Q REFERENCE TO SER, SER REGULATORY GUIDE SUPPLEMENT NO.
1, AND NUMBER REGULATORY GUIDE TITLE APPLICABLE LICENSE AMENDEMENTS l.1 Net Positive Suction Head SER p. 6-3 for Emerhency Core Cooling and Containment Heat Removal System Pumps
, 1.4 Assumptions Used for SER p. 2-10 and Eval.uating the Potential Supplement No. 1 p. 2-3 Raciological Consequences of a Loss-of-Coolant Accident for Pressurized Water Reactors 1.6 Independence Between SER p. 8-1 and p. 8-3 Redunifant Standby (Onsite)
Power Sources and Between Their Distribution Systems 1.7 Control of Combustible Gas SER p. 6-5 and 6-6 Concentrations 1.8 Personnel Selection and SER p. 13-3 Training 1.9 Selection of Diesel Generator SER p. 8-1 Set Capacity for Standby Power Supplies 1.11 Instrument Lines Penetrattng/
SER p. 6-5 Primary Reactor Containment 1.12 Instrumentation for Earthquakes SER p. 3-17 1.13 Fuel Storage Facility Design SER p. 9-2, 9-3 and Bases 9-13 s
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ITEM REFERENCE 12.
Potential Equipment Failure SER, p. 8-2, Supplement Assolcated with Degraded Gri No. 1, p. 8-1, and Amendment g
No. 7 Safety Evaluation 13.
PWR Secondary Water SER p. 5-8 and TS 3/4 7-10 Chemistry Monitoring Requirements (3-37) hy i7 14.
QA Program for Operations SER, p. )i(-l to }3I6 4 (3-38)
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-i 15.
Qualifications of Radiation Necessary action completed Protection Managet- (3-39) prior to issuance of OL -
a April 22, 1977 4
16.
Hydraulic Snubbers (3-43)
TS 3/4 7-20 through 7-35 17.
Steam Generator Feedwater NRC generic letter on Flow Instability (SGFWFI)
SGFWFI sent to licensee on (3-44)
Septenber 6, 1977 which stated B&W steam generators have not had this problem 18.
Respiratory Protection Necessary action completed Program (3-42)%
prior to issuance of OL -
April 22, 1977 19.
Deletion Technical Specification Amendment No. 8 issued on Requirements for Annual Operating February 28, 1977 deleted Report the Technical Specification Requirements for an Annual Operating Report 20.
Interim Fire Technical Amendment No. 9 issued Specifications (except as on March 22, 1978 noted in Item 11, Enclosure 1) 21.
Fuel Rod Bow Effects (3-22)
Amendment No. 11 issued
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on June 16, 1978 22.
PWR Reactor Vessel Seal By letter dated March 24, Ring Missile 1978, the licenses stated that the cavity annulus seal ring is not left in place during normal operation s
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