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. 'p Washington Public Power Supply System A JOINT OPERATING AGENCY
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P. O. Som 968 3000 Gro. WASHINGTON WAY RicHLAND, WASHINGTON 99352 PHONEtSO9) 946 1618 f
June 28, 1976 1
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Docket-Nos. 50-460 7
50-513 1
Director of Nuclear Reactor Regulation N
ATTN: Mr. Olan D. Parr i
Light Water Reactors Project Branch No. 3 I
U. S. Nuclear-Regulatory Commission
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Washington, D. C.
20555 L
Subject:
WPPSS NUCLEAR PROJECTS NOS. 1 AND 4 f
MARK C FUEL SURVEILLANCE PROGRAM j
Reference:
Letter, John F. Stolz, NRC, to J. J. Stein, WPPSS, dated April 2, 1976.
Dear Mr. Parr:
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The reference requested that we inform the NRC of our plans for a fuel surveillance program for the WNP-1 Mark C fuel.
We commit to the per-formance of a fuel surveillance program should the WNP-1 plant be the lead plant to use the B&W Mark C fuel.
No commitment to a surveillance program is made for the case that WNP-1 is not the lead plant.
By October 1,1976, we will provide the NRC with a summary of the sur-veillance program.
The details of the program will be provided in the FSAR currently scheduled for submittal in September,1978.
Very truly yours, O#
D. L. RENBERGER Assistant Director Generation & Technology l
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[J U j,g JR Schmieder - UE&C - w/att.
EG Ward - B&W - w/att.
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Docket Nos. 50-460 50-513
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. WPPSS NUCLEAR PROJECTS NOS.1 Ami 4
, MARK C FUEL SURVEILLANCE PROGRAM STATEOFWASHINGTON)) sse
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D. L. RENBERGER, Being first duly sworn, deposes and says: That he is th'e Assistant Director, Generation and Technology, for the WASHINGTON PUBLIC POWER SUPPLY SYSTEM, the. applicant herein; that he is authorized to submit the foregoing on behalf of said applicant; that he has read the foregoing.
and knows the contents thereof; and believes the same to be true to the best of his kncwledge.
DATED 1976 dOd W D. L. RENBERGER
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On this day personally appeared before me D. L. RENBERGER to me known to be the individual who executed the foregoing instrument and acknowledged that he signed the same as his free act and deed for the uses and purposes therein mentioned.
GIVEN under my hand and seal this 8//lb day of 1976.
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Ltr. notarized 6-28-76...
Ltr. advising that by October 1,1976 a summary of the surveillance program will be provided i
and the details of the program will be provided in the FSAR scheduled for September 1978...
(' 1 Signed C'y.; Received)
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WPPSS Nuclear Proj. # 1 SAFETY FOR ACTION /INFOR.'.!ailON ENVIlto SAB 7-1-76 l ASSIGNED AD :
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Our fuel surveillance requirements for the Mark C (17 x 17) fuel have been p~ resented and explained in letters to the Babcock & Wilcox Licensing Manager from the staff's V. Stello on May 9, 1974, from V. Stello on August 14, 1974, from D. Ross on March 10, 1976, and from D. Ross on September 20, 1976.
Our letter of March 10, 1976, explicitly stated that post-irradation surveillance on the first two reactor cores using the Mark C, fuel was required.
j In a letter dated July 26, 1974, (J. Mallay to V. Stello) Babcock & Wilcox committed to a surveillance program to be performed, "as a minimum", on, fuel in the initial core loading of Mark C fuel.
In a letter dated June 28,1]76 (K. Suhrke to D..Ross) Babcock & Wilcox provided a description of the verification surveillance program and stated their intent that the program would be performed only on the first plant having a total core of the Mark C (17 x 17) fuel.
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i We are, therefore, requiring a fuel surveillance program
';.4 for the first two plants with Mark' C fuel.
The details of the surveillance program requirements are provided in reference 19 Briefly, the program will consist of a visual inspection of.all the peripheral rods in the initial-core fuel assemblies as they are discharged into the spent fuel pool., The visual inspection will include observations for cladding defects, fretting, rod bowing, corrosion and deposition and geometric i
f distortion.
If any anomalies are detected during the visual examination, further investigation will be performed, including, under unusual circumstances, destructive examination of a fuel assembly or individual fuel rods as required.
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4.2.1.5 Fuel Mechanical Design Evaluation Conclusion Subject to the following conditions:
(1) favorable results of the Mark C assembly development
- program, (2) the successful operation and subsequent PIE of the two Mark C demonstration assemblies in the,0conee 2 reactor, we conclude that there is reasonable assurance that the cladding integrity of BSAR-205 Mark C (17x17) fuel will be maintained, that significant amounts of radioactivity will not be released, and that neither accidents nor earthquake-induced loads will result in either an inability to cool the fuel or interference with controi rod insertion. Our conclusion is based on (1) analytical results, (2) operating experience with similar l
Maximum Internal Gas Pressure Limit -- The maximum internal gas pressure limit
,'is as follows: The internal pressura of the fuel rod shall be less than tha system operating pressure.
The basis for this is to ensure that compressive l
cladding stress exists at reactor temperature conditions for which hydride for-j mations may occur. The initial backfill gas pressure is considered in conjunc-I tion with fission gas release during burnup in establishing EOL internal fuel pin pressures.
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. Capacity for Fission Cas Release - The capacity of the fuel rod end voids to accept released fission gas is considered in the design of the fuel rod.
The capacity is based on worst-case conditions, i
Cycling and Fatigue Limits - Combinations of primary and secondary stresses are evaluated for cycle fatigue. The design limit is 90% of the material fa-l tigue life as determined by the O'Donnel & Langer design curve.
Evaluation of cyclic loading is based on conservatively high estimates of the number of cycles to be expected. 'These cycles are described in the Standard System Spec-
,ification for the reactor.
i Fuel Conductivity and Melting Point - The effect of accumulated burnup on fuel conductivity and melting point is considered in determining fuel swelling, in-l ternal pressure, dimensional changes, and fuel temperatures.
The basis for burnup effects is presented in detail in 4.4.2.8.4 and 4.4.2.10.3.
__,y Surveillance Testing - An irradiation surveillance program to complement the Mark C fuel assembly qualification test program, described in B&W topical re-port BAW-10097, is planned. The irradiation surveillance program incorporates precharacterization and post-irradiation visual and dimensional inspection of select fuel assemblics.,As_a minimum, this surveillance program will be car-ried out in the initial core loading of the 17 x 17 tuel.
Gutteuc usW plans are, however, to load the first 17 x 17 assemblies as lead demonstration assemblies approximately two years before the first full core loading.
4.2.1.1.3.
Faulted Conditions
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The fuel assembly is designed to ensure the safe shutdown and required cooling of the reactor core under faulted conditions, including the conditions of a saf e shutdown earthquake and LOCA, separately and combined.
The maximum de-flections are limited to ensure a coolabic core geometry during the combined SSE/LOCA.
For SSE, the maximum deflections are limited to ensure adequate 7
control rod insertion.
The methods of analysis and the design criteria for the fuel assembly generally comply with subsection NG of the ASME Code, Sec-tion Ill, " Nuclear Power Plant Components." Paragraph NG-3225 of this refer-ence, " Faulted Conditions," is used in establishing the allowable design loads and stress intensity factors.
4.2.1.2.
Design Description The complete core has 205 fuel assemblics arranged in a square lattice to ap-proximate the shape of a cylinder. All fuel assemblies are identical in me-chanical construction and are mechanically interchangeable in any core loca-tion.
All fuel assemblies will accept any control assembly.
The fuel assembly serial number, located on the top edge of the upper end fitting, is used with a core location map to ensure proper location and orientation of the fuel as-sembly.
4,2_3 Babcock & \\Vilcox r
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