ML17139C416
| ML17139C416 | |
| Person / Time | |
|---|---|
| Site: | Susquehanna  |
| Issue date: | 05/17/1984 |
| From: | Youngblood B Office of Nuclear Reactor Regulation |
| To: | Curtis N PENNSYLVANIA POWER & LIGHT CO. |
| References | |
| NUDOCS 8405310275 | |
| Download: ML17139C416 (7) | |
Text
Docket No. 50-388 MAY Z7 iSS4 Mr. Norman W. Curtis Vice President Engineering 5 Construction - Nuclear Pennsylvania Power 5 Light Company 2 North Ninth Street Allentown, Pennsylvania 18101
Dear Mr. Curti s:
Subject:
Revisions to Startup Tests In a letter dated April 6, 1984, Pennsylvania Power 5 Light Company (PPSL) submitted proposed revisions to Section 14.2 of the FSAR covering the startup test program and requested NRC staff approval of these changes in accordance with License Condition 2.C.(5) of the Susquehanna Unit 2 license, NPF-22.
By letter dated May 1, 1984, the NRC staff approved the revision for Test ST-2.
Review of the remaining revision in the April 6, 1984 submittal has been com-pleted and a safety evaluation is enclosed.
The revisions to Tests ST-21, ST-25, ST-28, ST-32, ST-37, ST-39 and to FSAR Figure 14.2-5 contained in the April 6, 1984 submittal is hereby approved.
Sincerely, OBXQIKKSI(KKQBY:
B. J.
Youngblood, Chief Licensing Branch No.
1 Division of Licensing
Enclosure:
As stated cc:
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Norman.W. Curtis Vice President Engineering and Construction Pennsylvania Power
& Light Company 2 North Ninth Street Al 1 entown, Pennsyl vania 18101 cc:
Jay Silberg, Esq.
Shaw, Pittman, Potts
& Trowbridge 1800 M Street, N.
W.
Washington, D. C.,
20036 Edward M. Nagel, Esquire
'eneral Counsel and Secretary Pennsylvania Power
& Light Company 2 North Ninth Street Allentown, Pennsylvania 18101 Mr. William E. Barberich Nuclear Licensing Group Supervisor Pennsylvania Power
& Light Company 2 North Ninth Street Allentown, Pennsylvania 18101 Mr. G. Rhodes Resident Inspector P. 0.
Box 52 Shickshinny, Pennsylvania 18655 Gerald R. Schultz, Esq.
Susquehanna Environmental Advocates P. 0.
Box 1560 Wilkes-Barre, Pennsylvania 18703 Mr. E. B. Poser Project Engineer Bechtel Power Corporation P. 0.
Box 3965 San Francisco, California 94119 Ms. Colleen Ma~sh P. 0.
Box 538A, RD 84 Mountain Top, Pennsylvania 18707 Mr. Thomas J. Halligan Correspondent The Citizens Against Nuclear Dangers P. 0.
Box 5
- Scranto, Pennsylvania 18501 Mr. N.
D. Weiss Proiect Manager Mail Code 391 General Electric Company 175 Curtner Avenue San Jose, California 95125 Robert W. Adler, Esquire Office of Attorney General 505 Executive House P. 0.
Box 2357 Har risburg, Pennsylvania 17120 Dr. Judith H. Johnsrud Co-Director Environmental Coalition on Nuclear Power 433 Orlando Avenue State College, Pennsylvania 16801 Mr. Thomas M. Gerusky, Director Bureau of Radiation Protection Resources Commonwealth of Pennsylvania P. 0.
Box 2063 Harrisburg, Pennsyl vania 17120
SUPPLEMENTAL SAFETY EVALUATION REPORT SUS(UEHANNA STEAM ELECTRIC STATION (SSES)
UNIT 2:
14.0 INITIALTEST PROGRAM In a letter from N.
W. Curtis to A-. Schwencer dated April 6, 1984, the Pennsylvania Power and Light Company (PPSL) forwarded proposed revisions to Chapter FSAR 14.
These revisions were submitted for approval in accordance with the SSES Unit 2 Facility Operating Licensing NPF-22, Condition 2.C.5.
These revisions pertain to startup tests:
ST-21, Core Power-Void Mode Response; ST-25, Main Steam Isolation Valves; ST-28, Shutdown from Outside the Main Control Room; ST-32, Containment Atmosphere and Main Steam Tunnel Cooling; ST-37, Gaseous Radwaste System; and ST-39, Piping Vibration During Dynamic Transients.
In addition, revision of test conditions for several
These proposed revisions were reviewed and a discussion of each revision follows.
Item I ST-21, Core Power-Void Mode Response This change requests deleting the simulated failure of the pressure regulator.
The justification for this deletion is that step changes in pressure regulator set point, as also stipulated in the test procedure, are sufficient to demonstrate core response to pressure changes.
We find this modification to the Test ST-21 acceptable because the simulation of pressure regulator failure is also performed in Test ST-22, Pressure Regulator, at similar and other test points.
In addition, the vendor, GE, has recommended that for ST-21, Core Power-Void Mode Response, step changes in the pressure regulator are sufficient to meet the test objective.
Item 2 ST-25, Main Steam Isolation Valves The changes requested would a) modify the test objectives to clarify that this test is to demonstrate the maximum power at which a single valve closure can be made without a scram; b) modify test method description to clarify that all MSIVs are considered when demonstrating maximum power at which a
single valve closure can be made without a scram rather than just the fastest valve; and c) measuring a modified MSIV stroke time without delay time and revised acceptance criteria on MSIVs.
Clarifications a) and b) above are
, consistent with previous accepted test programs and are acceptable.
We find c) acceptable because
- 1) the delay time was measured during preoperation testing;
- 2) the delay time is electro-pneumatic and independent of valve conditions, and 3) the delay times were less than 0.5 seconds.
Item' ST-28, Shutdown from Outside the Main Control Room This change requests the insertion of the word scrammed" in the test objective.
This change'emoves the ambiguity of the word "shutdown" and reflects the commitment to scram the reactor as well as demonstrating the other aspects of reactor shutdown.
We find this change acceptable.
Item 4 ST-32, Containment Atmosphere and Main Steam Tunnel Cooling The changes requested reflect the fact that the cabling in the area has now been qualified to at least 185'F. 'herefore, the General Electric criteria on temperature remaining at or less than 185'F is the only necessary condition and local variations need not be maintained at or less than 167'F in this area.,
Since the cabling has been qualified for the higher (185'F) temperature, we find this change acceptable.
Item 5 ST-37, Gaseous Radwaste System The change requested revises the acceptance criteria to be consistent with the Technical Specifications.
We agree with the need for conformance between Technical Specifications and startup tests and, therefore, find this change acceptable.
Item 6
ST-39, Piping Vibration During Dynamic Transients The changes requested will a) clarify the test objective regarding which piping systems are to be tested; b) revise test method to reflect experience on startup of Unit I and c) modify level 2 acceptance criteria to reflect experience on startup of Unit 1.
The startup of Unit I indicated that only the main steamline inside containment and the reactor circulation system need be remotely monitored for dynamic performance.
Visual inspection of all other piping systems was sufficient.
Based on the experience of Unit I startup for justification, we find these changes acceptable.
Item 7 Figure 14.2-5, Test Condition Changes for Tests ST-7, ST-17 and ST-25 (a)
The change from test condition 3 to test condition 4 for test ST-7 was to minimize time natural circulation must be sustained (e.g
, the recirculation pumps are tripped).
Since it does not, affect the ability to meet the approved test objective, we find the change acceptable.
{b)
The ST-17 change provides more flexibilityof conditions for system thermal expansion tests.
Since expansion is not power level/flow dependent, we find this change acceptable.
(c)
On the basis that more useful results will be obtained by performing the Main Steam Isolation Valves Test, ST-25, at test condition 5 (higher power level and flow) rather than at test condition I, we find this test condition change acceptable.
In summary, we have reviewed the requested changes to the SSES Unit 2 Init'ial Test Program and find them acceptable.
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