ML19220B518
| ML19220B518 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 05/26/1978 |
| From: | Heltemes C Office of Nuclear Reactor Regulation |
| To: | Varga S Office of Nuclear Reactor Regulation |
| References | |
| TASK-TF, TASK-TMR NUDOCS 7904260496 | |
| Download: ML19220B518 (2) | |
Text
t D o e Ir e. M S o JISTR15UTION:
Cocket File QAB Projects CJHel temes, Chron. File DJSkovholt. DFM j ket N
'MAY 2 6 1978 RCDeYoung, DPM RMcDermott, QAB
.oc or. 0-320 M940.%NDUM FOR:
S. A. Yarga, Chief, Light Water Reactors Branch No. 4, Division of Project Management FROM:
C. J. Helteces, Jr., Chiaf, Quality Assurance Branch, Division of Project Management
SUBJECT:
THREE MILE ISLAND U.' FIT 2, DELETION OF PSEUDO EJECTED ROD TEST We have reviewed the infor nation provided in the licensee's May letter to NRR, and conclude that acceptable technical justification has 19, 1978 been proposed for deletion of the pseudo ejected rod worth test at 40%
Walt Brcoks of the CPB has also reviewed this information and power.
concurs in this decision.
E Neal sWed 57 AM. Cer' nd a
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C. J. Heltames, Jr., Chief x
Quality Assurance Branch Division of Project Managceent cc:
W. Brooks, CSS D. Fieno DSS J. Klingler, IE D. Haverkamp, IE, Reg. I H. S11rer, DPM B. Clayton, OPM PitLW^
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- 12. Section 3/4 7.1.5 (page B3/4 7-2) states that "The CPERABILITY of the main steam line isolation valves 2nsures that no more than one steam generator will blowdown in the event of a steam line rupture".
This statement is in error for the Three Mile Island Unit Number 2 design because of the slow acting MSIV's. Accordingly, we recommend that this section (3/4.7.1.5) be revised or removed completely from the technical specifications.
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